Text

Core Operating Limits Report, Revision 30
	ML22305A536
Person / Time
Site:	Palo Verde
Issue date:	10/28/2022
From:	Cox M; Arizona Public Service Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	102-08522-MSC/DHD
	Download: ML22305A536 (1)
	v • d • e

Technical Specification 5.6.5(d)

Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7636 102-08522-MSC/DHD Tel: (623) 393-5753 October 28, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Docket No. STN 50-530 Unit 3 Core Operating Limits Report, Revision 30 Pursuant to PVNGS Technical Specifications, Section 5.6.5(d), enclosed is the Unit 3 Core Operating Limits Report (COLR), Revision 30, which was made effective October 21, 2022. The changes implemented by the revision are to Section 3.2.1, Linear Heat Rate (LHR) and Figure 3.2.4-2, DNBR Margin Operating Limit Based on the Core Protection Calculators.

No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew S. Cox, Licensing Department Leader, at (623) 393-5753.

Sincerely, Cox, Matthew Digitally signed by Cox, Matthew S(Z05628)

S(Z05628) Date: 2022.10.28 16:01:48 -07'00' Matthew S. Cox Department Leader, Regulatory Affairs MSC/DHD/cr

Enclosure:

Unit 3 Core Operating Limits Report, Revision 30 cc:

S. A. Morris NRC Region IV Regional Administrator D. Galvin NRC NRR Project Manager for PVNGS L. N. Merker NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure Unit 3 Core Operating Limits Report Revision 30

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Effective: October 21, 2022 Responsible Engineer Cowdin, Digitally signed by Date Cowdin, Christopher Christophe (Z12133)

Date: 2022.10.19 r (Z12133) 08:09:24 -07'00' Design Verifier Digitally signed Date Gill, Shawn by Gill, Shawn P(Z37857)

P(Z37857) Date: 2022.10.19 08:21:59 -07'00' Responsible Section Leader McIntyre, Digitally signed Date by McIntyre, Luke Luke (Z11200)

Date: 2022.10.19 (Z11200) 11:24:25 -07'00' Page 1 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 Core Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 4.2.1 Fuel Assemblies 13 Page 2 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 19 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 20 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 21 (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 22 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 23 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 24 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 28 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 29 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 This Report has been prepared in accordance with the requirements of Technical Specifications 4.2.1 and 5.6.5. The Core Operating Limits have been developed using the NRC approved meth-odologies specified in Section 5.6.5 b of the Palo Verde Technical Specifications.

AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC) 3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR) 3.2.3 Azimuthal Power Tilt (Tq) 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 3.2.5 Axial Shape Index (ASI) 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 4.2.1 Fuel Assemblies Page 5 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

T.S Revision / Fuel Report No. Date Title Ref#a Supplement Applicability CENPD-0190- N.A. / N.A. January CE Method for Control Element Assem- Westinghouse 1 A 1976 bly Ejection Analysis Framatome (N001-1301-01204)

CENPD-266- N.A. / N.A. April 1983 The ROCS and DIT Computer Codes for Westinghouse 2 P-A Nuclear Design Framatome (N001-1900-01412)

NUREG-0852 N.A. / N.A. November Safety Evaluation Report related to the Westinghouse 3

1981 Final Design of the Standard Nuclear Framatome N.A. / 1 March 1983 Steam Supply Reference Systems Westinghouse 3 CESSAR System 80, Docket No. STN Framatome 50-470 N.A. / 2 September Westinghouse 3

1983 Framatome N.A. / 3 December Westinghouse 3

1987 Framatome CEN-356(V)- 01-P-A / N.A. May 1988 Modified Statistical Combination of Westinghouse 4 P-A Uncertainties Framatome (N001-1303-01747)

Enclosure 1-P N.A. / 1-P February System 80TM Inlet Flow Distribution Westinghouse 4

to LD-82-054 1993 (N001-1301-01228) Framatome CENPD-132 P N.A. / N.A. August Calculative Methods for the C-E Large Westinghouse 5

1974 Break LOCA Evaluation Model CENPD-132P N.A./ 1 February Calculational Methods for the C-E Large Westinghouse 5

1975 Break LOCA Evaluation Model CENPD-132-P N.A. / 2-P July 1975 Calculational Methods for the C-E Large Westinghouse 5

Break LOCA Evaluation Model CENPD-132 N.A. / 3-P-A June 1985 Calculative Methods for the C-E Large Westinghouse 5 Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS CENPD-132 N.A. / 4-P-A March 2001 Calculative Methods for the CE Nuclear Westinghouse Rev. 1 Power Large Break LOCA Evaluation 5

Model (N001-1900-01192)

Page 6 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 T.S Revision / Fuel Report No. Date Title Ref#a Supplement Applicability CENPD-132- N.A. / 4-P-A August Calculative Methods for the CE Nuclear Westinghouse P-A Addendum 1-P- 2007 Power Large Break LOCA Evaluation 5

A Model (N001-0205-00046)

CENPD-132 N.A. / December Revision 4 to the Supplement to Appen- Westinghouse 5 SUPP 4-P-A 2008 dix A of CENPD-132 Supplement 4-P-A APP A-Rev. 004 (N001-0205-00229)

CENPD-137-P N.A. / N.A. August Calculative Methods for the C-E Small Westinghouse 6 1974 Break LOCA Evaluation Model CENPD-137 N.A. / 1-P January Calculative Methods for the C-E Small Westinghouse 6

1977 Break LOCA Evaluation Model CENPD-137 N.A. / 2-P-A April 1998 Calculative Methods for the ABB C-E Westinghouse 6 Small Break LOCA Evaluation Model (N001-1900-01185)

N.A. N.A. / N.A. June 13, Letter: O.D. Parr (NRC) to F. M. Stern Westinghouse 1975 (CE), (NRC Staff Review of the 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

N.A. N.A. / N.A. September Letter: K. Kniel (NRC) to A. E. Scherer Westinghouse 27, 1977 (CE), (Evaluation of Topical Reports 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

CEN-372-P-A N.A. / N.A. May 1990 Fuel Rod Maximum Allowable Pressure Westinghouse 9

(N001-0201-00026)

N.A. N.A. / N.A. April 10, Letter: A. C. Thadani (NRC) to A. E. Westinghouse 1990 Scherer (CE), ("Acceptance for 10 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

NFM-005 1 / N.A. August Arizona Public Service Company PWR Westinghouse 2007 Reactor Physics Methodology Using Framatome 11 CASMO-4/SIMULATE-3 (NFM-005)

CENPD-282- 2 / N.A. March 2005 Technical Description Manual for the Westinghouse 12 P-A Vols. 1 CENTS Code Volume 1 Framatome (CENTS-TD MANUAL-VOL 1)

CENPD-282- 2 / N.A. March 2005 Technical Description Manual for the Westinghouse 12 P-A Vols. 2 CENTS Code Volume 2 Framatome (CENTS-TD MANUAL-VOL 2)

Page 7 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 T.S Revision / Fuel Report No. Date Title Ref#a Supplement Applicability CENPD-282- 2 / N.A. March 2005 Technical Description Manual for the Westinghouse 12 P-A Vols. 3 CENTS Code Volume 3 Framatome (CENTS-TD MANUAL-VOL 3)

CENPD-282- 2 / N.A. March 2005 Technical Description Manual for the Westinghouse 12 P-A Vols. 4 CENTS Code Volume 4 Framatome (CENTS-TD MANUAL-VOL 4)

CENPD-404- 0 / N.A. November Implementation of ZIRLOTM Cladding Westinghouse P-A 2001 Material in CE Nuclear Power Fuel 13 Assembly Designs (N001-1900-01329)

CENPD- 0 / N.A. July 2006 Optimized ZIRLOTM Westinghouse 404-P-A (N001-0203-00611) 13 Addendum 1-A CENPD- 0 / N.A. October Westinghouse Clad Corrosion Model for Westinghouse 404-P-A 2013 ZIRLO and Optimized ZIRLOTM 13 Addendum (N001-0205-00006) 2-A CENPD-188- N.A. / N.A. July 1976 HERMITE, A Multi-Dimensional Westinghouse A Space-Time Kinetics Code for PWR Framatome 14 Transients (HERMITE-TOPICAL)

CENPD-161- N.A. / N.A. April 1986 TORC Code, A Computer Code for Westinghouse P-A Determining the Thermal Margin of a 15 Reactor Core (N001-1301-01202)

CEN-160(S)-P 1-P / N.A. September CETOP-D Code Structures and Model- Westinghouse 1981 ing Methods for San Onofre Nuclear Framatome 16 Generating Station Units 2 and 3 (N001-1301-01185)

N.A. N.A. / N.A. September Safety Evaluation related to Palo Verde Westinghouse 29, 2003 Nuclear Generating Station, Unit 2 Framatome (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and 17 Uprated Power Operation, (September 29, 2003)

Page 8 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 T.S Revision / Fuel Report No. Date Title Ref#a Supplement Applicability N.A. N.A. / N.A. November Safety Evaluation related to Palo Verde Westinghouse 16, 2005 Nuclear Generating Station, Units 1, 2, Framatome and 3 - Issuance of Amendments Re:

17 Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005).

CEN-310-P-A 0 / N.A. April 1986 CPC Methodology Changes for the CPC Westinghouse 18 Improvement Program Framatome (N001-1303-02283)

CENPD-183- 0 / N.A. June 1984 Loss of Flow, C-E Methods for Loss of Westinghouse 19 A Flow Analysis Framatome (N001-1301-01203)

CENPD-382- 0 / N.A. August Methodology for Core Designs Contain- Westinghouse 20 P-A 1993 ing Erbium Burnable Absorbers (N001-0201-00035)

CEN-386-P-A 0 / N.A. August Verification of the Acceptability of a 1- Westinghouse 1992 Pin Burnup Limit of 60 MWD/kgU for 21 Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)

WCAP- 0 / N.A. August CE 16x16 Next Generation Fuel Core Westinghouse 22 16500-P-A 2007 Reference Report (N001-0203-00614)

WCAP- 0 / 1 Rev 1 December Application of CE Setpoint Methodol- Westinghouse 16500-P-A 2010 ogy for CE 16x16 Next Generation Fuel Framatome 22 (NGF)

(N001-0205-00063)

WCAP- 0 / 2-P-A June 2016 Evolutionary Design Changes to CE Westinghouse 16500-P-A 16x16 Next Generation Fuel and Method for Addressing the Effects of 22 End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (N001-0205-00048)

WCAP- 0 / N.A. October VIPRE-01 Modeling and Qualification Westinghouse 14565-P-A 1999 for Pressurized Water Reactor Framatome 23 Non-LOCA Thermal-Hydraulic Safety Analysis (N001-0205-00002)

WCAP- 0 / N.A. August Addendum 1 to WCAP-14565-P-A Westinghouse 14565-P-A, 2004 Qualification of ABB Critical Heat Flux 23 Addendum Correlations with VIPRE-01 Code 1-A (N001-0205-00003)

Page 9 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 T.S Revision / Fuel Report No. Date Title Ref#a Supplement Applicability WCAP- 0 / N.A. April 2008 Addendum 2 to WCAP-14565-P-A, Westinghouse 14565-P-A, Extended Applications of ABB-NV Cor-Addendum relation and Modified ABB-NV Correla-23 2-P-A tion WLOP for PWR Low Pressure Applications (N001-0205-00004)

CENPD- 0 / N.A. May 2000 ABB Critical Heat Flux Correlations for Westinghouse 24 387-P-A PWR Fuel (N001-0205-00042)

WCAP- 0 / N.A. August Westinghouse Correlations WSSV and Westinghouse 16523-P-A 2007 WSSV-T for Predicting Critical Heat 25 Flux in Rod Bundles with Side-Sup-ported Mixing Vanes (N001-0203-00615)

WCAP- 0 / N.A. August Implementation of Zirconium Diboride Westinghouse 16072-P-A 2004 Burnable Absorber Coatings in CE 26 Nuclear Power Fuel Assembly Designs (N001-0205-00226)

EMF-2103P-A 3 / N.A. June 2016 Realistic Large Break LOCA Methodol- Framatome 27 ogy for Pressurized Water Reactors EMF- 0 / N.A. March 2001 PWR Small Break LOCA Evaluation Framatome 28 2328(P)(A) Model, S-RELAP5 Based EMF- 0 / 1(P)(A) December PWR Small Break LOCA Evaluation Framatome 28 2328(P)(A) 2016 Model, S-RELAP5 Based BAW-10231P- 1 / N.A. January COPERNIC Fuel Rod Design Computer Framatome 29 A 2004 Code BAW-10241P- 2 / N.A. September BHTP DNB Correlation Applied with Framatome 30 A 2020 LYNXT (N001-0206-00200)

EPRI-NP- Mod 02 / N.A. Volume 1-4 VIPRE-01: A Thermal Hydraulic Analy- Westinghouse 31 2511-CCM-A (February sis Code for Reactor Cores Framatome 2017)

Mod 02 / N.A. Volume 5 VIPRE-01: A Thermal Hydraulic Analy- Westinghouse 31 (March sis Code for Reactor Cores Framatome 1988)

a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 10 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin (SDM) - Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.

3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.

3.1.4 - Moderator Temperature Coefficient (MTC)

The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.

3.1.5 - Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.

3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1, 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.1, 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:

a) Regulating Group 4 position is between 60 and 150 inches withdrawn.

Page 11 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).

3 Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and

>145.25 (RSPT indication). No further CEA withdrawal above FW is required for CEAs to meet the Transient Insertion Limit (TIL) requirements.

3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.

3.2.1 - Linear Heat Rate (LHR)

The linear heat rate limit shall be maintained in accordance with core burnup:

13.1 kW/ft for burnup < 450 EFPD

12.1 kW/ft for burnup 450 EFPD 3.2.3 - Azimuthal Power Tilt (Tq)

The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.

3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)

COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.

COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.

COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 12 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 3.2.5 - Axial Shape Index (ASI)

The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS OPERABLE

-0.18 AS 0.17 for power > 50%

-0.28 < ASI < 0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)

-0.10 ASI 0.10 for power >20%

3.3.12 - Boron Dilution Alarm System (BDAS)

With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.

3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 3000 ppm.

4.2.1 - Fuel Assemblies The Reactor Core contains the following fuel types:

Westinghouse CE16STD with ZIRLO' cladding

Westinghouse CE16NGF with Optimized ZIRLO' cladding

No lead test assemblies Refer to the ANALYTICAL METHODS Table for the methods applicable to a particular fuel type.

Page 13 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7

6 (500, 5.0) 5 REGION OF ACCEPTABLE SHUTDOWN MARGIN (% K/K)

OPERATION 4

3 REGION OF UNACCEPTABLE 2

OPERATION 1

(350, 1.0) 0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (F)

Page 14 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7

(500, 6.5) 6 REGION OF ACCEPTABLE 5

OPERATION SHUTDOWN MARGIN (% K/K) 4 (350, 4.0) 3 REGION OF UNACCEPTABLE 2

OPERATION 1

0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (F)

Page 15 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 (0%,0.5)

(100%,0) 0.0 (50%, 0.0)

-0.5 (100%,-0.2)

MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)

-1.0

-1.5 MTC AREA OF ACCEPTABLE

-2.0 OPERATION

-2.5

-3.0

-3.5

-4.0 (0%,-4.4) (100%,-4.4)

-4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit Page 16 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

20 20 16 100% to

>80% RTP 15 15 MINIMUM REQUIRED POWER REDUCTION 12 12 80% to

>70% RTP 10 10

(% OF RATED THERMAL POWER) 9 8 8 70% to

>45% RTP 6 6 5 5 4 4 4 45% RTP 3

3 2 2 1

0 0

0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES

WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:

- > 95 % RATED THERMAL POWER

- COLSS IN SERVICE AND CEACS IN SERVICE

- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %

- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 17 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE:

See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.

0.9 To meet the Transient Insertion Limit (TIL) all conditions below must be met:

0.8 CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.

AND CEA Group 3 must be fully withdrawn* for TRANSIENT INSERTION LIMIT FRACTION OF RATED THERMAL POWER 0.7 power levels 20%.

CEA Group 3 must be withdrawn 60" for power 0% and < 20%.

AND GROUP 5 60 INCHES CEA Group 4 must be fully withdrawn* for GROUP 5 108 INCHES 0.6 power levels 70.87%.

CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:

0.5 TIL4 = (172.5" x Fractional Power) + 25.5" (for power 20% and < 70.87%).

AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph SHORT TERM STEADY STATE INSERTION LIMIT 0.4 LONG TERM STEADY STATE INSERTION LIMIT or by the equation:

TIL5 = (172.5" x Fractional Power) - 64.5" (for power 37.39% and 100%).

0.3 0.2 GROUP 3 60 INCHES 0.1 0.0 GROUP 5 GROUP 3 GROUP 1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 150* 120 90 60 30 0 150* 120 90 60 30 0 CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).

No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.

Page 18 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:

See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.

0.9 To meet the Transient Insertion Limit (TIL) all conditions below must be met:

0.8 CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.

AND CEA Group 3 must be fully withdrawn* for TRANSIENT INSERTION LIMIT FRACTION OF RATED THERMAL POWER 0.7 power levels 20%.

CEA Group 3 must be withdrawn 60" for power 0% and < 20%.

AND CEA Group 4 must be fully withdrawn* for GROUP 5 108 INCHES 0.6 power levels 54.97%.

CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:

0.5 TIL4 = (250.9" x Fractional Power) + 9.82" (for power 20% and < 54.97%).

GROUP 5 60 INCHES AND CEA Group 5 must be withdrawn the 0.4 group 5 TIL (TIL5) as indicated on the graph LONG TERM STEADY STATE INSERTION LIMIT or by the equations:

SHORT TERM STEADY STATE TIL5 = (250.9" x Fractional Power) - 80.18" (for power 31.96% and 75.00%).

TIL5 = 108" (for power lever 75.00%).

0.3 INSERTION LIMIT 0.2 GROUP 3 60 INCHES 0.1 0.0 GROUP 5 GROUP 3 GROUP 1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 150* 120 90 60 30 0 150* 120 90 60 30 0 CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).

No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.

Page 19 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN) 40.0 50.0 60.0 70.0 TRANSIENT INSERTION LIMIT (75.0 INCHES) 80.0 (50% RATED THERMAL POWER) 90.0 OPERATION OPERATION UNACCEPTABLE RESTRICTED 100.0 110.0 LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES) 120.0 130.0 OPERATION ACCEPTABLE 140.0 150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 20 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGION OF UNACCEPTABLE OPERATION AZIMUTHAL POWER TILT (%)

10.0 5.0 REGION OF ACCEPTABLE OPERATION 0.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 21 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95, 20) 20 COLSS DNBR POWER OPERATION LIMIT REDUCTION 15

(% OF RATED THERMAL POWER) 10 5

(80, 5)

(70, 0) 0 50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0.06, 2.38) (0.1, 2.38) 2.3

(-0.1, 2.28)

CPC MINIMUM DNBR 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN 2.1 EACH OPERABLE CPC CHANNEL (0.05, 2.00) 2.0 (0.1, 2.00)

(-0.1, 1.93) UNACCEPTABLE 1.9 OPERATION 1.8

-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 23 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL) 3.6 ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 IN ANY OPERABLE CPC CHANNEL (0.0, 3.41) (0.1, 3.41) 3.4 CPC MINIMUM DNBR 3.3

(-0.1, 3.27) 3.2 UNACCEPTABLE OPERATION 3.1 3.0

-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 24 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 Keff > 0.97 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 Keff > 0.96 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Keff > 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 28 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ONA 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 29 of 29

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