Text

Unit 1 Core Operating Limits Report Revision 27, Unit 2 Core Operating Limits Report Revision 22, Unit 3 Core Operating Limits Report Revision 25
	ML19204A193
Person / Time
Site:	Palo Verde
Issue date:	07/22/2019
From:	Dilorenzo M; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-07955-MDD/TMJ
	Download: ML19204A193 (91)
	v • d • e

Technical Specification 5.6.Sd Palo Verde Nuclear Generating Station 5871 S. Wlntersburg Road Tonopah, AZ 85354 102-07955-MDD/TMJ July 22, 2019 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 Revision 27 Unit 2 Core Operating Limits Report Revision 22 Unit 3 Core Operating Limits Report Revision 25

Dear Sirs:

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

Revisions 27, 22, and 25, respectively, which were made effective July 1, 2019 .

The changes Implemented by these revisions are to the Table In the Analytical Methods section of each unit's COLR. Previously, documents referenced In that Table did not list all the reference Information required by the NOTE contained In Technical Specification 5.6.5b (Reporting Requirements - Analytical Methods). No technical changes are necessary.

These changes affect several pages In the respective COLRs. Revision bars have been applied to those pages which contain changes.

No commitments are being made to the Nuclear Regulatory Commission (NRC) by this letter. If you have any questions about this submittal please contact Michael D.

Dilorenzo, Nuclear Regulatory Affairs, Department Leader, at (623) 393-3495.

Sincerely,

~~ *~

0 1 G 11t-1.... fc:Jr-Michae1 D. Dilorenzo Nuclear Regulatory Affairs Department Leader MDD/TMJ/mg

Enclosures:

Unit 1 Core Operating Limits Report, Revision 27 Unit 2 Core Operating Limits Report, Revision 22 Unit 3 Core Operating Limits Report, Revision 25 cc:

S. A. Morris NRC Region IV Regional Administrator S. P. Llngam NRC NRR Project Manager for PVNGS M.M. O'Bannion NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure Unit 1 Core Operating Limits Report Revision 27

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PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 Page 2 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)

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

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

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

Operable)

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

Page 3 of 29

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 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 1 CORE OPERATING LIMITS REPORT Revision 27 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#a CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (N001-1301-01204)

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

2 Nuclear Design 266-P-A (N001-1900-01412)

Safety Evaluation Report related to the NUREG- N.A. November N.A.

Final Design of the Standard Nuclear 0852 1981 Steam Supply Reference Systems March 1983 1 CESSAR System 80, Docket No. STN 3 50-470 September 2 1983 December 3 1987 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (N001-1303-01747)

System 80TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (N001-1301-01228) 1-P to LD- 1993 82-054 Calculative Methods for the C-E Large CENPD- N.A. August 1974 N.A.

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

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

Break LOCA Evaluation Model 132-P Calculative Methods for the C-E Large CENPD- N.A. June 1985 3-P-A 5 Break LOCA Evaluation Model for the 132 Analysis of C-E and W Designed NSSS Page 6 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 T.S Title Report No. Rev Date Suppl Ref#a Calculative Methods for the CE Nuclear CENPD- N.A. March 2001 4-P-A Power Large Break LOCA Evaluation 132 Rev. 1 5

Model (N001-1900-01192)

Calculative Methods for the CE Nuclear CENPD- N.A. August 2007 4-P-A Power Large Break LOCA Evaluation 132 Adde-5 Model ndum (N001-0205-00046) 1-P-A Revision 4 to the Supplement to Appen- CENPD- N.A. December SUPP dix A of CENPD-132 Supplement 4-P-A 132 2008 4-P-A (N001-0205-00229) APP 5

A-REV 004 Calculative Methods for the C-E Small CENPD- N.A. August 1974 N.A.

6 Break LOCA Evaluation ModeL 137-P Calculative Methods for the C-E Small CENPD- N.A. January 1-P 6 Break LOCA Evaluation Model 137 1977 Calculative Methods for the ABB C-E CENPD- N.A. April 1998 2-P-A 6 Small Break LOCA Evaluation Model 137 (N001-1900-01185)

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.

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 1990 N.A.

9 (N001-0201-00026) P-A Page 7 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 T.S Title Report No. Rev Date Suppl Ref#a 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 2007 N.A.

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

Technical Description Manual for the CE-NPD 2 March 2005 N.A.

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

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

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

Material in CE Nuclear Power Fuel 404-P-A 2001 13 Assembly Designs (N001-1900-01329)

Optimized ZIRLOTM CENPD- 0 July 2006 N.A.

(N001-0203-00611) 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 (N001-0205-00006) Addendum 2-A HERMITE, A Multi-Dimensional CENPD- N.A. July 1976 N.A.

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

TORC Code, A Computer Code for CENPD- N.A. April 1986 N.A.

Determining the Thermal Margin of a 161-P-A 15 Reactor Core (N001-1301-01202)

Page 8 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 T.S Title Report No. Rev Date Suppl Ref#a 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 (N001-1301-01185)

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) 17 and November 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 1986 N.A.

18 Improvement Program P-A (N001-1303-02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June 1984 N.A.

19 Flow Analysis 183-A (N001-1301-01203)

Methodology for Core Designs Contain- CENPD- 0 August 1993 N.A.

20 ing Erbium Burnable Absorbers 382-P-A (N001-0201-00035)

Verification of the Acceptability of a 1- CEN-386- 0 August 1992 N.A.

Pin Burnup Limit of 60 MWD/kgU for P-A 21 Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)

CE 16x16 Next Generation Fuel Core WCAP- 0 August 2007 N.A.

22 Reference Report 16500-P-A (N001-0203-00614)

Page 9 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 T.S Title Report No. Rev Date Suppl Ref#a Application of CE Setpoint Methodol- WCAP- 0 December 1 ogy for CE 16x16 Next Generation Fuel 16500-P-A 2010 Rev. 1 22 (NGF)

(N001-0205-00063)

Evolutionary Design Changes to CE WCAP- 0 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 (N001-0205-00048)

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 (N001-0205-00002)

Addendum 1 to WCAP-14565-P-A WCAP- 0 August 2004 N.A.

Qualification of ABB Critical Heat Flux 14565-P-A, 23 Correlations with VIPRE-01 Code Addendum (N001-0205-00003) 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 (N001-0205-00004)

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

24 PWR Fuel 387-P-A (N001-0205-00042)

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

Implementation of Zirconium Diboride WCAP- 0 August 2004 N.A.

Burnable Absorber Coatings in CE 16072-P-A 26 Nuclear Power Fuel Assembly Designs (N001-0205-00226)

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

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

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

3.1.4 - Moderator Temperature Coefficient (MTC)

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

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

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

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

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

Page 11 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

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

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

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

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

3.2.1 - Linear Heat Rate (LHR)

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

3.2.3 - Azimuthal Power Tilt (Tq)

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

3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)

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

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

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

Page 12 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 3.2.5 - Axial Shape Index (ASI)

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

COLSS OPERABLE

-0.18 AS 0.17 for power > 50%

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

COLSS OUT OF SERVICE (CPC)

-0.10 ASI 0.10 for power >20%

3.3.12 - Boron Dilution Alarm System (BDAS)

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

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

Page 13 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7

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

OPERATION 4

3 REGION OF UNACCEPTABLE 2

OPERATION 1

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

Page 14 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7

(500, 6.5) 6 REGION OF ACCEPTABLE 5

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

OPERATION 1

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

Page 15 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 (0%,0.5)

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

-0.5 (100%,-0.2)

MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)

-1.0

-1.5 MTC AREA OF ACCEPTABLE

-2.0 OPERATION

-2.5

-3.0

-3.5

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

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

(% OF RATED THERMAL POWER)

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

20 20 16 100% to

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

>70% RTP 10 10

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

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

3 2 2 1

0 0

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

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

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

- > 95 % RATED THERMAL POWER

- COLSS IN SERVICE AND CEACS IN SERVICE

- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE:

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

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

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

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

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

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

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

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

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

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

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

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

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

Page 18 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Page 19 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN) 40.0 50.0 60.0 70.0 TRANSIENT INSERTION LIMIT (75.0 INCHES) 80.0 (50% RATED THERMAL POWER) 90.0 OPERATION OPERATION UNACCEPTABLE RESTRICTED 100.0 110.0 LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES) 120.0 130.0 OPERATION ACCEPTABLE 140.0 150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 20 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGION OF UNACCEPTABLE OPERATION AZIMUTHAL POWER TILT (%)

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

(% OF RATED THERMAL POWER)

Page 21 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95, 20) 20 COLSS DNBR POWER OPERATION LIMIT REDUCTION 15

(% OF RATED THERMAL POWER) 10 5

(80, 5)

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

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0.06, 2.38) (0.1, 2.38) 2.3

(-0.1, 2.28)

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

AT LEAST 1 CEAC OPERABLE IN 2.1 EACH OPERABLE CPC CHANNEL (0.08, 2.07) (0.1, 2.07) 2.0 (-0.1, 1.99)

UNACCEPTABLE 1.9 OPERATION 1.8

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL) 3.6 ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 IN ANY OPERABLE CPC CHANNEL (0.0, 3.41) (0.1, 3.41) 3.4 CPC MINIMUM DNBR 3.3

(-0.1, 3.27) 3.2 UNACCEPTABLE OPERATION 3.1 3.0

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

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Keff > 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 28 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 27 Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 Number of Operating Charging Pumps OPERATIONAL MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ONA 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 29 of 29

Enclosure Unit 2 Core Operating Limits Report Revision 22

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 Page 2 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)

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

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

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

Operable)

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

Page 3 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 28 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 29 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 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 2 CORE OPERATING LIMITS REPORT Revision 22 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#a CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (N001-1301-01204)

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

2 Nuclear Design 266-P-A (N001-1900-01412)

Safety Evaluation Report related to the NUREG- N.A. November N.A.

Final Design of the Standard Nuclear 0852 1981 Steam Supply Reference Systems March 1983 1 CESSAR System 80, Docket No. STN 3 50-470 September 2 1983 December 3 1987 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (N001-1303-01747)

System 80TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (N001-1301-01228) 1-P to LD- 1993 82-054 Calculative Methods for the C-E Large CENPD- N.A. August 1974 N.A.

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

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

Break LOCA Evaluation Model 132-P Calculative Methods for the C-E Large CENPD- N.A. June 1985 3-P-A 5 Break LOCA Evaluation Model for the 132 Analysis of C-E and W Designed NSSS Page 6 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 T.S Title Report No. Rev Date Suppl Ref#a Calculative Methods for the CE Nuclear CENPD- N.A. March 2001 4-P-A Power Large Break LOCA Evaluation 132 Rev. 1 5

Model (N001-1900-01192)

Calculative Methods for the CE Nuclear CENPD- N.A. August 2007 4-P-A Power Large Break LOCA Evaluation 132 Adde-5 Model ndum (N001-0205-00046) 1-P-A Revision 4 to the Supplement to Appen- CENPD- N.A. December SUPP dix A of CENPD-132 Supplement 4-P-A 132 2008 4-P-A (N001-0205-00229) APP 5

A-REV 004 Calculative Methods for the C-E Small CENPD- N.A. August 1974 N.A.

6 Break LOCA Evaluation ModeL 137-P Calculative Methods for the C-E Small CENPD- N.A. January 1-P 6 Break LOCA Evaluation Model 137 1977 Calculative Methods for the ABB C-E CENPD- N.A. April 1998 2-P-A 6 Small Break LOCA Evaluation Model 137 (N001-1900-01185)

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.

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 1990 N.A.

9 (N001-0201-00026) P-A Page 7 of 29

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 22 T.S Title Report No. Rev Date Suppl Ref#a Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.