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

Oaps Technical Specification 5.6.5.d 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:

Dear Sirs:

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 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 S. P. Lingam C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS 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 Date 1

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

)1 DN: cn=Geiszler, Kelly KpIIv

/\\j(Z07064) 1 vC *

y K Reason: 1 have reviewed this

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J{Z0706J^)

Responsible Section Leader Date

^9 r 1 S 0 n ^

li plgl,3lly Oiatles 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

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1 Page 1 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

Table of Contents Description Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 1

2 3

4 5

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 3.2.1 Linear Eleat Rate (LHR) 3.2.3 Azimuthal Power Tilt (Tq) 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 3.2.5 Axial Shape Index (ASl) 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 11 11 11 11 11 12 12 12 12 13 13 13 Page 2 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Eimits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Eimits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

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

Operable)

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

Page 14 16 17 18 20 21 22 23 Page 3 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

List of Tables Description 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 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 25 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 Ref#^

Title Report No.

Rev Date Suppl CE Method for Control Element Assem-CENPD-N.A.

January N.A.

1 bly Ejection Analysis (NOOl-1301-01204) 0190-A 1976 The ROCS and DIT Computer Codes for CENPD-N.A.

April 1983 N.A.

2 Nuclear Design (NOOl-1900-01412) 266-P-A Safety Evaluation Report related to the NUREG-N.A.

March 1983 1

Final Design of the Standard Nuclear 0852 September 1983 0

Steam Supply Reference Systems J

CESSAR System 80, Docket No. STN L

50-470 December 1987 3

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

4 Uncertainties (NOOl-1303-01747) 356(V)-P-A System 80' Inlet Flow Distribution Enclosure N.A.

February 1-P 4

(NOOl-1301-01228) 1-P toLD-82-054 1993 Calculative Methods for the CE Large CENPD-N.A.

March 4-P-A 5

Break LOCA Evaluation Model (NOOl-1900-01192) 132 2001 Rev. 1 Calculative Methods for the CE Small CENPD-N.A.

April 2-P-A 6

Break LOCA Evaluation Model (NOOl-1900-01185) 137-P 1998 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 Ref#"

Title Report No.

Rev Date Suppl 8

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

N.A.

September 27,1977 N.A.

9 Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026)

CEN-372-P-A N.A.

May 1990 N.A.

10 Letter: A. C. Thadani (NRC) to A. E.

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

N.A.

April 10, 1990 N.A.

11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)

NFM-005 1

August 2007 N.A.

12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)

CE-NPD 282-P-A Vols. 1 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)

CE-NPD 282-P-A Vols. 2 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)

CE-NPD 282-P-A Vols. 3 2

March 2005 N.A.

13 Implementation ofZIRLO^^ Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A 0

November 2001 N.A.

13 Optimized ZIRLO^^^

(NOOl-0203-00611)

CENPD-404-P-A Addendum 1-A 0

July 2006 N.A.

13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOTM (NOO 1-0205-00006)

CENPD-404-P-A Addendum 2-A 0

October 2013 N.A.

Page 7 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

T.S Title Report No.

Rev Date Suppl 14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)

CENPD-188-A N.A.

July 1976 N.A.

15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (NOOl-1301-01202)

CENPD-161-P-A N.A.

April 1986 N.A.

16 CETOP-D Code Structures and Model ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOOl-1301-01185)

CEN-160(S)-P 1-P September 1981 N.A.

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

N.A.

September 29,2003 November 16,2005 N.A.

18 CPC Methodology Changes for the CPC Improvement Program (NOOl-1303-02283)

CEN-310-P-A 0

April 1986 N.A.

19 Loss of Flow, C-E Methods for Loss of Flow Analysis (NOOl-1301-01203)

CENPD-183-A 0

June 1984 N.A.

20 Methodology for Core Designs Contain ing Erbium Burnable Absorbers (NOO1-0201-00035)

CENPD-382-P-A 0

August 1993 N.A.

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

CEN-386-P-A August 1992 N.A.

CE 16x16 Next Generation Fuel Core Reference Report (NOO 1-0203-00614)

WCAP-16500-P-A August 2007 N.A.

Application of CE Setpoint Methodol ogy for CE 16x16 Next Generation Fuel (NGF)

(NOOl-0205-00063)

WCAP-16500-P-A December 2010 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Eoss of Coolant Accident Analysis (NOOl-0205-00048)

WCAP-16500-P-A June 2016 2-P-A 23 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-EOCA Thermal-Hydraulic Safety Analysis (NOO1-0205-00002)

WCAP-14565-P-A October 1999 N.A.

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VlPRE-01 Code (NOOl-0205-00003)

WCAP-14565-P-A, Addendum 1-A August 2004 N.A.

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

WCAP-14565-P-A, Addendum 2-P-A April 2008 N.A.

ABB Critical Heat Flux Correlations for PWR Fuel (NOO1-0205-00042)

CENPD-387-P-A May 2000 N.A.

Page 9 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

T.S Ref#^

Title Report No.

Rev Date Suppl 25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOOl-0203-00615)

WCAP-16523-P-A 0

August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)

WCAP-16072-P-A 0

August 2004 N.A.

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

<3 gO 02 Z

o Q

H Z

00 (500, 6.5)

RE AC GION OF CEPTABLl5 OPERATION (350, 4.0)

REGION 0 UNACCEP F

tABLE OPERATIC i...............

i..........

100 200 300 400 COLD LEG TEMPERATURE (°E) 500 600 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 (I00%,0)

V * * *

(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) 0.9 0.8 M

oa.

<S ocuXH G

[S PS H.O zo

<a:u.

0.6 0.4 0.3 0.1 0.0 NOTE:

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

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

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 power >0% and <20%.

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

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

T1L4 = (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 or by the equation:

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

GROUP 5 I-1-

1 150* 120 90 60 I

-I I-GROUP 3 I-1-

1-1 I-GROUP1

-I-1-

1-1 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 TIE requirements.

Page 18 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 l

0.9 0.8 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.

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

M I

QC U

<e:

tL.

o 2;

o u<

0.6 0.4 0.3 0.0 ill.,

iiii

!§isi 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 power > 0% and < 20%.

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

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%).

AND CEA Group 5 must be withdrawn > the 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%).

GROUP 5 I----1---- 1----i-150* 120 90 60 I

-I-GROUP 3 I--- 1----1----1--- -I I--- i-GROUP1

-I--- 1----i----1 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0

GROUP4 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 1 CORE OPERATING LIMITS REPORT Revision 25 l

FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER z

Q K

c/5 WXoz zo o

Oh

<:wuX a§ aH 00 H

Qi Oh 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 TRANSIENT INSERTION LIVIIT (75.0 NCHES).

OPER UNAC AT^O^

CEPT/

.. 1. 1 1.. 1 Oij H

W c<<

a, H

ATIG?

iuCTE i.......

p o a B D B B e LIMIT

C/5 " h"

^

a G

K) a Ifx

° B

PJ g K B

U s § insaaBBB s) :

LoivfG TER A STEA DY ST/cTE INSERTIOI OPERATIOI' EPTAI5LE i....

i....

0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 FRACTION OF RATED THERMAL POWER 0.0 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 g,

t-J ci w

o 0.

<XHDS N<

15.0 10.0 5.0 0.0 20.0 REGION OF UNACCEPTABLE OPERATION REGION OE ACCEPTABLE OPERATION 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 ;

9 n

I EACH OPERABLE CPC CHANNELl (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) 3.5 a:

PQ z

Q IZI o

3.3 3.2 3.1 3.0

-0.20 ACCEPTABLE OPERATION ANY POWER LEVEL l BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL

(-0.1;,3.27) i i UNACCEPTABLE OPERATION

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 OPERATIONAL MODE Number of Operating Charging Pumps 0

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 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 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 hour 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 hour 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 hour 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 OPERATIONAL MODE Number of Operating Charging Pumps 0

1 1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours 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 OPERATIONAL MODE Number of Operating Charging Pumps 0

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours 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 hours 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^)

Independent Reviewer Date 1

(P Digitally signed by Geiszler, beiSZler, l KeHyJ(Z07064)

} 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 Date Digitally signed by Karlson, Charle:

1 I\\F(V55086) 1 h ^ ^ 1 O C

//

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 Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 1

2 3

4 5

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 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 2

2 2

12 13 13 13 Page 2 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

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

Operable)

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

Page 14 16 17 18 20

.21 22 23 Page 3 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 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 Kefl^ 0.98 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 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 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 25 27 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 Ref#^

Title Report No.

Rev Date Suppl 1

CE Method for Control Element Assem bly Ejection Analysis (NOOl-1301-01204)

CENPD-0190-A N.A.

January 1976 N.A.

2 The ROCS and DIT Computer Codes for Nuclear Design (NOOl-1900-01412)

CENPD-266-P-A N.A.

April 1983 N.A.

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

March 1983 September 1983 December 1987 1

2 3/

4 Modified Statistical Combination of Uncertainties (NOOl-1303-01747)

CEN-356(V)-P-A 01-P-A May 1988 N.A.

4 System 80' Inlet Flow Distribution (NOOl-1301-01228)

Enclosure 1-P to LD-82-054 N.A.

February 1993 1-P 5

Calculative Methods for the CE Large Break LOCA Evaluation Model (NOOl-1900-01192)

CENPD-132 N.A.

March 2001 4-P-A Rev. 1 6

Calculative Methods for the CE Small Break LOCA Evaluation Model (NOOl-1900-01185)

CENPD-137-P N.A.

April 1998 2-P-A 7

Letter: O.D. Parr (NRC) to F. M. Stem (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

N.A.

June 13, 1975 N.A.

Page 6 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

T.S Ref#"*

Title Report No.

Rev Date Suppl 8

Letter; K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P).NRC approval for 5.6.5.b.6.

N.A.

September 27, 1977 N.A.

9 Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026)

CEN-372-P-A N.A.

May 1990 N.A.

10 Letter; A. C. Thadani (NRC) to A. E.

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

N.A.

April 10, 1990 N.A.

11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)

NFM-005 1

August 2007 N.A.

12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)

CE-NPD 282-P-A Vols. 1 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)

CE-NPD 282-P-A Vols. 2 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)

CE-NPD 282-P-A Vols. 3 2

March 2005 N.A.

13 Implementation of ZIRLO^^ Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A 0

November 2001 N.A.

13 Optimized ZIRLO' (NOO1-0203-00611)

CENPD-404-P-A Addendum 1-A 0

July 2006 N.A.

13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO' (NOOl-0205-00006)

CENPD-404-P-A Addendum 2-A 0

October 2013 N.A.

Page 7 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

T.S Ref#""

Title Renort No.

Rev Date Suppl 14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAE)

CENPD-188-A N.A.

July 1976 N.A.

15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (NOOl-1301-01202)

CENPD-161-P-A N.A.

April 1986 N.A.

, 16 CETOP-D Code Structures and Model ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOOl-1301-01185)

CEN-160(S)-P 1-P September 1981 N.A.

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

N.A.

September 29,2003 November 16, 2005 N.A.

18 CPC Methodology Changes for the CPC Improvement Program (NOOl-1303-02283)

CEN-310-P-A 0

April 1986 N.A.

19 Loss of Flow, C-E Methods for Loss of Flow Analysis (NOOl-1301-01203)

CENPD-183-A 0

June 1984 N.A.

20 Methodology for Core Designs Contain ing Erbium Burnable Absorbers (NOOl-0201-00035)

CENPD-382-P-A 0

August 1993 N.A.

Page 8 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

T.S Ref#^

Title Report No.

Rev Date Suppl Verification of the Acceptability of a 1-Pin Bumup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel (NOO1-0201-00042)

CEN-386-P-A August 1992 N.A.

CE 16x16 Next Generation Fuel Core Reference Report (NOOl-0203-00614)

WCAP-16500-P-A August 2007 N.A.

Application of CE Setpoint Methodol ogy for CE 16x16 Next Generation Fuel (NGF)

(NOO 1-0205-00063)

WCAP-16500-P-A December 2010 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOO 1-0205-00048)

WCAP-16500-P-A June 2016 2-P-A VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (NOOl-0205-00002)

WCAP-14565-P-A October 1999 N.A.

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (NOO1-0205-00003)

WCAP-14565-P-A, Addendum 1-A August 2004 N.A.

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

WCAP-14565-P-A, Addendum 2-P-A April 2008 N.A.

ABB Critical Heat Flux Correlations for PWR Fuel (NOOl-0205-00042)

CENPD-387-P-A May 2000 N.A.

Page 9 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 21 l

T.S Ref#"*

Title Report No.

Rev Date Suppl 25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOO1-0203-00615)

WCAP-16523-P-A 0

August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)

WCAP-16072-P-A 0

August 2004 N.A.

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

<1 g,

g0 oi.

N

~~....................... 1 1..............~~

~~i.....................1 1........................ i..................~~

~~100 200 300 400 COLD LEG TEMPERATURE (°F) 500 600 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 (10p%,-4.4 (0%,-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) 02U oa.J
~~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 power >0% and <20%.~~
~~AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.~~
~~CEA Group 4 must be withdrawn > the group 4 TIL (TIL4) as indicated on the graph or by the equation:~~
~~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 or by the equation:~~
~~TIL5 = (172.5" X Fractional Power) - 64.5" (for power > 37.39% and < 100%).~~
~~GROUP 5 I-1-~~
~~^^1-1 150* 120 90 60~~
~~-I-1 GROUP 3~~
~~-I-1-~~
1
-I
~~-I-GROUP1~~
~~-I-1-~~
~~1-1 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
0.9 0.8 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.
To meet tbe Transient Insertion Limit (TIL) all conditions below must be met:
2
<s OLUK H
Q UH
<a:
u.ozo o<
Oi.
u.
0.6 0.1 0.0 fill 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 power >0% and <20%.
AND CEA Group 4 must be > fully withdrawn* for power levels > 54.97%.
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%).
AND CEA Group 5 must be withdrawn > the 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%).
GROUP 5 I-1-
1-1 150* 120 90 60
-I I-GROUP 3 I-1-
1-I-
GROUP1
-I-1 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 z
OS Q
KH c/5 U
Xuz zo c/5 o
0.
<uo XH0 z
w oc H
c/5 H
01 a.
0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 TRANSIENTINSER'hON LIVIIT (75.0 NCHES).
OPER UNAC AT^O^
CEPT/
[t w
1
..................J.
OPER REST]
ATIO?
iilCTE 1............
ABLE iw D
s Mstea
^ a a BB B B ERTIO^
n D B a o a B LIMIT o a a a B B 1 S (112.5 1 B BBBaa INCHE aaaaaaB s) :
i LorvlG TER]
DY ST/cTE INS OPERATIOr'} ACClEPTAIlLE
.... 1i.... 1i....
0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 FRACTION OF RATED THERMAL POWER 0.0 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 H
02U O
(X 5
sN 10.0 5.0 0.0 20.0 REGION OF UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPERATION 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)
UNACCEPTABLE
(-0.1,1.93) ;
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) os 2;
Q si 3.3 ZI uau 3.2 3.1 3.0
-0.20 ACCEPTABLE ANY POWER 1 BOTH CEACs ]
OPERA
,EVEL NOPER-TION ABLE IN AN' CHAN]
Y OPER^
NEL 03rwn O
Ann 'XAw
(-0.1i, 3.27)
UNAC OPERi H
S 1
fLE
........... i i...........
i............ i........... i...........
-0.15
-0.10
-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 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 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 hour 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 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 hour 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 hour 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours 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 hours 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 Date
^
1 Digitally signed by Geiszler, LlGISZlGT, 1 Kelly J(Z07064)
)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, Responsible Section Leader Date X
ff Oigitaliy signed by Karlson Kar son, WchanesFlVSSOSe) 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 Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 1
2 3
4 5
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 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 (ASl) 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 1
1 12 12 12 12 13 13 13 Page 2 of29
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l
List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)
CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)
Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)
COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)
Operable)
DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 14 16 17 18 20 21 22 23 Page 3 of 29
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l
List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 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> 0.98 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 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 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 25 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 Ref#""
Title Report No.
Rev Date Suppl CE Method for Control Element Assem-CENPD-N.A.
January N.A.
1 bly Ejection Analysis (NOOl-1301-01204) 0190-A 1976 The ROCS and DIT Computer Codes for CENPD-N.A.
April 1983 N.A.
2 Nuclear Design (NOO1-1900-01412) 266-P-A Safety Evaluation Report related to the NUREG-N.A.
March 1983 1
Final Design of the Standard Nuclear 0852 September 1983
'X Steam Supply Reference Systems CESSAR System 80, Docket No. STN Z
50-470 December 1987 3
Modified Statistical Combination of CEN-01-P-A May 1988 N.A.
4 Uncertainties (NOOl-1303-01747) 356(V)-P-A System 80' Inlet Flow Distribution Enclosure N.A.
February 1-P 4
(NOOl-1301-01228) 1-P to LD-82-054 1993 Calculative Methods for the CE Large CENPD-N.A.
March 4-P-A 5
Break LOCA Evaluation Model (NOOl-1900-01192) 132 2001 Rev. 1 Calculative Methods for the CE Small CENPD-N.A.
April 2-P-A 6
Break LOCA Evaluation Model (NOOl-1900-01185) 137-P 1998 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 Ref#""
Title Report No.
Rev Date Suppl 8
Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
N.A.
N.A.
September 27,1977 N.A.
9 Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026)
CEN-372-P-A N.A.
May 1990 N.A.
10 Letter: A. C. Thadani (NRC) to A. E.
Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
N.A.
N.A.
April 10, 1990 N.A.
11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
NFM-005 1
August 2007 N.A.
12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)
CE-NPD 282-P-A Vols. 1 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
CE-NPD 282-P-A Vols. 2 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)
CE-NPD 282-P-A Vols. 3 2
March 2005 N.A.
13 Implementation of ZIRLO' Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)
CENPD-404-P-A 0
November 2001 N.A.
13 Optimized ZIRLO' (NOOl-0203-00611)
CENPD-404-P-A Addendum 1-A 0
July 2006 N.A.
13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO' (NOO 1-0205-00006)
CENPD-404-P-A Addendum 2-A 0
October 2013 N.A.
Page 7 of 29
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l
T.S Ref#""
Title Report No.
Rev Date Suppl 14 HERMITE, A Multi-Dimensional Spaee-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)
CENPD-188-A N.A.
July 1976 N.A.
15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (NOOl-1301-01202)
CENPD-161-P-A N.A.
April 1986 N.A.
16 CETOP-D Code Structures and Model ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOOl-1301-01185)
CEN-160(S)-P 1-P September 1981 N.A.
17 Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29,2003) and Safety Evaluation related to Palo Verde 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).
N.A.
N.A.
September 29,2003 November 16, 2005 N.A.
18 CPC Methodology Changes for the CPC Improvement Program (NOOl-1303-02283)
CEN-310-P-A 0
April 1986 N.A.
19 Loss of Flow, C-E Methods for Loss of Flow Analysis (NOOl-1301-01203)
CENPD-183-A 0
June 1984 N.A.
20 Methodology for Core Designs Contain ing Erbium Burnable Absorbers (NOOl-0201-00035)
CENPD-382-P-A 0
August 1993 N.A.
Page 8 of 29
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l
T.S Ref#^
Title Report No.
Rev Date SuddI 21 Verification of the Acceptability of a 1-Pin Bumup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel (NOO1-0201-00042)
CEN-386-P-A 0
August 1992 N.A.
22 CE 16x16 Next Generation Fuel Core Reference Report (NOOl-0203-00614)
WCAP-16500-P-A 0
August 2007 N.A.
22 Application of CE Setpoint Methodol ogy for CE 16x16 Next Generation Fuel (NGF)
(NOO1-0205-00063)
WCAP-16500-P-A 1
December 2010 1
22 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOOl-0205-00048)
WCAP-16500-P-A 1
June 2016 2-P-A 23 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (NOO 1-0205-00002)
WCAP-14565-P-A 0
October 1999 N.A.
23 Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VlPRE-01 Code (NOOl-0205-00003)
WCAP-14565-P-A, Addendum 1-A 0
August 2004 N.A.
23 Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Cor relation and Modified ABB-NV Correla tion WLOP for PWR Low Pressure Applications (NOO1-0205-00004)
WCAP-14565-P-A, Addendum 2-P-A 0
April 2008 N.A.
24 ABB Critical Heat Flux Correlations for PWR Fuel (NOO1-0205-00042)
CENPD-387-P-A 0
May 2000 N.A.
Page 9 of 29
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 24 l
T.S Ref#
Title Report No.
Rev Date Suppl 25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOO1-0203-00615)
WCAP-16523-P-A 0
August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)
WCAP-16072-P-A t
0 August 2004 N.A.
~~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 1
~~0 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 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
<j g0 01 z
o Q
HPX (Zl (500, 5.0il RE AC OP GION OF CEPTABLI ERATION (REGION OF UNACCEPTABLE OPERATION i................ j.....................
(350, I.O) t..................... i................ 1..................
100 200 300 400 COLD LEG TEMPERATURE (°F) 500 600 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
<1 z
I 0
oc z
1 Q
z C/3 (500, 6.5)
RE AC GION OF CEPTABL]5 OPERATION (350, 4.0)
REGION 0 UNACCEP^
F FABLE OPERATIC>N
............................1 100 200 300 400 COLD LEG TEMPERATURE (°F) 500 600 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) 0.9 0.8 2
XH Q
wH<a U.
o
§ 0.6
£ 0.3 0.1 0.0 NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
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 power >0% and <20%.
AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.
CEA Group 4 must be withdrawn > the group 4 TIL (TIL4) as indicated on the graph or by the equation:
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 or by the equation:
TIL5 = (172.5" X Fractional Power) - 64.5" (for power > 37.39% and < 100%).
GROUP 5
-I--- 1--- -I----1 I-GROUP 3 I----1--- I-GROUP1 l------1----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----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) o 0.
-J u
P w
<a:
tt.
o
§ 0.9 0.8 0.6 0.0 NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met; 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 power >0% and <20%.
AND CEA Group 4 must be > fully withdrawn* for power levels > 54.97%.
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%).
AND CEA Group 5 must be withdrawn > the 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%).
GROUP 5 I-1-
1 150* 120 90 60 I
-I GROUP 3 I 1 1-
-I GROUP 1
-I 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0
GROUP4 GROUP 2 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 z
<a:PXH c/5 WXuzc-zop 00 o
<woXHO zp o:H c/5 H
(52 0.
0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 TRANSIEN[T INSERTION LIVilT (75.0 NCHES).
........ GPER UNAC ATIO?
CEPT.
li......
iVBLE 11
....... 1 sX GPER REST]
ATIG?
jaCTE i........
D Io
' LorsIG TER]M STEA DYST/^TE INSERTIO^ LIMITS (112.5 INCHE,s) :
OPERATIO^}ACC]EPTAE5LE
.... 1 i................ i....
1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 FRACTION OF RATED THERMAL POWER 0.0 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 Oi u
g 10.0 P
sN 0.0 20.0 REGION OF UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPERATION 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)
UNACCEPTABLE
(-0.1,1.93) :
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) 3.5 3.4 Pi aZ Q
sI 3-3 Z§ o
(X o
3.2 3.1 3.0
-0.20 ACCEl ANY P BOTH
^TABLE PWERI CEACs ]
OPERA
.EVEL INOPER TION ABLE IN ANl CHANl f OPER^
Sel
^BLE Cl>>C (0,0,.3.41)
(U.l, J.4IJ
(-0.11,3.27)
UNAC OPERi CEPTAI
\\TION Ile
............. i
-0.15
-0.10
-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
I 2
3 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 OPERATIONAL MODE Number of Operating Charging Pumps 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 hour 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 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 hour 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
I 2
3 3
12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours I hour 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours' 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

Text

Subject:

Dear Sirs:

Enclosures:

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