Text

Core Operating Limits Report (Colr), Revision 25, 21, and 24, Respectively
	ML18102B685
Person / Time
Site:	Palo Verde
Issue date:	04/12/2018
From:	Dilorenzo M; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-07682-MSC/MDD
	Download: ML18102B685 (91)
	v • d • e

Technical Specification 5.6.5.d Oaps Palo Verde Nuclear Generating Station 5871 S. Wintersburg Road Tonopah, AZ 85354 102-07682-MSC/MDD April 12, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 25 Unit 2 Core Operating Limits Report (COLR), Revision 21 Unit 3 Core Operating Limits Report (COLR), Revision 24

Dear Sirs:

Pursuant to Palo Verde Nuclear Generating Station (PVNGS) Technical Specifications, Section 5.6.5.d, enclosed are the Units 1, 2, and 3 Core Operating Limits Report (COLR),

Revisions 25, 21, and 24, respectively, which were made effective April 6, 2018. The change implemented by these revisions includes the following:

Revision to Analytical Methods to add the references associated with Westinghouse Next Generation Fuel (NGF).

Administrative and editorial corrections made for clarity.

These changes affect several pages. Revision bars have been applied to the changes.

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 Section Leader at (623) 393-5753.

Sincerely, Michael D. DiLorenzo Nuclear Regulatory Affairs Department Leader MSC/MDD/TMJ/sma

Enclosures:

Unit 1 Core Operating Limits Report, Revision 25 Unit 2 Core Operating Limits Report, Revision 21 Unit 3 Core Operating Limits Report, Revision 24 cc:

K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)

Revision 25

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNITl CORE OPERATING LIMITS REPORT Revision 25 Effective April 6, 2018 Responsible Engineer Date Wenzel, J DN:cn=Wenzel, Richard Rirh::^rrl /\R(Z99534) rVIV-llOILJ jj Re^on: lam the author of y?^thisdocument R(Z995J4)

Independent Reviewer

1 (j G 1 SZ1 0 r, (P Digitally signed by Geiszler, 11 Keliy J(Z07064)

Date )1 DN: cn=Geiszler, Kelly KpIIv /\j(Z07064) 1 vC *

y //_K _ document) Reason: 1 have reviewed this J{Z0706J^)

Responsible Section Leader ^9 r 1 S 0 n ^ li plgl,3lly Oiatles Date 1 Ef(V55086) 1^ ^ ^ 1 ^ C jj \DN: cn=Karlson, Charles F(V55086)

^ 1 1 cl 1 1^0 jJ R^on: lam approving this M do^n^jit=sa^

r- l\ Mw~ r-^0^8.04.03 08:25:18-07'00' F(V55086) ----------------------------------------------------------------------------------------------------------------------- 1 Page 1 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 Eleat 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 (ASl) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 Page 2 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 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 Eimits Versus Thermal Power (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Eimits 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 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 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 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 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 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Technical Specifications.

AFFECTER 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 Page 5 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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-approyed analytical methods used to determine the core operating limits, described in the following documents:

T.S Title Report No. Rev Date Suppl Ref#^

CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (NOOl-1301-01204)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (NOOl-1900-01412)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September 0

J 1983 L CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (NOOl-1303-01747)

System 80' Inlet Flow Distribution Enclosure N.A. February 1-P 4 (NOOl-1301-01228) 1-P toLD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A 5 Break LOCA Evaluation Model 132 2001 Rev. 1 (NOOl-1900-01192)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (NOOl-1900-01185)

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

Page 6 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l T.S Title Report No. Rev Date Suppl Ref#"

Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27,1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

9 (NOO1-0201-00026) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

Scherer (CE), ("Acceptance for 1990 10 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 1 August N.A.

Reactor Physics Methodology Using 2007 11 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

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

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

12 CENTS Code Volume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation ofZIRLO^^ Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 13 Assembly Designs (NOOl-1900-01329)

Optimized ZIRLO^^^ CENPD- 0 July 2006 N.A.

(NOOl-0203-00611) 404-P-A 13 Addendum 1-A Westinghouse Clad Corrosion Model for CENPD- 0 October N.A.

ZIRLO and Optimized ZIRLOTM 404-P-A 2013 13 (NOO 1-0205-00006) Addendum 2-A Page 7 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l T.S Title Report No. Rev Date Suppl HERMITE, A Multi-Dimensional CENPD- N.A. July N.A.

Space-Time Kinetics Code for PWR 188-A 1976 14 Transients (HERMITE-TOPICAL)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

Determining the Thermal Margin of a 161-P-A 1986 15 Reactor Core (NOOl-1301-01202)

CETOP-D Code Structures and Model CEN- 1-P September N.A.

ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3 (NOOl-1301-01185)

Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29,2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29,2003) and November 17 Safety Evaluation related to Palo Verde 16,2005 Nuclear Generating Station, Units 1,2, and 3 - Issuance of Amendments Re:

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

CPC Methodology Changes for the CPC CEN-310- 0 April N.A.

18 Improvement Program P-A 1986 (NOOl-1303-02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.

19 Flow Analysis 183-A 1984 (NOOl-1301-01203)

Methodology for Core Designs Contain CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)

Page 8 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l Ref#^ Title Report No. Rev Date Suppl Verification of the Acceptability of a 1- CEN-386- August N.A.

Pin Burnup Limit of 60 MWD/kgU for P-A 1992 Combustion Engineering 16x16 PWR Fuel (NOO1-0201-00042)

CE 16x16 Next Generation Fuel Core WCAP- August N.A.

Reference Report 16500-P-A 2007 (NOO 1-0203-00614)

Application of CE Setpoint Methodol WCAP- December ogy for CE 16x16 Next Generation Fuel 16500-P-A 2010 (NGF)

(NOOl-0205-00063)

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

VIPRE-01 Modeling and Qualification WCAP- October N.A.

for Pressurized Water Reactor 14565-P-A 1999 23 Non-EOCA Thermal-Hydraulic Safety Analysis (NOO1-0205-00002)

Addendum 1 to WCAP-14565-P-A WCAP- August N.A.

Qualification of ABB Critical Heat Flux 14565-P-A, 2004 Correlations with VlPRE-01 Code Addendum (NOOl-0205-00003) 1-A Addendum 2 to WCAP-14565-P-A, WCAP- April 2008 N.A.

Extended Applications of ABB-NV Cor 14565-P-A, relation and Modified ABB-NV Correla Addendum 23 tion WLOP for PWR Eow Pressure 2-P-A Applications (NOOl-0205-00004)

ABB Critical Heat Flux Correlations for CENPD- May 2000 N.A.

PWR Fuel 387-P-A (NOO1-0205-00042)

Page 9 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l T.S Title Report No. Rev Date Suppl Ref#^

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

Implementation of Zirconium Diboride WCAP- 0 August N.A.

Burnable Absorber Coatings in CE 16072-P-A 2004 26 Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin rSDM) - 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 CSOM) - 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 ('MTO 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 rCEAl 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 limits' shown in Figure 3.1.7-1^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-2.^

Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn' ^ 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.' ^

' 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 .

^ 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 1 CORE OPERATING LIMITS REPORT Revision 25 l 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).

^ 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 of 13.1 kW/ft shall be maintained.

3.2.3 - Azimuthal Power Tilt ITgl 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 lONBR^

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 1 CORE OPERATING LIMITS REPORT Revision 25 l 3.2.5 - Axial Shape Index TASD The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS OPERABLE

-0.18 < ASI <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.

Page 13 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN (500,5.0ll REGION OF ACCEPTABLE OPERATION REGIONiOF UNACCEPTABLE OPERATION (350, 1.0)

COLD LEG TEMPERATURE (°F)

Page 14 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500, 6.5)

RE GION OF AC CEPTABLl5 OPERATION

<3 g (350, 4.0)

O 02 Z

o Q

H Z

00 REGION 0 F UNACCEP tABLE OPERATIC i............... i......... .

100 200 300 400 500 600 COLD LEG TEMPERATURE (°E)

Page 15 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 V***

(I00%,0)

(50%, 0.0)

MTGAREAGF ACCEPTABLE OPERATION

< -3.0 (100%,-4.4 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 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

^<100% to

>80% RTF

<80% to

>70% RTF

<70% to

>45% RTF

^5% RTF 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 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)

NOTE:

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

0.9 To meet tbe 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 M power levels >20%.

CEA Group 3 must be withdrawn > 60 for o

a.

power >0% and <20%.

AND

< 0.6 CEA Group 4 must be > fully withdrawn* for S power levels > 70.87%.

oc CEA Group 4 must be withdrawn > the u

X H group 4 TIL (TIL4) as indicated on the graph G or by the equation:

[S T1L4 = (172.5" X Fractional Power) + 25.5" (for power > 20% and < 70.87%).

PS AND H. CEA Group 5 must be withdrawn > the O

0.4 group 5 TIL (TIL5) as indicated on the graph z or by the equation:

o TIL5 = (172.5" X Fractional Power) - 64.5" (for power > 37.39% and < 100%).

a: 0.3 u.

0.1 0.0 GROUP 5 GROUP 3 GROUP1 I 1 -I I- I 1- 1 I- -I 1- 1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 I-I---1-----1---- 1----1 I----1---- 1---- 1---- 1---- 1 150* 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 TIE requirements.

Page 18 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)

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 M power levels >20%.

CEA Group 3 must be withdrawn > 60 for I

< 0.6 power > 0% and < 20%.

AND CEA Group 4 must be > fully withdrawn* for QC power levels > 54.97%.

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

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

e: AND tL. CEA Group 5 must be withdrawn > the o 0.4 group 5 TIL (TIL5) as indicated on the graph 2;

or by the equations: ,

o ill., TIL5 = (250.9" X Fractional Power) - 80.18" u

0.3 iiii (for power > 31.96% and < 75.00%).

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

!§isi 0.0 GROUP 5 GROUP 3 GROUP1 I----1----1----i- -I- I--- 1----1----1--- -I I--- i- -I--- 1----i----1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP4 GROUP 2 I -I---1-----1---- 1---- 1 I----1-----1---- 1---- 1---- 1 150* 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 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 z

40.0 Q

K 50.0 c/5 W

X 60.0 o

z z 70.0 TRANSIENT INSERTION LIVIIT (75.0 NCHES).

o o 80.0

.. . 1 Oh w

u X

a

§ a

H 00 H

90.0 100.0 OPERAT^O^

UNACCEPT/

1

.. 1 1 a, H

W c<<

Oij H

ATIG?i.......

iuCTEp Qi 110.0

" h" a a G

° s B g B insaaBBB O h oaBDBBe

LoivfG TER A STEA DY ST/ cTE INSERTIOI *C/5 Ifx LIMIT ^ K)

§ K U PJ s) :

120.0 130.0 OPERATIOI' EPTAI5LE 140.0 150.0 i . . . . i . . . .

0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.0 FRACTION OF RATED THERMAL POWER Page 20 of 29 '

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGION OF UNACCEPTABLE OPERATION g,

t-J ci w

o

0. 10.0 X

H D

S N

5.0 REGION OE 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 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)

CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l FIGURE 3.2A-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL

(-0.1,2.28)

Z 2.2 I ACCEPTABLE OPERATION ;

I POWER AT OR ABOVE 90% I 5 AT LEAST 1 CEAC OPERABLE IN ;

I EACH OPERABLE CPC CHANNELl 9 ; ; n (0.05, 2.00)

UNACCEPTABLE OPERATION CORE AVERAGE ASI Page 23 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 FIGURE 3.2A-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OE SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)

ACCEPTABLE OPERATION ANY POWER LEVEL l BOTH CEACs INOPERABLE 3.5 IN ANY OPERABLE CPC CHANNEL a:

PQ z

Q 3.3 IZ I (-0.1;,3.27) i o

3.2 i UNACCEPTABLE OPERATION 3.1 3.0

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 > K^ff > 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 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 > K^ff > 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 I hour 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 ON A = Operation Not Allowed Page 27 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l Table 3.3.12-4 REQUIRED MONTTORWG FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 > Ke^> 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 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 ON A = Operation Not Allowed Page 28 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l 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 K^ff < 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

Enclosure PVNGS Unit 2 Core Operating Limits Report (COLR)

Revision 21

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 Effective April 6, 2018 Responsible Engineer Date Wenzel, '

CSSSS"""'

U DN: cn=Wenzel, Richard Rirh;^rH AP(Z99534)

I'lV-l IQI^ H R^son: 1 am the author of this j/^,^d(^umGriDi R(Z9953^)

1 (P Digitally signed by Geiszler, Independent Reviewer beiSZler, l} KeHyJ(Z07064)

Date DN: cn=Geiszler, Kelly KpIIv /\j(Z07064) l\d 1 y // Reason: 1 have reviewed this

//,^documGrit>

J(Z070^) 08:14:38 Responsible Section Leader Digitally signed by Karlson, Charle:

Date 1 I\F(V55086) 1 h ^ ^1 OC // cn=Karlson, Charles F(V55086) 1 1 Cl 1 1^^ II Reason: i am approving this

// dement =3s^

F(V550>)

Page 1 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 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 2 3.2.1 Linear Heat Rate (LHR) 2 3.2.3 Azimuthal Power Tilt (Tq) 2 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 Page 2 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 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 (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 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 Kefl^ 0.98 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 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 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 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies 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 Page 5 of29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 Title Report No. Rev Date Suppl Ref#^

CE Method for Control Element Assem CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (NOOl-1301-01204)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (NOOl-1900-01412)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September 3 1983 2 CESSAR System 80, Docket No. STN 50-470 December 1987 3

/

Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (NOOl-1303-01747)

System 80' Inlet Flow Distribution Enclosure N.A. February 1-P 4 (NOOl-1301-01228) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A 5 Break LOCA Evaluation Model 132 2001 Rev. 1 (NOOl-1900-01192)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (NOOl-1900-01185)

Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

Page 6 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l T.S Title Report No. Rev Date Suppl Ref#"*

Letter; K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P).NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

9 (NOO1-0201-00026) P-A 1990 Letter; A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

Scherer (CE), ("Acceptance for 1990 10 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 1 August N.A.

Reactor Physics Methodology Using 2007 11 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

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

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

12 CENTS Code Volume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLO^^ Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 13 Assembly Designs (NOOl-1900-01329)

Optimized ZIRLO' CENPD- 0 July 2006 N.A.

(NOO1-0203-00611) 404-P-A 13 Addendum 1-A Westinghouse Clad Corrosion Model for CENPD- 0 October N.A.

ZIRLO and Optimized ZIRLO' 404-P-A 2013 13 (NOOl-0205-00006) Addendum 2-A Page 7 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l T.S Title Renort No. Rev Date Suppl Ref#""

HERMITE, A Multi-Dimensional CENPD- N.A. July N.A.

Space-Time Kinetics Code for PWR 188-A 1976 14 Transients (HERMITE-TOPICAE)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

Determining the Thermal Margin of a 161-P-A 1986 15 Reactor Core (NOOl-1301-01202)

CETOP-D Code Structures and Model CEN- 1-P September N.A.

ing Methods for San Onofre Nuclear 160(S)-P 1981

, 16 Generating Station Units 2 and 3 (NOOl-1301-01185)

Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29,2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) and November 17 Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1,2, and 3 - Issuance of Amendments Re:

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

CPC Methodology Changes for the CPC CEN-310- 0 April N.A.

18 Improvement Program P-A 1986 (NOOl-1303-02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.

19 Flow Analysis 183-A 1984 (NOOl-1301-01203)

Methodology for Core Designs Contain CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOOl-0201-00035)

Page 8 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l T.S Suppl Title Report No. Rev Date Ref#^

Verification of the Acceptability of a 1- CEN-386- August N.A.

Pin Bumup Limit of 60 MWD/kgU for P-A 1992 Combustion Engineering 16x16 PWR Fuel (NOO1-0201-00042)

CE 16x16 Next Generation Fuel Core WCAP- August N.A.

Reference Report 16500-P-A 2007 (NOOl-0203-00614)

Application of CE Setpoint Methodol WCAP- December ogy for CE 16x16 Next Generation Fuel 16500-P-A 2010 (NGF)

(NOO 1-0205-00063)

Evolutionary Design Changes to CE WCAP- June 2016 2-P-A 16x16 Next Generation Fuel and Method 16500-P-A for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOO 1-0205-00048)

VIPRE-01 Modeling and Qualification WCAP- October N.A.

for Pressurized Water Reactor 14565-P-A 1999 Non-LOCA Thermal-Hydraulic Safety Analysis (NOOl-0205-00002)

Addendum 1 to WCAP-14565-P-A WCAP- August N.A.

Qualification of ABB Critical Heat Flux 14565-P-A, 2004 Correlations with VIPRE-01 Code Addendum (NOO1-0205-00003) 1-A Addendum 2 to WCAP-14565-P-A, WCAP- April 2008 N.A.

Extended Applications of ABB-NV Cor 14565-P-A, relation and Modified ABB-NV Correla Addendum 23 tion WLOP for PWR Low Pressure 2-P-A Applications (NOO 1-0205-00004)

ABB Critical Heat Flux Correlations for CENPD- May 2000 N.A.

PWR Fuel 387-P-A (NOOl-0205-00042)

Page 9 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l T.S Title Report No. Rev Date Suppl Ref#"*

Westinghouse Correlations WSSV and WCAP- 0 August N.A WSSV-T for Predicting Critical Heat 16523-P-A 2007 25 Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOO1-0203-00615)

Implementation of Zirconium Diboride WCAP- 0 August N.A.

Burnable Absorber Coatings in CE 16072-P-A 2004 26 Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)

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

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 ISDMl - 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 IMTCl 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 ICEAl 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 limits' shown in Figure 3.1.7-!^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 3.1.7-2.^

Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn ^ 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. ^

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 .

^ 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 II of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 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).

^ 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 rLHRI The linear heat rate limit of 13.1 kW/ft shall be maintained.

3.2.3 - Azimuthal Power Tilt ITgl 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 (ONBRI 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 mOPERABEE.

Page 12 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 3.2.5 - Axial Shape Index rASI)

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

COLSS OPERABLE

-0.18 < ASI <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 IBDAS')

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.

Page 13 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN (500, 5.0j REGION OF ACCEPTABLE OPERATION O 3 REGION UNACCEPTABLE OPERATION (350, 1.0)

COLD LEG TEMPERATURE (°F)

Page 14 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500, 6.5)

RE GION OF AC CEPTABLI5 OPERATION

<1 g,

g0 (350,4.0) oi.

S z

1 Q

X on REGION 0 F UNACCEP FABLE OPERATIC>N

....................... 1 1............ .. i.....................1 i..................

1 ........................

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

Page 15 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 (0%,0.5)

(100%,0)

(50%, p.O)

MTG AREAGF ACCEPTABLE OPERATION

< -3.0 (0%,-4. (10p%,-4.4 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 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

'<100% to

>80% RTP

<80% to

>70% RTP

^70% to

>45% RTP

^5% RTP 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 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)

NOTE:

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

0.9 To meet tbe 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 02 CEA Group 3 must be > fully withdrawn* for U

0.7 power levels >20%.

CEA Group 3 must be withdrawn > 60" for o

a.

power >0% and <20%.

J AND

< CEA Group 4 must be > fully withdrawn* for S

02 power levels > 70.87%.

U CEA Group 4 must be withdrawn > the X

H group 4 TIL (TIL4) as indicated on the graph Q or by the equation:

U TIL4 = (172.5" X Fractional Power) + 25.5" H (for power > 20% and < 70.87%).

OC AND tt. CEA Group 5 must be withdrawn > the O

group 5 TIL (TIL5) as indicated on the graph

§ or by the equation:

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

02 H.

0.0 GROUP 5 GROUP 3 GROUP1 I ^ 1- 1 -I- 1 -I 1 -I -I- -I 1- 1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2

-I----1----1---- 1---- 1 I----1-----1-----1---- 1---- 1 150* 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 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)

NOTE:

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

0.9 To meet tbe 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 power levels >20%.

CEA Group 3 must be withdrawn > 60" for 2 power >0% and <20%.

AND

< 0.6 CEA Group 4 must be > fully withdrawn* for sOL power levels > 54.97%.

U CEA Group 4 must be withdrawn > the K group 4 TIL (TIL4) as indicated on the graph H

Q or by the equation:

U TIL4 = (250.9" X Fractional Power) + 9.82" H

(for power >20% and < 54.97%).

a: AND

u. CEA Group 5 must be withdrawn > the o group 5 TIL (TIL5) as indicated on the graph z or by the equations:

o TIL5 = (250.9" X Fractional Power) - 80.18" o (for power > 31.96% and < 75.00%).

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

u. fill 0.1 0.0 GROUP 5 GROUP 3 GROUP1 I 1- 1 -I I- I 1- I- -I- 1 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 GROUP 4 GROUP 2

-I---- 1--- 1---- 1----1 I----1---- 1-----1---- 1---- 1 150* 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 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 z 40.0 OS Q

K H 50.0 c/5 U

X 60.0 u

z z 70.0 TRANSIENTINSER'hON LIVIIT (75.0 NCHES).

o c/5 o 80.0 0.

w u

o 90.0 OPER AT^O^ [t 1

..................J.

OPER ATIO?1............

X H

0 UNAC CEPT/ABLE iw REST]iilCTE D z

w 100.0 oc H

s c/5 H

01 110.0

< ^ a a BB B B n D B a o a B o a a a B B 1 1 B BBBaa aaaaaaB

a. i LorvlG TER]Mstea DY ST/ cTE INSERTIO^ LIMIT S (112.5 INCHE s) :

120.0 130.0 OPER ATIOr'} ACClEPTAIlLE 140.0 150.0 . . . . 1i . . . . 1i . . . .

0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.0 FRACTION OF RATED THERMAL POWER Page 20 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGION OF UNACCEPTABLE OPERATION H

02 U

O 10.0 (X

5 sN 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 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)

U.}

(80, 5)

CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0.;06, 2.38) (0.1,2.38)

(-0.1,2.28)

Z 2.2

ACCEPTABLE OPERATION \

^ if

POWER AT OR ABOVE 90% ?

I : ; ; ?

AT LEAST I CEAC OPERABLE IN ?

I EACH OPERABLE CPC CHANNELj (0.05, 2.00)

(-0.1,1.93) ; UNACCEPTABLE OPERATION CORE AVERAGE ASI Page 23 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l 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)

ACCEPTABLE OPERA TION ANY POWER 1,EVEL BOTH CEACs ] NOPER-ABLE IN AN'Y OPER^

rw 03 n O CHAN]NEL Ann 'XAw os 2;

Q s

i 3.3 Z

I (-0.1i, 3.27) u a

u 3.2 UNAC S fLE OPERi H 1 3.1 3.0 ...........i i........... i............ i........... i...........

-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 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 Kgff > 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 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 > K^ff > 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 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 > K^ff > 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 2 CORE OPERATING LIMITS REPORT Revision 21 l 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 < 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

Enclosure PVNGS Unit 3 Core Operating Limits Report (COLR)

Revision 24

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 Effective April 6, 2018 Responsible Engineer Date Wenzel, CSS'" )l DN: cn=WenzeI, Richard Richard AS.,he author of

/7 ^this dooJment R(Z995^4) Da;ej0ia03.30,5:38:32 Independent Reviewer ^

LlGISZlGT, 1 Digitally signed by Geiszler, 1 Kelly J(Z07064)

Date )lDN:cn=Geiszler, Kelly KpIIV /\J(Z07064) 1 \C 1 jr u R^son; 1 have reviewed this

/^J^,>-'ddcurnent'^

J (Z070^) D=;-^20,8:04.03 08:,6:5, X ff Oigitaliy signed by Karlson Responsible Section Leader Kar son, WchanesFlVSSOSe)

Date ll DN: cn=Karlson, Charles rhArlpc: /W55086) 1 1U 1 I ^ J // R^^on: 1 am approving

,^this docurhent F(V55036)

Page 1 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l 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 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 1 3.1.7 Regulating CEA Insertion Limits 1 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 (ASl) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 Page 2 of29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l 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 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 (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 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 24 l 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 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 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 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 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 24 l This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies 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 Page 5 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l 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 Title Report No. Rev Date Suppl Ref#""

CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (NOOl-1301-01204)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (NOO1-1900-01412)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September

'X 1983 Z CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (NOOl-1303-01747)

System 80' Inlet Flow Distribution Enclosure N.A. February 1-P 4 (NOOl-1301-01228) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A 5 Break LOCA Evaluation Model 132 2001 Rev. 1 (NOOl-1900-01192)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (NOOl-1900-01185)

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

Page 6 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l T.S Title Report No. Rev Date Suppl Ref#""

Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27,1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

9 (NOO1-0201-00026) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

Scherer (CE), ("Acceptance for 1990 10 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 1 August N.A.

Reactor Physics Methodology Using 2007 11 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

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

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

12 CENTS Code Volume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLO' Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 13 Assembly Designs (NOOl-1900-01329)

Optimized ZIRLO' CENPD- 0 July 2006 N.A.

(NOOl-0203-00611) 404-P-A 13 Addendum 1-A Westinghouse Clad Corrosion Model for CENPD- 0 October N.A.

ZIRLO and Optimized ZIRLO' 404-P-A 2013 13 (NOO 1-0205-00006) Addendum 2-A Page 7 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l T.S Title Report No. Rev Date Suppl Ref#""

HERMITE, A Multi-Dimensional CENPD- N.A. July N.A.

Spaee-Time Kinetics Code for PWR 188-A 1976 14 Transients (HERMITE-TOPICAL)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

Determining the Thermal Margin of a 161-P-A 1986 15 Reactor Core (NOOl-1301-01202)

CETOP-D Code Structures and Model CEN- 1-P September N.A.

ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3 (NOOl-1301-01185)

Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29,2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29,2003) and November 17 Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:

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

CPC Methodology Changes for the CPC CEN-310- 0 April N.A.

18 Improvement Program P-A 1986 (NOOl-1303-02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.

19 Flow Analysis 183-A 1984 (NOOl-1301-01203)

Methodology for Core Designs Contain CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOOl-0201-00035)

Page 8 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l T.S Title Report No. Rev Date SuddI Ref#^

Verification of the Acceptability of a 1- CEN-386- 0 August N.A.

Pin Bumup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16x16 PWR Fuel (NOO1-0201-00042)

CE 16x16 Next Generation Fuel Core WCAP- 0 August N.A.

22 Reference Report 16500-P-A 2007 (NOOl-0203-00614)

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

(NOO1-0205-00063)

Evolutionary Design Changes to CE WCAP- 1 June 2016 2-P-A 16x16 Next Generation Fuel and Method 16500-P-A for Addressing the Effects of 22 End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOOl-0205-00048)

VIPRE-01 Modeling and Qualification WCAP- 0 October N.A.

for Pressurized Water Reactor 14565-P-A 1999 23 Non-LOCA Thermal-Hydraulic Safety Analysis (NOO 1-0205-00002)

Addendum 1 to WCAP-14565-P-A WCAP- 0 August N.A.

Qualification of ABB Critical Heat Flux 14565-P-A, 2004 23 Correlations with VlPRE-01 Code Addendum (NOOl-0205-00003) 1-A Addendum 2 to WCAP-14565-P-A, WCAP- 0 April 2008 N.A.

Extended Applications of ABB-NV Cor 14565-P-A, relation and Modified ABB-NV Correla Addendum 23 tion WLOP for PWR Low Pressure 2-P-A Applications (NOO1-0205-00004)

ABB Critical Heat Flux Correlations for CENPD- 0 May 2000 N.A.

24 PWR Fuel 387-P-A (NOO1-0205-00042)

Page 9 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l T.S Title Report No. Rev Date Suppl Ref#

Westinghouse Correlations WSSV and WCAP- 0 August N.A WSSV-T for Predicting Critical Heat 16523-P-A 2007 25 Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOO1-0203-00615)

Implementation of Zirconium Diboride WCAP- 0 August N.A.

Burnable Absorber Coatings in CE 16072-P-A 2004 26 Nuclear Power Fuel Assembly Designs (NOOl-0205-00226) t

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 24 l The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin TSOM) - 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 rSDMl - 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 ('MTQ 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 ICEAl 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 limits' shown in Figure 3.1.7-!^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-2. 0 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn' ^ 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.' ^

' 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 .

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 24 l 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).

^ 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 of 13.1 kW/ft shall be maintained.

3.2.3 - Azimuthal Power Tilt ITg)

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 lONBR)

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 24 l 3.2.5 - Axial Shape Index (ASP The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS OPERABLE

-0.18 < ASI <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 (BDASI 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.

Page 13 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN (500, 5.0il RE GION OF AC CEPTABLI

<j OP ERATION g

0 01 z

o Q

H P

X (Zl (REGION OF UNACCEPTABLE OPERATION (350, I.O) i................ j..................... t..................... i................ 1..................

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

Page 14 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500, 6.5)

RE GION OF AC CEPTABL]5 OPERATION

<1 z0 I (350, 4.0) oc z

1Q z

C/3 REGION 0 F UNACCEP^FABLE OPERATIC>N

............................1 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F)

Page 15 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 (0%,0.5)

(50%, p.O)

MTGAREAGF ACCEPTABLE OPERATION (100%,-4.4 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 24 l FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

'<100% to

>80% RTF

<80% to

>70% RTF

<70% to

>45% RTF

^5% RTF 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 24 l FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)

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

<< power levels >20%.

CEA Group 3 must be withdrawn > 60" for 2 power >0% and <20%.

AND

< 0.6 CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.

CEA Group 4 must be withdrawn > the X group 4 TIL (TIL4) as indicated on the graph H

Q or by the equation:

w TIL4 = (172.5" X Fractional Power) + 25.5" H

< (for power > 20% and < 70.87%).

a AND U. CEA Group 5 must be withdrawn > the o group 5 TIL (TIL5) as indicated on the graph

§ or by the equation:

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

£ 0.3 0.1 0.0 GROUP 5 GROUP 3 GROUP1

-I--- 1--- -I----1 I- I----1--- I- l------1----1----1 150* 120 90 60 30 0 150*120 90 60 30 0 150* 120 90 60 300 GROUP 4 GROUP 2 I----1--- 1------1--1----1 I----1--- 1----1----1--- 1 150* 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 24 l FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)

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 power levels >20%.

CEA Group 3 must be withdrawn > 60" for o

0. power >0% and <20%.

-J AND

< 0.6 CEA Group 4 must be > fully withdrawn* for power levels > 54.97%.

u CEA Group 4 must be withdrawn > the group 4 TIL (TIL4) as indicated on the graph P or by the equation; w TIL4 = (250.9" X Fractional Power) + 9.82"

< (for power > 20% and < 54.97%).

a: AND tt. CEA Group 5 must be withdrawn > the o group 5 TIL (TIL5) as indicated on the graph

§ or by the equations:

& TIL5 = (250.9" X Fractional Power) - 80.18" (for power > 31.96% and < 75.00%).

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

0.0 GROUP 5 GROUP 3 GROUP 1 I 1 -I I 1 1- -I -I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP4 GROUP 2 I l---- 1---- 1----1----1 I----1---- 1-- 1----- 1----1 150* 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 24 l FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 z

40.0 a:

P X 50.0 H

c/5 W

X 60.0 u

z c-z 70.0 TRANSIEN[T INSERTION LIVilT (75.0 NCHES).

o p

00 o 80.0

< 1 w 1 o

X 90.0 ........ GPER ATIO?li...... ....... 1 GPERATIG?i........

H O

z UNAC CEPT.iVBLE s X

REST]jaCTE D p 100.0 o:

H c/5 H

(52 110.0 I

o 0.

' LorsIG TER]M STEA DYST/^TE INSERTIO^ LIMIT S (112.5 INCHE,s) :

120.0 130.0 OPERATIO^}ACC]EPTAE5LE 140.0 150.0 . . . . 1 i . . . . ............i . . . .

1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.0 FRACTION OF RATED THERMAL POWER Page 20 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGION OF UNACCEPTABLE OPERATION Oi u

g 10.0 P

sN 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 24 l FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)

CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL

,;06, 2.38) (0.1,2.38)

(-6.1,2.28)

Z 2.2 S ACCEPTABLE OPERATION I POWER AT OR ABOVE 90%

AT LEAST I CEAC OPERABLE IN j

; ; n EACH OPERABLE CPC CHANNELI (0.05, 2.00)

(-0.1,1.93) : UNACCEPTABLE OPERATION CORE AVERAGE ASl Page 23 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 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)

ACCEl^TABLE OPERA TION ANY P PWERI.EVEL 3.5 BOTH CEACs ]INOPER ABLE IN ANlf OPER^^BLE Cl>>C CHANlSel 3.4 (0,0, .3.41) (U.l, J.4IJ Pi a

Z Q

s I 3-3 Z

§ o (-0.11,3.27)

(X o

3.2 UNACCEPTAIIle OPERi\TION 3.1 3.0 ............. i

-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 24 l 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 K^ff > 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 24 l 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 > > 0.97 Number of Operating Charging Pumps OPERATIONAL MODE 2 3 0 I 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I hour 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 24 l 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 > K^ff > 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 I hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l 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 3 0 1 2 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 24 l 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 K^ff < 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 I 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 I hour 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

ML18102B685

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