ML110760085

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Core Operating Limits Report, Cycle 19
ML110760085
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 03/11/2011
From: John Stanley
Constellation Energy Nuclear Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML110760085 (44)
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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of fl Constellation *'~eDF

%0 Energy- ,,,D CALVERT CLIFFS NUCLEAR POWER PLANT March 11, 2011 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 -

Core Operating Limits Report for Unit 2, Cycle 19 Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached Core Operating Limits Report for Unit 2, Cycle 19, Revisions 0 and I are provided for your records.

Please replace the Unit 2 Core Operating Limits Report in its entirety, with the attached Revision 1 (Attachment 2).

Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.

JJS/PSF/bjd Attachments: (1) Core Operating Limits Report for Unit 2, Cycle 19, Revision 0 (2) Core Operating Limits Report for Unit 2, Cycle 19, Revision 1 cc: Resident Inspector, NRC (Without Attachment)

D. V. Pickett, NRC S. Gray, DNR W. M. Dean, NRC

ATTACHMENT (1)

CORE OPERATING LIMITS REPORT FOR UNIT 2, CYCLE 19, REVISION 0 Calvert Cliffs Nuclear Power Plant, LLC March 11, 2011

Caution: Valid only for U2C19 Modes 5, 6 or Defueled

.C. nstel atiowý Mgergy° Calvert Cliffs Nuclear Power Plant, Inc.

Core Operating. Limits-Report (COLR)

Unit 2 Cycle 19 Revision 0 Effective Date:-2 2 5.)1(

2/2 ~ ill RESPONSIBLE ENGINEER / DATE

?~q ILrty .I INDEPENDENT REVIEWER I DATEI EES- PWR CORE DESIGN I DATE Rev. 0 Calvert Cliffs 2,

'CalvertCliffs Cycle 19 2, Cycle COLR 19.COLR .Page bf 20 Page 1I of 20 Rev. 0

CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 19 The following limits are included in this Core OperatingLimits Report:

Specification Title Page.

Introduction.............................. ....... ........ . . . ....4 Definitions ................................... ......... *......................... :............ ...... 5 Licensing Restrictions ..................... ..................... 66......................................

3.1.1 Shutdown Margin (SDM) ...... .................... I............. ...... I .......-.---....... 7 3.1.3 Moderator Temperature Coefficient (MTC) ............................................ ...... ,I 7 3:1.4 Control Element Assembly (CEA) Alignment ......................................................... 7 31.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 7 3.2.1 Linear Heat Rate (LHR)......... ........................................................................... 7 312.3 Total Integrated Radial Peaking Factor (F, ).................8 3.2.5 Axial Shape Index (ASI) ...................................................................................... 8 31.3.1 Reactor Protective System (RPS) Instrumentation - Operating ........ ................ 8 3.9.1 Boron Concentration ............................................................................................ 9 List of Approved Methodologies ............................................................................. 18 The following figures are: included in this CorevOperating Limits Report:

Number Title Page.

Figure 3.1-6: .CEA Group'Insertion Limits Vs. Fractionbof Rated Thermal:Pmower.... ........ 10.

Figure 3.2.1-1 Allowable PeakLinear Heat Rate vs. Time in Cycle........................................... 11 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits........................... 12

'Figure 3.2.3 Total Integrated Radial Peaking Factor (F1 ) vs.

Allowable Fraction of Rated Thermal Power .......................................................... 13 Figure 3.2.5 DNB Axial Flux Offset Control Limits ......................................................... 14 Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint Peripheral Axial. Shape Index vs. Fraction of Rated Thermal Power ....................................................... 15 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1....................... .. 16 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part 2 ......................................... 17 Calvert Cliffs 2, Cycle 19.C.OLR Page 2 of 20 CvrCf2Cc19OPg2f0Rev. 0

UNIT 2 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 Page 3 of 20 Rev. 0 Qalvert4Cjiffs 19 COLR CycW 19 Calvert Cliffs 2, Cycle COLR Page.3 of 20 .Rev. .0

INTRODUCTION This report provides the cycle-specific limits for operation' of Calvert Cliffs Unit 2, Cycle 19. 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 Integrated Radial Peaking Factor (F).T)

Axial Shape. Index (ASI)

Reactor Protective System (RPS) Instrumentation.-.Operating, Boron Concentration In addition, this report contains a number of figures which give limits onthe 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 deyeloped using the NRC'approv ed 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 2 Cycle. 19 (U2C19) COLR per Safety Evaluation SE00507 Revision 0.- U2C19 may operate in Modes 5, 6 or in a defueled condition. Although U2C19 is only authorized to enter Modes 5, 6, and defueled- tonditions, limits presented within this::

COLR relate to some parameters only applicable. to operation in higher plant modes.:

Ca .et.lifs2,Cyle1.CLRPae o.2 Rv 0 61výrt Cliffs 2, Cycle 19 COLR Page 4 of 20 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.

SASI =lower - upper _y" lower + upper The Axial Shape Index (Y1 ) used for the trip and pretrip signals in the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel.

Yi.AYE+.B Total Integrated Radial PeakingFactor.- F "T

The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core.

Calvert Cliffs 2, Cycle 19.COLR Tage 5 of 20  :'Rev. *0

LICENSING RESTRICTIONS 1). "Calvert Cliffs will adhere to the deviations noted in Section 1 of EMF-2103 until such time as:

AREVA develops anew revision of EMF-2103,

  • The NRC approves the new revision of EMF-2103, and
  • Calvert Cliffs implements. the new, NRC-approved revision of EMF-2103.

This commitment will terminate when the above item's are. met or a license. amendment is approved to permit the use of a different evaluation method to replace EMF-2103."

Reference:

NL-2010-000006-009.

2) "For Unit 1 and Unit 2: Core Operating Limits Report Figures 3.1.6, 3.2.3, and 3.2.5 will not be changed without prior NRC approval until an NRC-accepted generic, or CCNPP-specific, basis is developed for analyzing the Control Rod Bank Withdrawal event, the Control Element Assembly Drop, and the Control Element Assembly Ejection (power' level-sensitive transients) at full power conditions only."

Reference:

Response 6 in Letter from Mr. G. H. GelIricIh'(CCNPP) to Document Control Desk (NRC),

dated December.30,2010, Supplement.to the License Amendment Request: Transition from Westinghouse Nuclear Fuel to AREVA NuclearFuel

3) "For Unit 1.and Unit 2:I Approval ofthe use of S-RELAP5 is restricted to only those WI1* safetyanalysesthat confirm acceptable transient performance relative to the specified acceptable fuel design limits. Prior transient specific NRC approval is required for transient performance relative to reactor coolant pressure boundary integrity until an NRC-accepted, generic, or CCNPP-specific, basis is developed for the use of S-RELAP5 to demonstrate reactor coolant pressure boundary integrity."

Reference:

Response 9 in Letter from Mr. G. H. Gellrich (CCNPP) to Document Control Desk (NRC),

dated December 30, 2010, Supplement to the License Amendment Request: Transition from Westinghouse Nuclear Fuel to AREVA Nuclear Fuel Calvert Cliffs 2, Cycle 19 COLR Page 66f20 Rev.,0

CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)

Tavg> 200 °F - Modes 3 and 4:

The shutdown margin shall be > 3.5% Ap.

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- Ap/"F at rated thermal power..

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

The allowable time to realign a CEA is 120 minutes when the pre-misaligned FJ is < 1.65 and zero (0) minutes when the pre-misaligned YFjT is > 1.65..

The pre-misaligned F. value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days prior to the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero:(0).

minutes.

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

The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6.

Figure 3.1.6 will not be changed unless the requirements in Licensing Restriction #2 are met.

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 3.2-14.

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 32.1.2):.

The-alarm setpoints are equal to or less than 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`3.2.12-2 Calvert Cliffs 2, Cycle 19 COLR Page 7 of 20 ReV.

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 1.07 .
2. An engineering uncertainty factor of 1.03,..

31a For measured thermal power less than or equal to 50 percent but greaterlthan 20 percent, of rated full, core power a thermal power measurementuncertainty factor of 1.035.

3.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020.

3.2.3 Total Integrated Radial Peaking Factor (F,) (SR 3.2.3.1)

The calculated value of F,' shall be limited to < 1.65.

The allowable combinations ofthermal powe, CEA position, and FT are shown on COLR.

Figure 3.2.3.

Figure 3.2.3 will not be changed unless the requirements in Licensing Restriction #2 are met.

3.2.5 Axial Shape Index (ASI) (SR.3.2.5.1) _4 The axial shape index and thermal power shall be maintained equal to or less than the limits' of COLR Figure 3.215 for CEA insertions specified by.COLR Figure 3.1.6.

Figure 3.2.5 will not be changed unless the requirements in Licensing Restriction #2 are met.

3.3.1 Reactor Protective System (RPS) Instrumentation i- Operating (Reactor.Trip Setpoints)(TS Table 3.3.1-1)

The Axial Power Distribution -,High trip setpoint and allowable values are given in COLR" Figure 3.3.1-1.

The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. Theallowable values areto be-not less than the larger of(1). 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3.

Calvert Cliffs 2, Cycle 19 COLR Page 8 of 20 Rev. 0'.

3.9.1 Boron Concentration (SR 3.9.1.1)

The conservative -boron concentration will maintain the Ikfr at 0.95 or less (including-a 1% Ak/k refuelingallowance for uncertainties). The refueling boron concentration shall be maintained uniform. For Mode 6 operation the RCS temperature must be maintained

< 1400 F.

U2C19 Refueling Boron Concentration Limits Post-Refueling UGS or RV Head Lift Height <12 Inches No Restriction Restrictions.

4-Minimum Required Refueling Boron Concentration:

This number includes:

  • Chemistry Sampling Unceitainty > 263.4 ppm > 2342 ppm.
  • Boron-4ODepletion Allowance
  • Margin for dilution of refueling pooli (Note 1) (Note 1):'

betweený low and high level alarms

" Unlimited number of temporary rotations of fuel assemblies

" Extra Conservatism for empty locations

-during refueling operations.

Note: (1) The limit in the above table represents the minimum required refueling boron concentration. It is acceptable for NEOP-23 to conservatively specify higher values.

Calvert Cliffs 2, Cycle 19 COLR a

.Pageg9.of 20 Rev. 0

1.000 0.900 CC U- 0.800 LU 0.700 I--

-Jl 0.600 LU 0.500%o 0.400 LA-0.300 0.200 0.100 Above ZPPDIL SE'POINT REGULATING GROUP 5 REGULATING GiROUPP3 REGULATING GROUP I I I I,: ] I I . I I - 80 IOO I I I 0% 20% 40% 60% 80% 100% 0% 20% 40% 60% 80%,1 100%0% 20%: 40% 60%ý 80% 100%

-$If1 135" 108" 81" '4" 27" 0" .135" 81'" 54" 27" 0" 135" 108'" 81" 54" 27" 0..

REGULATING GROUP 2 I I I I I  ! I I.:  :

0% 20% 40% 60% 80% 100%0% 20% 40% 60% :.80% 100%

135" 108" 81" 54" 27" 0" 135" 108" 81" 54" 27" 01.

%CEA INSERTION, INCHES CEA WITHDRAWN (ARO is defined in NEOP-23)

Note:

Per Tech Spec Bases 3.1.5 and 3.1.6, CEAs are considered to be fully withdrawn at 129 inches.

Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Page 10 of 20 Rev. 0 Cliffs 2, Calvert Cliffs. 19 COLR Cycle 19 2, Cycle COLR Page 10 of 20 Rev. 0.

17.0 16.5

. 16.0 15.5 ij 15.0 UNACCEPTABLE OPERATION w +

O UWW -J 14.5 M LLL14.3,

.J: 14.0 ACCEPTABLE OPERATION 13.5_

13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable PeakLinear Heat Rate vs. Time in Cycle I .

Calvert Cliffs 2, Cycle 19 COLR, Peo2ev

,Page I I of 20 Rov. a.,

1.10 1.05 1.00

,0.95 0.90 0.85 Lu 0.80 0

0. 0.75

_1 0.70 Lud 0.65 I-zU 0.60, 0

z 0.55 0

0.50 0.45 0.40:

0.35 0.30 --

0.25 0.20

-0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIAL SHAPE INDEX, Y, Figure 3.2.1-2 Linear Heat Rate Axial Flux:Offset Control Limits (AXIAL SHAPE INDEX limits for Linear HeatRate when using Excore Detector Monitoring

-System)..

(LCO Limits are not needed below 20% thermal power per SE00433)

(See NEOP-23 for Operational Limits).

Calvert Cliffs 2, Cycle 19 COLR Page 12 of 20 R~ev.;0"

1.05 w 0.95 OPERATION 0 REGION 0.5

.. 0.85 '(1.7325,0.80)

, 0.75

,ZFrT LIMIT CURVE o 0.65 u- 0.55 0

z *ACCEPTABLE o04OPERATION C-, REGION 0.35 U-M 0.25 O (1.819,0.20)

-'0.15 0.05t 1.60 1.65 1.70 1.75 1.80 1.85' FrT Figure 3.23.

Total Integrated Radial Peaking Factor (Fr) vs.

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

Calvert Cliffs 2ý 2, CyO16.19 COLR Cycle 19 COLR' Page 13 of 20 Rev.0 Calved 13 of 20 Rev. 0

1.10 1.05

(-0.08,1.00)(.15,1. )

1.00

-j UNACCEPTABLE UNACCEPTABLE w 0.95 OPERATION, OPERATION REGION '

w 0.90 + REGION 3: 0.85 w (0.3, 0.80) 0.80 0 0.75: ACCEPTABLE 0.70 (-0.3, 0.70) :OPERATION REGION 0.65 Lu 0.60 0 0.55

(-0.3, 0.50)

U_ 0.50 0.45 0.40 0.35 0.30

(-( .42, 0.20) (0.3, 0.20) 0.25 0.20.

-0.40 -0.20 0.00 0.20 0.40 0.60

-0.60 PERIPHERAL AXIAL SHAPE INDEX, Yo Figure 3.2.5 DNI Axial Flux Offset Control Limits (LCO Limits are notfneeded below 20% thermal power per SE00433)

(See NEOP-23 for Operational-Limits)

Calvert Cliffs 2, Cycle 19 COLR -Page 14 of 20 P kev. 0

1.300 1.250 1.200 1.150 1.100 1.050 1.000 Uj 0.950 O 0.900

. 0.850

' 0.800

'- 0.750 I- 0.700 LL 0.650 Q

0

. .oo I.- 0.550*

5- 0.500 0.450, 0.400 0.350 0.300 0o.250 0.200 0.150 L

-0.80 -0.60 -0.40 -0.20 0.00 0.20 0.40 0.60- 0.80 PERIPHERAL. AXIAL SHAPE INDEX, Y, Figure 3.3.1-1 Axial Power Distribution - High Trip Setpoint .

Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs2, Cycle I9COLR Page 15 of 20 Rev. 0 ReV.

1.60 P var =2869.5 x (Al) x (QR1)+ 17.98 x Tin - 10820 1.50 QNBAI xQRi 1.40

(-0.6, 1.3) I+

1.30 1.20 Ai 1. +0.16 x 1

.(+0.6,.11) 1.10 A1~ 0.5--S,+1

.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 MaAgin/Low Pressure Trip Setpoint - Part 1 (ASI vs. A)kj Calvett Cliffs 2, Cycle 19 COLR' 1 of 20

ý Page 16 Rey..O.,

Pvar pTrip = 2869.5 x (A1) x (QR1) + 17.98 x Tjn - 10820 QDNB = Al x QR1 1.2 - - I- (1.2,1.2) 1.1QRI (RTP) +0.0 1i 0 ,* 1.0~Q~

___A

__ -_ 0_

.0.9 10 (0.6, 081 0.8 "__.

0.7 ___ QR, 0.375 x (RTP) + 0.625

  • oý6 03R 1 0.9167 x (RIP) + 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. QR1j)

Page 17of20 Rev. 0 Calvert Cliffs 2, 2, Cycle 19 COLK Cycle 19 Rev. 0 Qilvert'Cliffi COLR Pake 17 (if 20

LIST OF APPROVED METHODOLOGIES

1. ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU" Advanced Nuclear Fuels Corporation, December 1991
2. BAW- 10240(P)(A); Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods" Framatome ANP, May 2004
3. EMF-92-116(P)(A); :Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs" Siemens Power Corporation, February 1999
4. EMF-92-153(P)(A), Revision i, "HTPDeparture from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005
5. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume I -

Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997

6. EMF-1961 (P)(A), Revision 0, "Statistical Setpoint/Transient Methodology for Combustion-Engineering Type Reactors," Siemens Power Corporation, July 2000
7. EMF-2 103 (P)(A), Revision 0, "Realistic Large Break LOCA Methodology, for Pressurized Water Reactors" Framatome ANP, April 2003 [Licensing Restriction #1]
8. EMF-23 10(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors" Framatome ANP, May 2004 [Licensing Restriction #3]
9. EMF-2328(P)(A), Revision 0, "PWR Small Break.LOCAEEvaluation Model,".S-RELAP5 Based" Framatome ANP, March 2001
10. XN-75-32(P)(A), Supplements 1, 2, 3 & 4, "Computational Procedure for Evaluating.Fuel Rod Bowing" Exxon Nuclear Company Inc., February 1983
11. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for

,,Pressurized Water Reactors" Exxon Nuclear Company Inc., October 1983

12. XN-NF-79-56(PXA), Revision I and.Supplement 1, "Gadolinia Fuel Properties for LWR Fuel Safety Evaluation" Siemens Power Corporation, October:1981
13. XN-NF-82-06(P)(A), Revision i&Supplements 2,4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup" Exxon Nuclear Company Inc., October 1986.
14. XN-NF-82-2 (P)(A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations" Exxon Nuclear Company Inc., August.

1983

15. XN-NF-85-92(P)(A), Revision 0, "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results" Exxon Nuclear Company Inc., September 1986.

. Calv6rt Cliffs 2, Cycle 19 COLR Calvert Cliffs 2, CyclePage 18 19 COLRof 20 Rev. 0 18 of 20 Revi.O

16. CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination of SystemParameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units I and 2,"

January 1980

17. CEN-1 91 (B)-P, ".CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981
18. 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)]
19. CENPD- 161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986
20. CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981
21. CENPD-22 5-P-A, "Fuel and Poison Rod Bowing," June 1983
22. CENPD-3 82-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers,"

August 1993

23. CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974
24. CEN- 161 -(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989
25. CEN-161-(B)-P, Supplement 1-P, "Improvements to Fuel Evaluation Model," April 1986
26. Letter-fromrMr. S. A. McNeil, Jr. (NRC) to Mr.-J. A. Tieman (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN-161-(B)-P,
  • Supplement l-P, Improvements to Fuel Evaluation Model" (Approval of CEN- 161 (B),

Supplement I-P)

27. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990
28. CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977
29. CENPD-387-P-A,, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel"
30. CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLOTO Cladding Material in CE Nuclear Power Fuel Assembly Designs".
31. WCAP-1 1596-P-A, "Qualification of the PHOENIX-PANC Nuclear Design System for Pressurized WaterReactor Cores," June 1988.
32. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September 1986.
33. WCAP-10965-P-A Addendum 1,."ANC: A Westinghouse Advanced NodalComputer Code; Enhancements to ANC Rod Power Recovery," April 1989.

Page 19 Of 20 Rev. 0

'Calvert 2, Cycle Calvert Cliffs 2, 19 COLR Cycle 19 COLR Page 19 6f 20 Rev. 0

34. WCAP-16072-P.-A, 'Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," August 2004.
35. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"

August 2004.

Calvert Cliffs 2, Cycle 19 COLR Page 20, of 20 Rev. 0

ATTACHMENT (2)

CORE OPERATING LIMITS REPORT FOR UNIT 2, CYCLE 19, REVISION 1 Calvert Cliffs Nuclear Power Plant, LLC March 11, 2011

SENGi '

Core Operating Limits Report (COLR)

Unit. 2 Cycle 19 Revision 1 Effective Date: ____________

RESPONSIBLE ENGINEER / DATE INDEPENDENT REVIEWER / DATE ES - PWR CORE DESIGN I DATE calvert Cliffs 2, Cycle19 COLR Page 1~f21 Rev. I

I CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 19 The following limits are included in this Core Operating Limits Report:

  • Specification Title Page Introduction .......................... ................................... ............................................ . 4 Definitions .............................................. ..........................

.. 5 Licensing Restrictions............................................ 6 3.1.1 Shutdown Margin (SDM) ........................................... .................................... 8 3.1.3 Moderator Temperature Coefficient (MTC)........................................................ 8 3.1.4 Control Element Assembly (CEA) Alignment .................. ........................... .8 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits ........................... 88...

3.2.1 Linear Heat Rate (LHR) ............ I ............ ................... 8, 3.2.3 Total Integrated Radial Peaking Factor (F1 T) ......................................................... 9 3.2.5 Axial Shape Index (A SI) ..... *...... ................................................ ........................ 2.... 9

.3.3.1 Reactor Protective System (RPS) Instrumentation - Operating .............................. ..9 3.9.1 Boron Concentration ...................................... ....................................................... 10 List of Approved Methodologies ................... ............................................................ 19 The following figures are included in this Core Operating Limits Report:

Number Title Pane Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power .... ............. 1.

Figure 3.2.1-1 Allowable Peak*Linear Heat Rate vs. Time in Cycle ................................ ............ 1..12 Figure 3.2.1-2. Linear Heat Rate Axial Flux Offset Control Limits .............................. 13 T.

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

Allowable Fraction of Rated Thermal Power ...................................................... 14 Figure 3.2.5 DNB Axial Flux Offset Control Limits.....,............... .........................

. 15 Figure 3.3.1-1 Axial Power Distribution -.High Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power....... ......................... 16 Figure 3.3.1-2 Thermal MargilLow Pressuie Trip Setp0int- Part 1.......,. ............................. 17 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint - Part22 ....... I............................ 18 Calvert Cliffs 2. Cycle 19 COLR 7 -- d ......

Pae 2 of 2. Rev. I

UNIT 2 CORE OPERATING LIMITS REPORT LIST OF EFFECTIVE PAGES Page No. Rev, No.

2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 1i

.. . l..1 ' " .. 1 '__.. ...

12 1 13 1 14 1 15 1 16 "

17 1 18 1 -

19 1 20 1 21 1

. 19. C .RPg f2 e..

C.l..r Clfs2 Cycle...

Calveirit Cliffý 2, Cycle 19 COLR Page 3 of 21 R6v. I

INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 19. 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 Integrated Radial Peaking Factor (FrT)

Axial Shape Index (ASI)

Reactor Protective System (RPS)Instrumentation - Operating Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications.

This report has been prepared in accordance with the requirements of Technical Specifications.

The cycle specific limits have been developed using the NRC-approved methodologies given in the "List of Approved Methodologies" section of this report and in the Technical Specifications.

COLR Revision 0 Initial release of the Unit 2 Cycle 19 (U2C19) COLR per Safety Evaluation SE00507 Revision 0. U2C19 may operate in Modes 5, 6 or in a defueled condition. Although U2C19 is only authorized to enter Modes 5, 6, and defueled conditions, limits presented within this COLR relate to some parameters only applicable to operation in higher plant modes.

COLR Revision 1 Revision 1 of the U2C19 COLR was issued per Safety Evaluation SE00507 Rev. 1, which authorized operation of U2C19 core in all plant modes.

Calvert Cliffs 2, Cycle 19 COLR . Page 4 of21 Rev. 1

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 -Y lower + upper The Axial Shape Index (Y1 ) used for the trip and pretrip signals in the Reactor Protection System (RPS) is the above value (YE) modified by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel.

Y =AYE + B Total Integrated Radial Peaking Factor - FrT The Total Integrated Radial Peaking Factor is the ratio of the peak pin power to the average pin power in an unrodded core.

Calvert cliffs 2, Cycle 19 COLR Pag 5 of21 Rev. 1

LICENSING RESTRICTIONS

1) For the Asymmetric Steam Generator Transient analysis performed in accordance with the methodology of Technical Specification 5.6.5.b.8, the methodology shall be revised to capture the asymnmetric core inlet temperature distribution and application of local peaking augmentation factors. The.revised methodology shall be applied to Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.
2) For the Seized Rotor Event analysis performed in accordance with the methodology of Technical Specification 5.6.5.b.8, the methodology shall be revised to capture the asymmetric core inlet flow distribution. The revised methodology shall be applied to Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.
3) For the Control Element Assembly Ejection analysis performed in accordance with the methodology of Technical Specification 5.6.5.b.I 1, the cycle-specific hot zero power peak average radial fuel enthalpy is calculated based on a modified power dependent insertion limit with Control Element Assembly Bank 3 assumed to be fuillyinserted (only in the analysis, not in actual plant operations). This revised methodology shall be applied to Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.
4) The Small Break Loss of Coolant accident performed in accordance with the methodology of Technical Specification 5.6.5.b.9 shall be analyzed using a break spectrum with augmented detail related to break size. This revised methodology shall be applied to Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.
5) Core Operating Limits-Report Figures 3.1.6, 3.2.3, and 3.2.5 shall not be changed without prior NRC review and approval until an NRC-accepted generic, or Calvert Cliffs-specific, basis is developed for analyzing the Control Element Assembly Rod Bank Withdrawal Event, the Control Element Assembly Drop, and the Control Element Assembly Ejection (power level-sensitive transients) at full power conditions only.
6) Approval of the use of S-RELAP5 (Technical Specification 5.6.5.b.8) is restricted only to those safety analyses that confirm acceptable transient performance relative to the specified acceptable fuel design limits. Prior transient specific NRC approval is required to analyze transient performance relative to reactor coolant pressure boundary integrity until NRC-approval is obtained for a generic or Calvert Cliffs-specific-basis: for the use of the methodology in Technical Specification 5.6.5.b,8 to demonstrate reactor coolant pressure boundary integrity.

Rev. 1 Calvert Cliffs 2, Cycle 19 COLR Calvert Cliffs 2, Cycle 19Page Page of 21 66 of COLR 21 ýý:Rev. I

7) For the RODEX2-based fuel thermal-mechanical design analysis performed in accordance with the methodology of Technical Specification 5.6.5.b.3, Calvert Cliffs Unit 2 core reload designs (starting with Cycle 19) shall satisfy the following criteria:
a. Predicted rod internal pressure shall remain below the steady state system pressure.
b. The linear heat generation rate fuel centerline melting safety limit 9hall remain below 21.0 KW/ft.
8) For the Control Element Assembly Ejection analysis, Calvert Cliffs Unit 2 core reloads (starting with Cycle 19) shall satisfy the following criteria:
a. Predicted peak radial average fuel enthalpy when calculated in accordance with the methodology of Technical Specification 5.6.5.b. I1shall remain below 200 cal/g.
b. For the purpose of evaluating radiological consequences, should the S-RELAP5 hot spot model predict fuel temperature above incipient centerline melt conditions when calculated in accordance with the methodology of Technical Specification 5.6.5.b.8, a conservative radiological source term (in accordance with Regulatory Guide 1.183, Revision 0) shall be applied to the portion of fuel beyond incipient melt conditions (and combined with existing gap source term), and cladding failure shall be presumed.
9) The approval of the emergency core cooling system evaluation performed in accordance with the methodology of Technical Specification 5.6.5.b.7 shall be valid only for Calvert Cliffs Unit 2, Cycle 19. To remove this condition, Calvert Cliffs shall obtain NRC approval of the analysis of once- and twice-burned fuel for core designs following Unit 2 Cycle 19.

Reference:

Letter from Douglas V. Picket (NRC) to George H. Gellrich (CCNPP)*dated February 18, 2011, Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 - Amendment Re: Transition from Westinghouse Nuclear Fuel to AREVA Nuclear Fuel (TAC Nos. ME2831 and ME2832)

Clff Calver'.,.. 2, Cyl 19 C.R.ag.7o...ev Calvert Cliffs 2, Cycle 19 COLR Page 7 of 21 Rev. I

CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 19 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)

Tavg > 200 7F - Modes 3 and 4.

The shutdown margin shall be > 3.5% Ap.

Tavg *5200F -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' Ap/°F at rated thermal power.

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

The allowable time to realign a CEA is 120 minutes when the pre-misaligned FrT is < 1.65 and zero (0) minutes when the pre-misaligned FT is > 1.65 The pre-misaligned F. value used to determine the allowable time to realign the CEA shall be the latest measurement taken within 5 days prior to the CEA misalignment. If no measurements have been taken within 5 days prior to the misalignment and the full core power distribution monitoring system is unavailable then the time to realign is zero (0) minutes.

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

The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6.

Figure 3.1.6 will not be changed' unless the requirements in Licensing Restriction 5 are met.

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 or less than 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.

Cycle 19 COLR Page 8 of 21 Rev. 1 Cliffs 2, Calvert Cliffs Calvert 2, Cycle 19 COLR Page 8 of 21 .Rev. -

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 1.07
2. An engineering uncertainty factor of 1.03, 3.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.

3,b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertaintyfactor of 1.020.

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

The calculated value of F.r shall be limited to < 1.65.

The allowable combinations of thermal power, CEA position, and FJ are shown on COLR Figure 3.2.3.

Figure 3.2.3. will not be changed unless the requirements in Licensing Restriction 5 are met.

3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1)

The axial shape index and thermal power shall be maintained equal to or less than the limits of COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.

Figure 3.2.5 will'not be changed unless the requirements in Licensing Restriction 5 are met.

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 3.3.11..

The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2 and 3.3.1-3. The allowable values are to be not less than the larger of (1) 1875 psia or (2) the value calculated from COLR Figures 3.3.1-2 and 3.3.1-3.

Calvert Cliffs 2, Cycle 19 COLR Page 9 of 21 .. ;Rev. I

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

< 1400 F.

U2C19 Refueling Boron Concentration Limits Post-Refueling UGS or RV Head Lift Height Restrictions.

No Restriction < 12 Inches Minimum Required Refueling Boron Concentration:

This number includes:

  • Chemistry Sampling Uncertainty > 2634 ppm > 2342 ppm
  • Boron-10 Depletion Allowance
  • Margin for dilution of refueling pool (Note 1), (Note 1) between low and high level alarms
  • Unlimited number of temporary rotations of fuel assemblies Extra Conservatism for empty locations during refueling operations.

Note: (1) The limit in the above table represents the minimum required refueling boron concentration. It is acceptable for NEOP-23 to conservatively specify higher values.

Page lOof2l Rev. 1 Cycle 19 Calvert Cliffs 2, Cycle COLR 19 COLR Page 10 of 21 Rev. I

1.000 0.900 0.800 0.700 0.600 osoo It 0.400 U

0.300 0.200 0o.00 AI, Qve ZPPDIL SE*OQNTr EGULTIN GRUP GULATING GROUP REGULATING GR9_UF' I

20% I 41%.

4oQ% ]-I 1 I I 0% 60% 80% 100% 0% 20% 40% 60% 80% 100%0% 20% 40% 69% 80% 100%

135" 108" 81' 54" 27".. 0". 135"' 108" 81" 54" 27" O" 135" 108" 81" 54"1 27" 0" REUATN GRU 4 ULATINGGROUP2 I , I... , I .

0%. YT1 I 1 1 02%40% 60% 80% 100%0% 20% 40% 60% 80% 100%

  • 135". 108" 81r 54" 27" 0" 135" 108" 81" 54" 27" 0"

%CEA INSERTION INCHES CEA WITHDRAWN (ARO is defined in NEOP-23)

Note:

Poe Tec SoptB*ses.3.1.5 and 3.1.6, CEAs are-considered to be y withdrawn at 129 inches.

Figure 3.1.6 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power This figure ,annot bechanged without prior NRC approval.

C.lver Cliffs.2, Cycle.. 19...C... . 'e.. Page 11 o' 1 I

,Drt tAý 4._Cycle A- 19 COLR Page .11 of .21 Re~v. I

17.0 if 16.5 I.!

F-u 16.0  !-

z uIW 15.5 W÷ W0 iu + 15.0 UNACCEPTABLE OPERATION C.)

Lu +

a.. J 14.5 LL14.3 0

14.0 ACCEPTABLE OPERATION 13.5 13.0 BOC EOC TIME IN CYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Rev. 1 Calvert Cliffs 2. Cycle 19 COLR Calvert Cliffs 2, Cycle Page Page 12 of2l 12 19 COLR of 21 Re-v. I

1.10 1.05 1.00 0.95 -0.091, 0.950 0.075, 0.950 0.90

  • 0.85 UNACCEPTABLE OPERATION UNACCEPTABLE

' 0.80 REGION OPERATION O - REGION 0.75 4(0.70 ACCEPTABLE S065OPERATION 0.65 REGION 0.60 0, -0.264, 0.600 0.248, 0.600 z 0.55 0

Q 0.50 7 0.45 0.40 0.35 0.30 025 -0.264, 0.200 0..248, 0.200 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

(,XI AJ SHAPE INDEX. jimits.for Linear Heat Rate when using Excore Detector Mo itoring System)

(LCO Limits are not need.edbelow 20% thermal power per SE00433)

(See NEOP-23 for Operational Limits):

ag 13 Cavetlifs2,Cyle19C.R *~ .. Re,..1 Offs 2,.CIycld 19 COLR Page 13 of 21 Rev. I

1.05 UNACCEPTABLE W 0.95 OPERATION 0.5 *REGION (1.7325, 0.80)

W 0.75

.I- -F- FT LIMIT CURVE W 0.65 A. 0.55 0

z o 0.45 ACCEPTABLE OPERATION o REGION 0.35

,LL w

. 0.25 0.15 (1.819, 0.20) 4 0.05 1.60 1.65 1.70 1.75 1.80 1.85 FrT Figure 3.2.3 Total Integrated Radial Peaking Factor (FrT) VS.

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

This figure cannot be changed without prior NRC approval.

Rev. 1 19 COLR Calvert Cliffs 2, Cycle 19 COLR Page 14of21 Page 14 of 21 ;Rev. 1

1.10 1.05 1.oo (-0.08,1.00) (0.15,1.00)

,J 0.95 UNACCEPTABLE UNACCEPTABLE

-J OPERATION OPERATION REGION--

u;0.90 REGION O 0.85 +

0 a-

,I' 0.80 (0.3, 0.80)

LU

-J 0.75 ACCEPTABLE

(-0.3, 0.70) rlPPPATIA)M 0.70 REGION ,

UI 0.65 2

0.60 0.55

(-0.3, 0.50) 0.50 0 0.45 +

z 0.40 C.

0.35 0.30 0.25 ) .42, 0.20) (0.3, 0.20)

A in 4 101. I I .. fl .1

-0.60 -0.40 40.20 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-23 for Operational Limits)

This figiur cannot be changed without prior NRC approval.

Caivert Cliffs 2, Cycle 19 COLR Page 15 of 21 Rev.

1.300 1.250 1.200 UNACCEPTABLE (0.0, 1.17) UNACCEPTABLE 1.150 OPERATION OPERATION REGION REGION 1.100 -

1.050 .

1.000 (-0.2, 1.00) (0.2, 1.00)

W 0.950 O 0.900 0.850 W 0.800

- 0.750

- 0.700

u. 0.650 0

Z 0.600 ACCEPTABLE o o^s-- ' OPERATION 050REGION 5- 0.500

.0.450 0.400 (-0.6, 0.40) (0.6, 0.40) 0.350 0.300 0.250 0.200 0.150 I .

-0.80 -0.60 -0.40 -0.20 0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIAL SHAPE INDEX, Y, Figure 3.3.1-1 Axial Power Distribution - High .Trip Setpoint Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs 2, Cycle 19 COLR Page 16 of 21 -Rev. I

1.60 Pvar 2869.5 x (Ai) x (QRi) + 17.98 xTin- 10820 1.50 .. N= Al x QRi 1.40

(-0.6, 1.!3) 1.30 1.20 A( +0. 163 xA 1+1.0 1.10 1(+006, 1.1 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 33.1-2 Thermal Margin/Low Pressure Trip Setpoint - Part 1 (ASI vs. A 1 )

Calvert Cliffs 2, Cycle 19 COLRP Page 17.0if 21 Rew. I

pTrp -2869.5 x(A1) x (QR1) + 17.98 x Ti, -10820 QDNB =A1 x QR1 (1.2,1.2) 1.2 11QR,=(RTP) +0.0:

1.0 ___.

0.9 0.8 ____ _ _

0 QR1 = 0.375 x (RTP) + 0.62%

S0.6 _ _ _ _ _ _ __

0.5 '__ ___"_"__

0.4 _ /QR, = 0.9167 x (RTP) + 0.3 0.3

0. .

0.2 0.1 0.0 1 0 0 0 . 9 1 .

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. QR1) 18 of2l Page 18 of 21 Rev. I Cycle 19 Calvert Cliffs 2, Cycle COLR 19 COLR Page Rev. I

LIST OF APPROVED METHODOLOGIES

1. ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology. for Rod Burnups of 62 GWd/MTU" Advanced Nuclear Fuels Corporation, December 1991
2. BAW- 10240(P)(A), Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved

-Methods" Framatome ANP, May 2004

3. EMF 116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs" Siemens Power Corporation, February 1999 [Licensing Restriction 7]
4. EMF-92-153(P)(A), Revision 1,. "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005 5.1 EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -

Methodology Description, Volume 2 - Benchmarking Results," Siemens Power Corporation, January 1997

6. EMFW1961*(P)(A), Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000
7. EMF-2103 (P)(A), *Revision*0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors" Framatome ANP, April 2003 [Licensing Restriction 9]
8. EMF-!23 10(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water I Reactors" Framatome ANP, May 2004 [Licensing Restrictions 1, 2, 6, and 8b]
9. EMF-2328(PXA), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based" Framatome ANP, March 2001 [LicensingRestriction 4]
10. XN-NF-75-32(P)(A), Supplements 1, 2, 3 & 4, "Computational Procedure for Evaluating Fuel Rod Bowing" Exxon Nuclear Company Inc., February 1983
11. XN-NF-78-44(NP)(A), "A Generic Analysis of the.Control Rod Ejection Transient for Pressurized Water Reactors" Exxon Nuclear Company Inc., October 1983 [Licensing Restrictions 3 and8a]
12. XN-NF-79-56(P)(A), Revision I and Supplement 1, "Gadolinia Fuel Properties for LWR Fuel Safety Evaluation" Siemens Power Corporation, October 1981
13. XN-NF-82-06(P)(A), Revision I & Supplements 2, 4, and 5, "Qualification of Exxon Nuclear

'Fuel for Extended Burnup" Exxon Nuclear Company Inc., October 1986

14. XN-NF-82-21(P)(A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations" Exxon Nuclear Company Inc., August 1983 Calvert Cliffs-2, Cycle 19 COLR Page 19 of 21 Rev. I

15: XN-NF-85-92(P)(A), Revision 0, "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results" Exxon Nuclear Company Inc., September 1986;

16. 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,"

I January 1980

17. CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981
18. Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P (three parts) and CEN- 191 (B)-P)]
19. CENPD- 161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986
20. CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981
21. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983
22. CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers,"

August 1993

23. CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974
24. CEN-161-(B)-P-A, "Improvements to Fuel Evaluation Model," August 1989
25. CEN-161-(B)-P, Supplement I-P, "Improvements to Fuel Evaluation Model," April 1986
26. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and 50-318, "Safety Evaluation of Topical Report CEN- 161-(B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN- 161 (B),

Supplement 1-P)

27. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 1990
28. CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977
29. CENPD-3 87-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel"
30. CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLOTm Cladding Material in CE Nuclear Power Fuel Assembly Designs".
31. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.
32. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," SePtember 1986..
33. WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code;,

Enhancements to ANC Rod Power Recovery," April 1989.

Calvert Cliffs 2, Cycle 19 COLR Page 20 of 21 Rev. I'

34. WCAP- 16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs," August 2004.
35. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"

August 2004.

Page 21 of 21 Rev. I Cliffs 2, Calvert Cliffs 2, Cycle 19 COLR Cycle 19 COLR Page 21 of 21 Rev. I

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