ML042020082

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Units, 1 and 2, License Amendment Request: Incorporate Methodology References for the Implementation of PHOENIX-P, Anc, Paragon, and Zirconium Diboride Into the Technical Specifications
ML042020082
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/15/2004
From: Montgomery B
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML042020082 (44)
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Text

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 Constellation Energy Group July 15, 2004 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant UnitNos. I & 2; DocketNos. 50-317 & 50-318 License Amendment Request: Incorporate Methodology References for the Implementation of PHOENIX-P, ANC, PARAGON, and Zirconium Diboride into the Technical Specifications Pursuant to 10 CFR 50.90, the Calvert Cliffs Nuclear Power Plant, Inc. hereby requests an amendment to the Renewed Operating License Nos. DPR-53 and DPR-69 to add references to the list of approved core operating limits analytical methods in the Technical Specifications for Calvert Cliffs Unit Nos. I and 2.

The amendment would add the following references to the Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5.b that lists the analytical methods used to determine the core operating limits:

  • WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores"
  • WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery"
  • WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON" The significant hazards discussion and the technical basis for this proposed change are provided in Attachment (1). Marked up pages of the affected Technical Specification are provided in Attachment (2).

Attachment (3) provides fuel cycle specific comparisons of key physics parameters for past plant operation to support the applicability of the Westinghouse Nuclear Physics PHOENIX-P, ANC Code for Calvert Cliffs. The supplemental benchmarking data provided in Attachment (3) is for Unit 2. It has been determined that this supplemental information is representative for Unit I due to the close system and fuel management design similarities of both units. The Technical Specification Bases will be changed as appropriate to support this amendment.

Our Plant Operations and Safety Review Committee and Nuclear Safety Review Board have reviewed these proposed changes to the Technical Specifications and our determination of significant hazards.

Document Control Desk July 15, 2004 Page 2 They have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.

We request approval of this change by January 15, 2005 to support loading of a core designed with these methodologies during our Spring 2005 refueling outage. That outage is scheduled to begin in mid-February 2005.

Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, B ce S. ntgomery Manager, Ivert Cliffs Nuclear P wer Plant Engineering Services STATE OF MARYLAND

TO WIT:

COUNTY OF CALVERT 1,Bruce S. Montgomery, being duly sworn, state that I am Manager - Calvert Cliffs Nuclear Power Plant Engineering Services (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

C, Subscribed and sworn before me, a Notary Public in and 'for th e State of Ma and and County of 0______ , this J54k-day of , 2004.

WITNESS my Hand and Notarial Seal:

(/9 An _ A{,-

MELIa5t4lPhlit -_

NOTAP.I PUBUC STATE OF MARYLAND v My comrT1Ision Extires Novemrrier 1, 200y My Commission Expires: Il I I ha Date - .- - - -

BSM/DJM/bjd

Document Control Desk July 15, 2004 Page 3 Attachments: (1) Technical Basis and No Significant Hazards Consideration (2) Marked up Technical Specification Pages (3) Supplemental Information Describing the use of the Westinghouse PHOENIX-P, ANC Code Package for Calvert Cliffs Nuclear Power Plant cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR R. V. Guzman, NRC

ATTACHMENT (1)

TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION TABLE OF CONTENTS

1. DESCRIPTION
2. PROPOSED CHANGE
3. BACKGROUND
4. TECHNICAL ANALYSIS
5. NO SIGNIFICANT HAZARDS CONSIDERATION
6. ENVIRONMENTAL CONSIDERATION
7. PRECEDENCE
8. REFERENCES Calvert Cliffs Nuclear Power Plant, Inc.

July 15,2004

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION

1. DESCRIPTION This letter requests an amendment to Renewed Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2. The proposed change provides the necessary references in Technical Specification 5.6.5.b to reflect the use of the nuclear physics codes, PHOENIX-P, ANC and PARAGON, and for use of Zirconium Diboride (ZrB 2 ) integral burnable absorbers for Calvert Cliffs Nuclear Power Plant (CCNPP) Units I and 2.
2. PROPOSED CHANGE Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5.b lists the analytical methods used to determine the core operating limits. These analytical methods have been previously reviewed and approved by the Nuclear Regulatory Commission (NRC). The proposed license amendment request adds references to this Technical Specification list to reflect the use of the Westinghouse nuclear physics codes PHOENIX-P, ANC, PARAGON, and the use of Zirconium Diboride (ZrB 2 ) integral burnable absorbers.

This proposed change to Technical Specification 5.6.5.b is shown in Attachment (2). The same change will be made in the Core Operating Limits Report (COLR).

3. BACKGROUND Nuclear designs and the safety evaluations for reload cores for CCNPP have been performed using the Combustion Engineering-Asea Brown Boveri, Inc. (CE-ABB) reload methodology. The current methodology uses the CE-ABB nuclear physics code package DIT/ROCS (as approved in CENPD-266-P-A). This neutronics methodology is summarized in the Updated Final Safety Analysis Report, Section 3.4.9.

Calvert Cliffs Nuclear Power Plant plans to use the latest Westinghouse nuclear physics codes with the continued application of the CE-ABB reload and safety analysis methodology. This change in the nuclear physics codes is based on the integration of technologies arising from the consolidation of the former CE-ABB nuclear entities with Westinghouse Electric Company, LLC. The traditional Westinghouse neutronics methods have used the PHOENIX-P and ANC codes. These codes have previously been reviewed and approved by the NRC (References 1,2, and 3). PHOENIX-P is the Westinghouse transport code traditionally used to provide nuclear input data to the ANC Code. ANC is the Westinghouse diffusion theory code used to calculate core design parameters. Calvert Cliffs Nuclear Power Plant plans to use these codes for design calculations beginning with the reload that is scheduled for the Unit 2 2005 Refueling Outage.

The PARAGON computer code is a neutron transport code that can be used with a nuclear design code system or as a stand alone code. It is a direct replacement for the PHOENIX-P code. Calvert Cliffs plans to use the PARAGON/ANC physics codes for future reload calculations. The new PARAGON code has been reviewed and approved by the NRC (Reference 4). Calvert Cliffs agrees to all conditions in the NRC Safety Evaluation.

Calvert Cliffs Nuclear Power Plant currently uses Erbia as burnable neutron absorber, but plans to use Zirconium Diboride (ZrB 2 ) as a burnable absorber. The basis for this transition to ZrB 2 is economic considerations. The description of Integral Fuel Burnable Absorber (IFBA) was originally documented in Reference 6. Application of ZrB2 burnable absorbers for CE cores is addressed separately in Reference 5.

Technical Specification 5.6.5.b currently does not include references that reflect the use of the Westinghouse nuclear physics code package and does not include references that reflect the use of ZrB 2 1

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION integral burnable absorbers for the Calvert Cliffs reactor cores. The proposed Technical Specification change provides these references.

Attachment (2) contains a copy of the affected Technical Specification pages marked-up to show the proposed changes. Attachment (3) is supplemental information describing the use of the Westinghouse PHOENIX-P, ANC Code, including comparisons between core physics predictions and actual operating data for CCNPP. The information in Attachment (3) is submitted to further demonstrate the acceptability of the proposed changes.

4. TECHNICAL ANALYSIS PHOENIX-P and ANC The PHOENIX-P, ANC code package has been used extensively for the design of reload cores and for evaluation of reload safety for a wide range of core sizes and fuel array sizes encompassing both Westinghouse and Combustion Engineering (e.g., St. Lucie Unit 2, Millstone 3) designs. The capability and functionality of the PHOENIX-P, ANC code package is well known by the nuclear industry and is described in References 1, 2, and 3. These codes are used to confirm the values of neutronic parameters including selected cycle-specific reactor physics parameter limits in the COLR.

PHOENIX-P is a Westinghouse two-dimensional multi-group transport theory code that has been approved for calculating lattice physics parameters and determining neutronics input for a nodal code.

ANC is an approved Westinghouse three-dimensional two-group diffusion theory nodal code, which was approved for use with PHOENIX-P. The ANC code is based on coarse mesh nodal diffusion theory using nodal expansion method with coupled feedback.

Based on significant experience, including benchmarks on several CE type reactors, the application of the PHOENIX-P, ANC code package is expected to provide predictions of key core parameters that are essentially the same as those obtained with the current DIT/ROCS system. Benchmarking has shown that results from the PHOENIX-P, ANC code package are essentially the same as those obtained from the current DIT/ROCS system. Margins in nuclear design, based solely on the transition in nuclear physics methods, are expected to remain essentially unchanged. To further support the applicability of the PHOENIX-P, ANC code package for CCNPP, fuel cycle specific comparisons of key physics parameters for past plant operation are provided in Attachment (3).

Implementation of the PHOENIX-P, ANC code package requires no functional changes in the current reload methods. There are no changes in the safety analyses or safety methods. Changes are limited to those necessary to support effective and accurate electronic transfer of data from the PHOENIX-P, ANC code package to the downstream interface codes which are components of the current reload methodology.

The first reload cycle for application using the PHOENIX-P, ANC code package for CCNPP is planned for Unit 2 Fuel Cycle 16. The Fuel Cycle 16 core is scheduled to be loaded in the spring of 2005.

PARAGON The PARAGON computer code is a neutron transport code that can be used with a nuclear design code system and is a direct replacement of the PHOENIX-P code.

2

I ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION Topical Report WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"

confirms the qualifications of the code both as a stand alone transport code and as a substitute for the PHOENIX-P code as a nuclear data source for nodal codes. As part of the qualification process, the Topical Report includes a comparison of PARAGON predicted values to measured data from several plants. This comparison includes data from Calvert Cliffs measurements. Benchmarking has shown that results from the PARAGON/ANC code package are essentially the same as those obtained from the current PHOENIX-P ANC system. Topical Report WCAP-16045-P-A concludes that application of PARAGON, including CE fuel designs, does not result in any undesirable changes in predicted fuel performance or safety analysis results.

The other references in the COLR used to determine operating limits will remain applicable with the use of PARAGON. Future changes to the values of these operating limits are controlled by the 10 CFR 50.59 process, may only be developed using NRC approved methodologies, and must remain consistent with all applicable plant safety analysis limits addressed in the Updated Final Safety Analysis Report. The consequences of the design basis accidents will continue to be calculated using NRC accepted methodologies. Assumptions used in the safety analysis are not changed by the use of PARAGON.

Safety analysis acceptance criteria are not being altered by the use of PARAGON.

Zirconium Diboride Burnable Absorber Calvert Cliffs Nuclear Power Plant currently uses Erbia as an integral burnable neutron absorber, but plans to transition to Zirconium Diboride (ZrB2 ) as a burnable absorber. Zirconium Diboride is applied as very thin coating on the outer surface of the uranium dioxide fuel pellets prior to loading in the fuel rod.

The ZrB 2 coatings may be natural or enriched with the boron-10 isotope. Boron-10 has a large neutron absorbing cross-section that reduces the thermal flux and power in the region of the Zirconium Diboride.

Neutron absorption by boron-10 produces helium gas that is released into the fuel rod plenum. The effect of this helium production is taken into account in the Calvert Cliffs fuel rod design and safety evaluations using NRC approved methods. Boron-10 depletion and helium production related to ZrB2 are described in detail in the Zirconium Diboride Topical Report (Reference 5).

Application of ZrB 2 burnable absorbers for CE cores is addressed in WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs,"

(Reference 5). Topical Report WCAP-16072-P was approved by the NRC in May 2004, and includes a detailed description of the ZrB2 burnable absorbers and summarizes the evaluation of the effects of the ZrB 2 material characteristics on design and safety analyses. Calvert Cliffs agrees to all conditions and limitations in the Safety Evaluation Report that approved the Zirconium Diboride Topical.

Due to the rapid burnout of the Zirconium Diboride burnable absorbers, peak soluble boron concentration may occur after the beginning of the fuel cycle. This may result in the peak positive moderator temperature coefficient of reactivity occurring after the beginning of the fuel cycle. Staff training and procedures will be updated for this operating strategy.

Calvert Cliffs will confirm that the peak positive hot full power (HFP) moderator temperature coefficient (MTC) is within the Technical Specification limits at the highest Reactor Coolant System soluble boron concentration predicted during full power operation. The peak positive HFP MTC will be determined by adjusting the HFP MTC measured at beginning of cycle to the maximum HFP soluble boron concentration expected during the fuel cycle.

3

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION Summary The PHOENIX-P, ANC, PARAGON, and DIT/ROCS code packages are capable of accurately modeling the neutronic behavior of the current fuel designs and ZrB2 fuel. The first reload cycle for application using the Westinghouse ZrB2 for CCNPP is planned for Unit 2 Fuel Cycle 16, which is scheduled to be loaded in the first quarter of 2005.

5. NO SIGNIFICANT HAZARDS CONSIDERATION Calvert Cliffs Nuclear Power Plant is proposing an amendment to the Renewed Operating License that will add references to the list of approved topical reports used to generate Core Operating Limits Report (COLR) limiting values in Technical Specification 5.6.5.b. These references include the Westinghouse PARAGON, PHOENIX-P, and ANC codes, and the use of Zirconium Diboride as a burnable neutron absorber material. These Codes were previously approved by Nuclear Regulatory Commission. The proposed Technical Specification changes have been evaluated against the standards in 10 CFR 50.92 and have been determined to not involve a significant hazards consideration in the operation of the facility in accordance with the proposed amendment.
1. Operation of the facility in accordance wvith the proposed amendment would not involve a significant increasein the probabilityor consequences of an accidentpreviously evaluated.

The proposed amendment adds references to Technical Specification 5.6.5.b. This Technical Specification lists methods that are used to determine core operating limits. These proposed additional references will allow the use of the Westinghouse nuclear physics codes and a burnable neutron absorber material at Calvert Cliffs Nuclear Power Plant.

These proposed additional references will allow the use of the Westinghouse nuclear physics codes PARAGON, PHOENIX-P, and ANC. These Westinghouse codes will be used for the design of reload cores and for safety evaluation of reload cores. Benchmarking has shown that results from these nuclear physics codes are essentially the same as those obtained from the current DIT/ROCS code systems. These codes will not increase the probability or consequences of an accident because plant systems will not be operated outside of design limits, no different equipment will be operated, and system interfaces will not change.

The use of these computer codes will not increase the consequences of an accident because Limiting Conditions for Operation (LCOs) will continue to restrict operation to within the regions that provide acceptable results, and Reactor Protective System (RPS) trip setpoints will restrict plant transients so that the consequences of accidents will be acceptable. Also, the consequences of the accidents will be calculated using NRC accepted methodologies.

These proposed additional references to Technical Specification 5.6.5.b will allow the use of the burnable neutron absorber material Zirconium Diboride. Zirconium Diboride absorbs neutrons, which reduces the thermal flux and power in the region with the Zirconium Diboride. Neutron absorption by Zirconium Diboride produces helium gas that is released into the fuel rod plenum.

The effect of this helium production is taken into account in the fuel design and safety evaluations using codes reviewed and approved by the Nuclear Regulatory Commission.

Implementation of Zirconium Diboride may result in the peak most positive moderator temperature coefficient occurring after beginning of cycle. The core burnup characteristic is well understood as a result of extensive industry experience. Positive moderator temperature coefficient at the beginning of cycle is also within operational experience at Calvert Cliffs and as such, do not represent a significant change in the operation of the plant.

4

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION The proposed additional Technical Specification references are not accident initiators. The assumed accident initiators are not changed by the introduction of proposed additional Technical Specification references. Therefore, operation of the facility in accordance with the proposed amendment will not involve a significant increase in the probability of an accident previously evaluated.

The use of the proposed methods will not significantly impact the fission product inventory and transport assumptions in the current licensing basis analyses. Therefore, the radiological consequences of an accident previously evaluated will not increase.

The use of the proposed methods wvill not increase the consequences of an accident because Limiting Conditions for Operation will continue to restrict operation to within the regions that provide acceptable results, and Reactor Protective System trip setpoints will restrict plant transients so that the consequences of accidents will not exceed the safety analysis acceptance criteria.

Therefore, the proposed Technical Specification changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Operationof thefacility in accordance iwith the proposedamendment would not createthe possibility of a new'or different kind ofaccidentfroin any accidentpreviously evaluated These proposed additional references will allow the use of the *Vestinghouse nuclear physics codes PARAGON, PHOENIX-P, and ANC. These codes will be used to confirm the values of selected cycle-specific reactor physics parameter limits from the Technical Specifications and the Core Operating Limits Report. These codes will not change the physical plant or the modes of operation. Benchmarking has shown that results from these codes are essentially the same as those optioned from the current DIT/ROCS code package. The plant systems will not be operated outside of design limits, no different equipment will be operated, and system interfaces will not change. This code package will not create a new or different accident from those previously evaluated.

The proposed amendment also adds the Zirconium Diboride burnable absorber topical report to the Technical Specification list of the approved topical reports used to generate the values in the Core Operating Limits Report. With this burnable absorber, the plant systems will not operate outside of design limits, no different equipment will be operated, and system interfaces will not change. This burnable absorber will not create a new or different accident from those previously evaluated.

Therefore, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Operation of the facility in accordance with the proposed amendment would not involve a signifcant reduction in a margin of safety.

Safety limits ensure that specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients, and anticipated operational occurrences. All fuel limits and design criteria will be met based on the approved methodologies defined in the topical reports. The RPS in combination with all LCOs, will continue to prevent any anticipated combination of transient conditions for Reactor Coolant System temperature, pressure, and thermal power level that would result in a violation of the safety limits.

5

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION The reload safety analyses determine the LCOs settings and RPS setpoints that establish the initial conditions and trip setpoints. These conditions and setpoints ensure that the Design Basis Events (postulated accidents and anticipated operational occurrences) analyzed in the Updated Final Safety Analysis Report produced acceptable results.

The proposed amendment adds references to Technical Specification 5.6.5.b. This Technical Specification lists methods that are used to determine core operating limits. These proposed additional references will allow the use of the Westinghouse computer codes, PARAGON, PHOENIX-P, and ANC, and a burnable neutron absorber material Zirconium Diboride at Calvert Cliffs Nuclear Power Plant. These references were previously reviewed and approved by Nuclear Regulatory Commission.

Therefore, the proposed changes will not involve a significant reduction in the margin of safety.

Based on the above evaluations, Calvert Cliffs Nuclear Power Plant concludes that the use of the Westinghouse computer codes PARAGON, PHOENIX-P, and ANC and a burnable neutron absorber material Zirconium Diboride presents no significant hazards consideration under the standards set forth in 10 CFR 50.92. A finding by the Nuclear Regulatory Commission of no significant hazards consideration is justified.

6. ENVIRONMENTAL CONSIDERATION We have determined that operation with the proposed amendment would not result in any significant change in the types, or significant increases in the amounts, of any effluents that may be released offsite, nor would it result in any significant increase in individual or cumulative occupational radiation exposure.

Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed amendment.

7. PRECEDENCE The Westinghouse PHOENIX-P, ANC code package has been used extensively for the design of reload cores and for evaluation of reload safety. This has been performed for a wide range of core sizes and fuel array sizes encompassing typical designs for Westinghouse, Combustion Engineering (St. Lucie Unit 2, Millstone 3), Framatome (Koeberg), and VVER (Temelin) designs. The capabilities and functionality of the PHOENIX-P, ANC technology is well known by the NRC and the nuclear industry.

Zirconium Diboride has been used extensively for a neutron burnable absorber for a wide range of core designs. Its use has been previously approved by the NRC for generic use and for St. Lucie Unit 2 (1998), a CE reactor design.

8. REFERENCES
1. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988
2. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986
3. WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code:

Enhancements to ANC Rod Power Recovery," April 1989

4. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON" 6

ATTACHMENT (1)

TECHNICAL BASIS AND SIGNIFICANT HAZARDS CONSIDERATION

5. WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs"
6. WCAP- I 0444-P-A, "Reference Core Report Vantage 5 Assembly," September 1985 7

ATTACHMENT (2)

MARKED UP TECHNICAL SPECIFICATION PAGES 5.6-8 Calvcrt Cliffs Nuclear Power Plant, Inc.

July 15, 2004

Reporting Requirements 5.6 5.6 Reporting Requirements ii. CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2" 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 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" 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)
43. CENPD-387-P-A, "ABB Critical Heat Flux Correlations for PWR Fuel"
44. CENPD-199-P, Supplement 2-P-A, Appendix A, "CE Setpoint Methodology"
45. CENPD-404-P-A, "Implementation of ZIRLOT` Cladding Material in CE Nuclear Power Fuel Assembly Designs"
46. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model"
47. CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model"
c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as CALVERT CLIFFS - UNIT 1 5.6-8 Amendment No. 259 CALVERT CLIFFS - UNIT 2 Amendment No. 236

INSERT A

48. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores"
49. WCAP-1 0965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code"
50. WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery"
51. WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs"
52. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON"

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P, ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT Calvert Cliffs Nuclear Power Plant, Inc.

July 15, 2004

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT ABSTRACT This document provides benchmarking data for the Westinghouse PHOENIX-P, ANC code. The computer programs used are part of the PHOENIX-P, ANC code package (PHOENIX-P, ANC) and are obtained from Westinghouse Electric Company, LLC. The results of these calculations are compared to operating data from Calvert Cliffs Nuclear Power Plant Unit 2. Both Calvert Cliffs reactors are designed to be essentially identical: both reactor cores consist of 217 assemblies of the Combustion Engineering, Inc. (CE) 14x14 design. Therefore, the results of these comparisons are applicable to both Calvert Cliffs reactors. These comparisons further demonstrate the applicability of the PHOENIX-P, ANC codes to perform reload design calculations for Calvert Cliffs Nuclear Power Plant, Units 1 and 2.

1

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE OF CONTENTS SECTION PAGE

1. INTRODUCTION AND CONCLUSIONS .................................................................. 4
2. PHYSICS MODEL VERIFICATION FOR CALVERT CLIFFS NUCLEAR POWER PLANT .................................... 4 2.1 CYCLE DESCRIPTIONS .................................... 4 2.2 -ZERO POWER PHYSICS TESTS ..... 4............................

2.2.1 CRITICAL BORON CONCENTRATION ..................................... 5 2.2.2 MODERATOR TEMPERATURE COEFFICIENT .................................... 5 2.2.3 CONTROL ROD WORTH ..................................... 5 2.2.4 DIFFERENTIAL BORON WORTH ..... 5............................

2.3 POWER OPERATION .................................... 5 2.3.1 BORON LETDOWN CURVES ..................................... 5 2.3.2 POWER PEAKING FACTORS ..................................... 5 2.3.3 AXIAL POWER DISTRIBUTIONS ..... 6............................

2.3.4 RELATIVE POWER DISTRIBUTIONS .................................... 6 2.4

SUMMARY

.................................... 6 LIST OF TABLES TABLE PAGE 2.2-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 HZP Critical Boron Concentration Comparison Between Measurement and Prediction .7 2.2-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 HZP Moderator Temperature Coefficient Comparison Between Measurement and Prediction .7 2.2-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 Control Rod Worth Comparison Between Measurement and Prediction .8 2.2-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 HZP Differential Boron Worth Comparison Between Measurement and Prediction .9 2.3-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Boron Letdown Comparison Between Measurement and Prediction .10 2.3-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Boron Letdown Comparison Between Measurement and Prediction .11 2.3-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Fxy and Fr Comparison Between Measurement and Prediction .12 2.3-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 F1 yand Fr Comparison Between Measurement and Prediction .13 2

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT LIST OF FIGURES FIGURE PAGE 2.1-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Core Loading Pattern ............................... 14 2.1-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Core Loading Pattern ............................... 15 2.3-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Boron Letdown Comparison Between Measurement and Prediction ............................................................... 16 2.3-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Boron Letdown Comparison Between Measurement and Prediction ............................................................... 17 2.3-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Between Plant Measurement and ANC - 274 MWD/MTU ................................... 18 2.3-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Between Plant Measurement and ANC - 9,954 MWD/MTU ................................ 19 2.3-5 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Between Plant Measurement and ANC - 20,612 MWD/MTU ................................................... 20 2.3-6 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Between Plant Measurement and ANC - 432 MWD/MTU ........................................................ 21 2.3-7 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Between Plant Measurement and ANC - 8,999 MWD/MTU ................................ 22 2.3-8 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Between Plant Measurement and ANC - 19,721 MWD/MTU .............................. 23 2.3-9 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC - 274 MWD/MTU ................................... 24 2.3-10 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC - 9,954 MWD/MTU ................................ 25 2.3-11 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC - 20,828 MWD/MTU .............................. 26 2.3-12 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC -219 MWD/MTU ................................... 27 2.3-13 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC - 8,999 MWD/MTU ................................ 28 2.3-14 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC - 19,721 MWD/MTU .............................. 29 3

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT

1. INTRODUCTION AND CONCLUSIONS This report provides comparisons between predictions and operating data as a further demonstration of the applicability of the PHOENIX-P, ANC code package to perform reload design calculations for Calvert Cliffs Nuclear Power Plant.

Design calculations have been performed with the PHOENIX-P, ANC codes for Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14. These results are compared to actual plant operating data. Both Calvert Cliffs reactors are designed to be essentially identical: both reactor cores consist of 217 assemblies of the CE 14x14 design. Therefore, the results of these comparisons are applicable to both Calvert Cliffs' reactors. These comparisons further demonstrate the applicability of the PHOENIX-P, ANC codes to perform reload design calculations for Calvert Cliffs Nuclear Power Plant Units 1 and 2.

All methods used to generate the results detailed in this report (computer programs, model development, and data processing) are standard licensed methods used by Westinghouse Electric Company, LLC.

The results from these comparisons further demonstrate the applicability of the PHOENIX-P, ANC code package to perform reload design calculations for Calvert Cliffs Nuclear Power Plant.

2. PHYSICS MODEL VERIFICATION FOR CALVERT CLIFFS NUCLEAR POWVER PLANT Core physics model verification for Calvert Cliffs Nuclear Power Plant includes comparisons between measurements and predictions for Cycles 13 and 14. Calvert Cliffs Nuclear Power Plant Unit 2 is currently in its 15th cycle of operation. In this section, predictions made using the PHOENIX-P, ANC code package are compared to zero power physics test measurements and at power operating data. As stated in Section 1, the methods employed to generate the predictions reported in this section are standard licensing methods used by Westinghouse Electric Company, LLC.

Calvert Cliffs Nuclear Power Plant is a CE reactor with a thermal rating of 2700 MW. The core consists of 217 assemblies of the CE 14x14 design.

2.1 CYCLE DESCRIPTIONS Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 began operation in May 1999 and shutdown in March 2001 after a 21.1 GWd/MT cycle. Erbia was used for burnable absorber material. The core loading pattern for Cycle 13 including a description of the fresh fuel and the locations of control rods are shown in Figure 2.1-1.

Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 began operation in May 2001 and shutdown in February 2003 after a 19.8 GWd/MT cycle. Erbia was used for burnable absorber material. The core loading pattern for Cycle 14 including a description of the fresh fuel and the locations of control rods are shown in Figure 2.1-2.

2.2 ZERO POWER PHYSICS TESTS After each refueling, startup physics tests are conducted to verify that the nuclear characteristics of the core are consistent with design predictions.

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT While the reactor is maintained at hot zero power (HZP) conditions, the following physics parameters are measured:

  • Critical Boron Concentration,
  • Moderator Temperature Coefficient,
  • Differential Boron Worth.

2.2.1 CRITICAL BORON CONCENTRATION Table 2.2-1 provides the comparisons between HZP critical boron concentration measurements and predictions for Cycles 13 and 14. The values represent all rods out (ARO). As shown, excellent agreement is demonstrated for each case.

2.2.2 MODERATOR TEMPERATURE COEFFICIENT Table 2.2-2 provides the comparisons between HZP Moderator Temperature Coefficient measurements and predictions for Cycles 13 and 14. Again, excellent agreement is demonstrated.

2.2.3 CONTROL ROD WORTH Table 2.2-3 provides the Control Rod Worth comparisons between measurements and predictions for Cycles 13 and 14. The predicted rod worths are calculated at the exact conditions of the measurement. Excellent agreement is observed between measured and predicted integral worth.

2.2.4 DIFFERENTIAL BORON WORTH Table 2.2-4 provides the differential boron worth comparisons between measurements and predictions for Cycles 13 and 14. Both the measured and predicted values are obtained using the worth of the Regulating Banks in pcm divided by the change in boron concentration from ARO to Regulating Banks inserted.

2.3 POWER OPERATION 2.3.1 BORON LETDOWN CURVES Reactor Coolant System boron concentrations are measured at the plant. Critical boron concentrations are measured at, or very close, to hot full power, ARO, equilibrium xenon and samarium conditions. These measurements are compared to the predicted boron letdown curves for Cycles 13 and 14 in Figures 2.3-1 and 2.3-2. The predicted curves are obtained from design depletions with the three-dimensional ANC model. Tables 2.3-1 and 2.3-2 show the difference in ppm between measurement and ANC at various cycle exposures. The difference between measured and predicted critical boron concentration for both cycles is quite good.

2.3.2 POWER PEAKING FACTORS Power peaking factors Fr and F. are measured with the core monitoring code CECOR using incore detectors. These peaking factors are compared to predicted peaking factors in Tables2.3-3 and 2.3-4. The predicted values are obtained from three-dimensional ANC calculations performed for core conditions similar to those at the time of the measurement.

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT Overall, the comparisons show excellent agreement between measured and predicted peaking factors.

2.33 AXIAL POWER DISTRIBUTIONS Measured core average axial power distributions for Beginning-of-Cycle, Middle-of-Cycle, and End-of-Cycle obtained with the core monitoring code CECOR using incore detectors. These axial power distributions are compared to predicted axial distributions in Figures 2.3-3 through 2.3-8. The predicted distributions are obtained from three-dimensional ANC calculations performed for core conditions similar to those at the time of the measurement. Overall, the comparisons show excellent agreement betveen measured and predicted axial power distributions.

2.3.4 RELATIVE POWER DISTRIBUTIONS Relative power distributions are measured with the core monitoring code CECOR using incore detectors. The measured power distributions for Beginning-of-Cycle, Middle-of-Cycle, and End-of-Cycle are compared to predicted power distributions in Figures 2.3-9 through 2.3-14.

The predicted distributions are obtained from three-dimensional ANC calculations performed for core conditions similar to those at the time of the measurement. The comparisons show excellent agreement.

2.4

SUMMARY

In this section, predictions made using the PHOENIX-P, ANC code package are compared to zero power physics test measurements and at power operating data from Calvert Cliffs Nuclear Power Plant. In all cases, the predictions agree well with the measurements and produce results that are essentially the same as the current DIT/ROCS system. The agreement between the predictions and the measurements reported here further demonstrates the applicability of the PHOENIX-P, ANC code package to perform reload design calculations for Calvert Cliffs Nuclear Power Plant.

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE 2.2-1 Calvert Cliffs Nuclear Powcr Plant Unit 2 Cycles 13 and 14 HZP Critical Boron Concentration Comparison Between Measurement and Prediction BORON CONCENTRATION (PPM)

MEASURED PREDICTED DIFF.

CYCLE CONFIGURATION (M) (P) (M-P) 13 ARO 2118 2117 1 14 ARO 2054 2055 -1 TABLE 2.2-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 HZP Moderator Temperature Coefficient Comparison Between Measurement and Prediction MODERATOR TEMPERATURE COEFFICIENT (PCMP/F)

MEASURED PREDICTED DIFF.

CYCLE CONFIGURATION (M) (P) (M-P) 13 ARO 5.55 5.51 0.04 14 ARO 4.75 4.82 -0.07 7

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE 2.2-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 Control Rod Worth Comparison Between Measurement and Prediction CONTROL ROD WORTH (PCM)

CEA MEASURED PREDICTED DIFFERENCE CYCLE GROUP (M) (P) (%)

(MJP- 1) *100 13 5 290 271 7.0 4 633 641 -1.2 3 907 904 0.3 2 1000 1023 -2.2 1 368 347 6.1 Total 3198 3186 0.4 14 5 350 327 7.0 4 632 650 -2.8 3 853 893 -4.5 2 843 905 -6.9 1 605 582 4.0 Total 3283 3357 -2.2 8

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE 2.2-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycles 13 and 14 HZP Differential Boron Worth Comparison Between Measurement and Prediction I DIFFERENTIAL BORON WORTH (PCM/PPM)

MEASURED PREDICTED DIFFERENCE CYCLE CONFIGURATION (M) (P) (%)

(M/P- 1) *100% l AVERAGE OVER 77 13 REGULATING BANKS -7.42 -. 1 -3.8 l AVERAGE OVER7 14 REGULATING BANKS -7.83 -7.76 0.9I 9

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE 23-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Boron Letdown Comparison Bet ween Measurement and Prediction HFP BORON LETDOWN (PPM)

EXPOSURE 1 MEASURED l PREDICTED DIFFERENCE (MWD/MTU__(P) (M-P) 206 1614 1617 -3 522 1591 1596 -5 997 1571 1567 4 1247 1566 1559 7 2350 1523 1517 6 3227 1474 1472 2 4113 1441 1418 23 5252 1352 1342 10 6109 1291 1281 10 6773 1236 1226 10 8100 1128 1116 12 9416 973 960 13 10843 859 846 13 11574 801 789 12 12905 691 683 8 14139 588 572 16 15341 476 464 12 16230 401 387 14 17340 304 288 16 18229 223 204 19 19342 124 104 20 20291 38 17 21 20639 5 -15 20 10

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT TABLE 2.3-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Boron Letdown Comparison Between Measurement and Prediction HFP BORON LETDOWN (PPM)

EXPOSURE MEASURED l PREDICTED DIFFERENCE (MWD/MTU) (M) l (P) (M-P) 198 1548 1561 -13 510 1523 1538 -15 884 1512 1522 -10 1942 1473 1472 1 2815 1425 1426 -1 3907 1363 1343 20 4778 1304 1297 7 5596 1225 1218 7 6463 1162 1154 8 7552 1089 1074 15 8797 987 970 17 10165 874 858 16 11285 777 764 13 12342 689 672 17 13339 603 584 19 14300 507 488 19 15164 423 403 20 16315 317 301 16 17126 243 226 17 17979 166 149 17 18912 80 65 15 19774 3 -15 18 11

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT Table 2.3-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Fxy and Fr Comparison Between Measurement and Prediction Burnup l Measured Measured l Predicted l Predicted l (MWD/MTU) Fxy l Fr l Fxy l Fr l MP Fxy l M-P Fr 1000 1.53 1.51 1.50 1.50 0.03 0.01 1999 1.54 1.52 1.51 1.51 0.03 0.01 3001 1.55 1.53 1.52 1.51 0.03 0.02 3999 1.56 1.53 1.52 1.52 0.04 0.01 6001 1.56 1.54 1.52 1.52 0.04 0.02 8001 1.56 1.54 1.51 1.51 0.05 0.03 10000 1.55 1.53 1.50 1.49 0.05 0.04 12000 1.53 1.52 1.48 1.47 0.05 0.05 14000 1.51 1.50 1.46 1.45 0.05 0.05 16001 1.50 1.48 1.44 1.43 0.06 0.05 17999 1.48 1.46 1.42 1.41 0.06 0.05 20001 1.45 1.44 1.40 1.40 0.05 0.04 21002 1.44 1.43 1.39 1.39 0.05 0.04 12

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT Table 2.3-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Fxy and Fr Comparison Between Measurement and Prediction l Burnup Measured Measured Predicted Predicted l l MWD/MTU Fxy Fr F1 J Fr M-P Fxy M-P Fr 999 1.57 1.48 1.54 1.47 0.03 0.01 2001 1.52 1.45 1.50 1.49 0.02 -0.04 3000 1.48 1.46 1.49 1.49 -0.01 -0.03 3999 1.49 1.47 1.49 1.49 0.00 -0.02 6000 1.50 1.48 1.49 1.49 0.01 -0.01 8001 1.50 1.48 1.48 1.48 0.02 0.00 10001 1.50 1.48 1.48 1.47 0.02 0.01 11999 1.50 1.48 1.48 1.47 0.02 0.01 14000 1.50 1.48 1.47 1.46 0.03 0.02 15999 1.49 1.47 1.46 1.45 0.03 0.02 18000 1.48 1.46 1.44 1.44 0.04 0.02 19782 1.47 1.45 1.43 1.42 0.04 0.03 13

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR PONVER PLANT FIGURE 2.1-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Core Loading Pattern C2JI Ca C2R3 C2P2 C2R3 Ca CP C2R2 5 4 5 C2N2 C2 C2R2 C2 C2R3 C2P2 C2R2 C2 C2R2 B 3 1 C21 C2R3 C2P2 Car CM2 CR3 C2P2 CR2 Cro 4 B 2 C CP2 CR3 CP2 C2R3 CP2 CR3 Cr0 ORO A C C2R3 CM2 C2R3 CM2 CR3 C210 CR1 ONO 2 A CMr CR2 Ca2 CR3 CMo CR1 ONO 3 A 4 4- + 4 CPI CP2 C2R2 CMo CMR ONO 5 C A CR2 CR2 CPO CRO CN4 1 C Legend BatchoID CN2 C2K2 ICEAI GrupID FUEL INVENTORY:

ENRICH No. of No. of No. of REGID s /o U-235 Assem. Erbia BA's C2J1 3.40 5 C2M2 4.08 4 12 C2NO 4.46 12 C2N2 4.46 8 20 C2N4 4.46 4 44 C2PO 4.47 24 C2PM 4.47 8 20 C2P2 4.47 60 44 CR0 4.47 8 C2R1 4.47 12 20 C2R2 4.46 32 44 C2R3 4.47 40 68 14

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.1-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Core Loading Pattern CILI C2R2 C2S2 C2R3 C2S3 C2R3 C2R2 C2S1 54 _ _ _ _ _ _ _ 5 _ CPO C2R2 C2S2 C2R2 Cs3 C2R3 CS2 C2R2 CMs B 3 1 CPI C2S2 C2R2 CMR C2R3 CS3 C2R3 Cs2 ORO 4 B _ _ _ 2 _ _ _ C C2R3 C2S3 CR3 C2S3 C2R3 C2S3 CR C2SO

__ _ _ _ _ _ _ _ _ _ _ _ _ _ A _ _ _ _ C C2S3 C2R3 C2S3 C2R3 C2S3 C2R2 C2S1 C2P0

___ __ __ __ _ _ _ _ 2 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ A CR3 Cs2 C2R3 CS3 C2R2 CMS CPO 3 A 4 1- t t CR2 CR2 C2S2 CR CMS C2PO S C A CS1 CS1 CRO aOs Cao 1 C Legend Batch ID C~PO C2P CEA Group ID FUEL INVENTORY:

ENRICH No. of No. of REGID W/o U-235 Assem. Erbia CILI 3.40 I C2PO 4.47 24 C2PM 4.47 8 20 C2RO 4.47 8 C2RM 4.47 12 20 C2R2 4.46 32 44 C2R3 4.47 40 68 CSO 4.26 8 CMS 4.27 24 20 C2S2 4.27 24 44 C2S3 4.27 36 68 15

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-1 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Boron Letdown Comparison Between Measurement and Prediction 1800, - ,, . , , ,, ,, , , , , ,i.......

1'00 mmI imn irurnm~timmrrrvrr 11Thrn-rnm

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+..Measured 12000 t X X iredictes PX0 I

800.0+ W 111 L 11 11I11IT1111111111111 6 0. TlT I1LLLJT ]IN r 400- t[ 1 ~ I0t~ 8 W 3

. . . . . . . . . . . . . . . . . . .I . . . . . . . . . . . . .

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_III O. I 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 22000 Cycle Burnup (MWDIMTU) 16

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-2 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Boron Letdown Comparison Betwveen Measurement and Prediction 10 -u 1600 1 1 1 1 1 1 l' ' l ! I 1 1! 1l '1 1!

l l ! ! 'I I' ' I ' ' I'I

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400 _ _. _ _ _I_ . I , . I I I I I . I I I 200 0 I ilTFIiThI mTF 11Th 1TTT TITI1 TTITiThT-I T 0 2000 4000 6000 8000 10000 12000 14000 16000 18000 -4 20000 Cycle Bumup (MWDIMTU) 17

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-3 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Bet-ween Plant Measurement and ANC - 274 MNVD/MTU Predicted A Measured Al2 1 I 1 '

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-4 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Between Plant Measurement and ANC - 9,954 MWDtMTU

- Predicted & Measured 1.2, 0.72 Io _____I I -I I f t l^  ? I I I__

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ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-5 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Axial Power Distribution Comparison Between Plant Measurement and ANC - 20,612 MWD/MTU l- Predicted a Measured 12T I l __T

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SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-6 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Between Plant Measurement and ANC -432 MWD/MTU

- Predicted A Measured 1.2 1.1 - . - - . -

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Core Height (%)

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ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR PONVER PLANT FIGURE 23-7 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Between Plant Measurement and ANC - 8,999 MWD/MTU 1.20 . -.- -

I-Predicted ^ Measured T

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rTI TT TT I r__T 0.0 10.0 2U.U 3U.0 40.0 MU.0 60.0 70.0 8u.0 So.o 100.0 Core HeIght (*/)

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ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-8 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Axial Power Distribution Comparison Betwecn Plant Measurement and ANC - 19,721 MWD/MTU

-Predidted & Measured

.. _X I T I l l - l -_

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ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-9 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC -274 MNWD/MTU Legend: ANC Predicted Assembly Average Power Measured Data Cycle 13 BOC

% Difference 0.625 0.973 1.296 1.103 1.371 1.124 1.053 0.951 0.598 0.954 1.268 1.102 1.372 1.110 1.051 0.934 4.515 1.992 2.208 0.091 -0.073 1.261 0.190 1.820 0.271 0.248 0.973 1.269 1.079 1.321 1.140 1.397 1.023 0.931 9.274 0.951 1.233 1.048 1.320 1.130 1.409 1.024 0.927 2.313 2.920 2.958 0.076 0.885 -0.852 -0.098 0.431 .0.191 0.174 1.296 1.076 1.070 1.063 1.356 1.139 1.297 0.811 9.770 1.289 1.033 1.051 1.049 1.366 1.144 1.318 0.813 0.543 4.163 1.808 1.335 -0.732 -0.437 -1.593 -0.246 1.103 1.316 1.059 1.314 1.113 1.340 1.074 0.805 1.099 1.311 1.045 1.324 1.117 1.362 1.080 0.803 0.364 0.381 1.340 -0.755 -0.358 -1.615 -0.556 0.249 1.371 1.132 1.350 1.110 1.329 1.090 1.004 0.315 1.387 1.126 1.361 1.118 1.378 1.103 1.011 0.291

-1.154 0.533 -0.808 -0.716 -3.556 -1.179 -0.692 8.247 1.124 1.390 1.133 1.334 1.087 1.030 0.393 1.129 1.408 1.136 1.356 1.100 1.040 0.374

-0.443 -1.278 -0.264 -1.622 -1.182 -0.962 5.080 4 4 4. 4. 4.

1.053 1.018 1.290 1.066 0.994 0.391 1.065 1.022 1.312 1.071 0.998 0.365

-1.127 -0.391 -1.677 -0.467 -0.401 7.123 0.951 0.930 0.808 0.797 0.303 0.954 0.933 0.812 0.794 0.281

-0.314 -0.322 -0.493 0.378 7.829 0.274 0.198 0.253 0.192 8.300 3.125 24

i ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-PIANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-10 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC - 9,954 MWD/MTU Legend: ANC Predicted Assembly Average Power Measured Data Cycle 13 MOC

% Difference 0.690 0.997 1.341 1.097 1.377 1.078 1.041 1.040 0.671 0.971 1.335 1.093 1.382 1.053 1.022 1.035 2.832 2.678 0.449 0.366 -0.362 2.374 1.859 0.483 0.331 0.303 0.997 1.293 1.073 1.351 1.108 1.355 1.006 1.008 9.241 0.972 1.282 1.047 1.356 1.092 1.363 0.989 1.002 2.572 0.858 2.483 -0.369 1.465 -0.587 1.719 0.599 0.239 0.211 1.341 1.071 1.055 1.055 1.369 1.093 1.271 0.818 13.270 1.349 1.049 1.035 1.037 1.378 1.080 1.288 0.810

-0.593 2.097 1.932 1.736 -0.653 1.204 -1.320 0.988 1.097 1.348 1.053 1.344 1.094 1.333 1.017 0.790 1.091 1.355 1.036 1.354 1.085 1.355 1.018 0.790 0.550 -0.517 1.641 -0.739 0.829 -1.624 -0.098 0.000 1.377 1.103 1.367 1.093 1.335 1.037 0.976 0.327 1.396 1.090 1.382 1.092 1.372 1.046 0.990 0.314

-1.361 1.193 -1.085 0.092 -2.697 -0.860 -1.414 4.140 1.078 1.352 1.091 1.332 1.037 1.002 0.406 1.069 1.368 1.085 1.360 1.046 1.019 0.390 0.842 -1.170 0.553 -2.059 -0.860 -1.668 4.103 1.041 1.004 1.270 1.014 0.972 0.405 1.030 0.989 1.291 1.016 0.983 0.392 1.068 1.517 -1.627 -0.197 -1.119 3.316 4 4- + + 4-1.040 1.009 0.818 0.787 0.318 1.036 1.004 0.811 0.783 0.296 0.386 0.498 0.863 0.511 7.432 0.333 0.242 0.306 0.231 8.824 4.762 25

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 23-11 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 13 Relative Power Distribution Comparison Between Plant Measurement and ANC - 20,828 MWD/MTU Legend: ANC Predicted Assembly Average Power Measured Data Cycle 13 EOC

% Difference 0.741 0.992 1.279 1.042 1.289 1.043 1.064 1.152 0.716 0.954 1.266 1.026 1.288 1.016 1.040 1.152 3.492 3.983 1.027 1.559 0.078 2.657 2.308 0.000 0.429 0.403 0.992 1.246 1.036 1.276 1.048 1.284 1.025 1.116 6.452 0.955 1.234 0.997 1.271 1.023 1.287 1.003 1.124 3.874 0.972 3.912 0.393 2.444 -0.233 2.193 -0.712 0.315 0.289 1.279 1.035 1.022 1.015 1.291 1.053 1.260 0.889 8.997 1.279 1.004 0.988 0.985 1.291 1.034 1.279 0.883 0.000 3.088 3.441 3.046 0.000 1.838 -1.486 0.680 1.042 1.275 1.014 1.277 1.050 1.290 1.025 0.853 1.025 1.275 0.986 1.278 1.035 1.308 1.030 0.871 1.659 0.000 2.840 -0.078 1.449 -1.376 -0.485 -2.067 1.289 1.045 1.290 1.050 1.290 1.033 1.027 0.384 1.296 1.027 1.297 1.039 1.310 1.042 1.059 0.378

-0.540 1.753 -0.540 1.059 -1.527 -0.864 -3.022 1.587 1.043 1.283 1.053 1.290 1.034 1.048 0.469 1.024 1.297 1.041 1.314 1.044 1.080 0.464 1.855 -1.079 1.153 -1.826 -0.958 -2.963 1.078 1.064 1.024 1.260 1.024 1.025 0.468 1.059 1.015 1.293 1.035 1.055 0.458 0.472 0.887 -2.552 -1.063 -2.844 2.183 1.152 1.117 0.890 0.851 0.376 1.190 1.150 0.897 0.874 0.365

-3.193 -2.870 -0.780 -2.632 3.014 0.432 0.317 0.419 0.319 3.103 -0.627 26

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-12 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC - 219 M1VD/MTU Legend: ANC Predicted Assembly Average Power Measured Data

% Difference 0.654 1.023 1.363 1.081 1.324 1.087 1.110 1.227 0.644 1.020 1.368 1.086 1.324 1.082 1.128 1.239 1.553 0.294 -0.365 -0.460 0.000 0.462 -1.596 -0.969 0.418 0.400 1.023 1.306 1.082 1.292 1.087 1.365 1.066 1.158 4.500 1.032 1.312 1.095 1.297 1.093 1.361 1.072 1.153

-0.872 -0.457 -1.187 -0.386 -0.549 0.294 -0.560 0.434 0.288 0.265 1.363 1.082 1.076 1.020 1.290 1.085 1.302 0.870 8.679 1.367 1.095 1.094 1.033 1.292 1.077 1.295 0.854

-0.293 -1.187 -1.645 -1.258 -0.155 0.743 0.541 1.874 1.081 1.293 1.021 1.252 1.040 1.265 1.028 0.802 1.074 1.295 1.035 1.266 1.055 1.271 1.031 0.767 0.652 -0.154 -1.353 -1.106 -1.422 -0.472 -0.291 4.563 1.324 1.087 1.290 1.041 1.240 1.011 0.935 0.297 1.318 1.095 1.302 1.061 1.263 1.034 0.940 0.306 0.455 -0.731 -0.922 -1.885 -1.821 -2.224 -0.532 -2.941 1.087 1.365 1.086 1.266 1.011 0.940 0.335 1.083 1.369 1.102 1.290 1.041 0.958 0.326 0.369 -0.292 -1.452 -1.860 -2.882 -1.879 2.761 1.110 1.064 1.302 1.029 0.936 0.335 1.114 1.068 1.309 1.058 0.950 0.349

-0.359 -0.375 -0.535 -2.741 -1.474 -4.011 1.227 1.155 0.868 0.802 0.297 1.204 1.134 0.852 0.766 0.279 1.910 1.852 1.878 4.700 6.452 0.416 0.279 0.390 0.252 6.667 10.714 27

. 1 ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-13 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC - 8,999 MWD/MTU Legend: ANC Predicted Assembly Average Power Measured Data

% Difference 0.717 1.004 1.354 1.078 1.361 1.042 1.021 1.103 0.684 0.997 1.358 1.077 1.360 1.033 1.029 1.122 4.825 0.702 -0.295 0.093 0.074 0.871 -0.777 -1.693 0.411 0.396 1.004 1.297 1.054 1.342 1.087 1.340 0.986 1.061 3.788 1.001 1.298 1.060 1.343 1.083 1.339 0.991 1.067 0.300 -0.077 -0.566 -0.074 0.369 0.075 -0.505 -0.562 0.292 0.270 1.354 1.055 1.068 1.045 1.360 1.072 1.269 0.822 8.148 1.363 1.063 1.073 1.043 1.359 1.060 1.272 0.815

-0.660 -0.753 -0.466 0.192 0.074 1.132 -0.236 0.859 1.078 1.342 1.046 1.345 1.084 1.330 1.008 0.788 1.085 1.350 1.048 1.351 1.087 1.338 1.013 0.765

-0.645 -0.593 -0.191 -0.444 -0.276 -0.598 -0.494 3.007 1.361 1.086 1.360 1.085 1.337 1.041 0.965 0.317 1.367 1.090 1.370 1.090 1.350 1.054 0.969 0.321

-0.439 -0.367 -0.730 -0.459 -0.963 -1.233 -0.413 -1.246 1.042 1.340 1.073 1.330 1.041 0.989 0.369 1.040 1.350 1.081 1.349 1.057 0.998 0.358 0.192 -0.741 -0.740 -1.408 -1.514 -0.902 3.073 1.021 0.985 1.269 1.009 0.965 0.369 1.027 0.992 1.280 1.020 0.970 0.375

-0.584 -0.706 -0.859 -1.078 -0.515 -1.600 4 4- 4- 4-1.103 1.059 0.822 0.788 0.317 1.105 1.058 0.812 0.758 0.298

-0.181 0.095 1.232 3.958 6.376 0.409 0.282 0.390 0.259 4.872 8.880 28

C %.

ATTACHMENT (3)

SUPPLEMENTAL INFORMATION DESCRIBING THE USE OF THE WESTINGHOUSE PHOENIX-P/ANC CODE PACKAGE FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIGURE 2.3-14 Calvert Cliffs Nuclear Power Plant Unit 2 Cycle 14 Relative Power Distribution Comparison Between Plant Measurement and ANC - 19,721 MWD/MTU Legend: ANC Predicted Assembly Average Power Measured Data

% Difference 0.766 0.983 1.280 1.030 1.299 1.018 1.032 1.140 0.731 0.979 1.285 1.028 1.300 1.004 1.028 1.160 4.788 0.409 -0.389 0.195 -0.077 1.394 0.389 -1.724 0.493 0.482 0.983 1.247 1.012 1.285 1.043 1.288 0.988 1.105 2.282 0.976 1.248 1.012 1.287 1.037 1.290 0.994 1.118 0.717 -0.080 0.000 -0.155 0.579 -0.155 -0.604 -1.163 0.353 0.335 1.280 1.012 1.037 1.016 1.308 1.045 1.260 0.867 5.373 1.287 1.014 1.029 1.005 1.309 1.038 1.271 0.867

-0.544 -0.197 0.777 1.095 -0.076 0.674 -0.865 0.000 1.030 1.285 1.017 1.300 1.057 1.308 1.022 0.845 1.035 1.290 1.008 1.299 1.050 1.318 1.029 0.843

-0.483 -0.388 0.893 0.077 0.667 -0.759 -0.680 0.237 1.299 1.043 1.308 1.057 1.315 1.054 1.024 0.373 1.306 1.040 1.312 1.050 1.306 1.056 1.032 0.372

-0.536 0.288 -0.305 0.667 0.689 -0.189 -0.775 0.269 1.018 1.288 1.046 1.308 1.054 1.046 0.429 1.011 1.294 1.045 1.319 1.056 1.056 0.423 0.692 -0.464 0.096 -0.834 -0.189 -0.947 1.418 1.032 0.987 1.260 1.023 1.024 0.429 1.029 0.992 1.270 1.027 1.032 0.438 0.292 -0.504 -0.787 -0.389 -0.775 -2.055 4 4 4 4 4 1.140 1.102 0.866 0.845 0.373 1.154 1.112 0.863 0.835 0.360

-1.213 -0.899 0.348 1.198 3.611 L - . A ................,............ a a 0.491 0.341 0.477 0.322 2.935 5.901 29

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