ML22305A536
| ML22305A536 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/28/2022 |
| From: | Cox M Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 102-08522-MSC/DHD | |
| Download: ML22305A536 (1) | |
Text
Technical Specification 5.6.5(d)
A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7636 Tel: (623) 393-5753 102-08522-MSC/DHD October 28, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Docket No. STN 50-530 Unit 3 Core Operating Limits Report, Revision 30 Pursuant to PVNGS Technical Specifications, Section 5.6.5(d), enclosed is the Unit 3 Core Operating Limits Report (COLR), Revision 30, which was made effective October 21, 2022. The changes implemented by the revision are to Section 3.2.1, Linear Heat Rate (LHR) and Figure 3.2.4-2, DNBR Margin Operating Limit Based on the Core Protection Calculators.
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew S. Cox, Licensing Department Leader, at (623) 393-5753.
Sincerely, Matthew S. Cox Department Leader, Regulatory Affairs MSC/DHD/cr
Enclosure:
Unit 3 Core Operating Limits Report, Revision 30 cc:
S. A. Morris NRC Region IV Regional Administrator D. Galvin NRC NRR Project Manager for PVNGS L. N. Merker NRC Senior Resident Inspector for PVNGS Cox, Matthew S(Z05628)
Digitally signed by Cox, Matthew S(Z05628)
Date: 2022.10.28 16:01:48 -07'00'
Enclosure Unit 3 Core Operating Limits Report Revision 30
Page 1 of 29 PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 3 CORE OPERATING LIMITS REPORT Revision 30 Effective: October 21, 2022 Responsible Engineer Date Design Verifier Date Responsible Section Leader Date
- Cowdin, Christophe r (Z12133)
Digitally signed by Cowdin, Christopher (Z12133)
Date: 2022.10.19 08:09:24 -07'00' Gill, Shawn P(Z37857)
Digitally signed by Gill, Shawn P(Z37857)
Date: 2022.10.19 08:21:59 -07'00'
- McIntyre, Luke (Z11200)
Digitally signed by McIntyre, Luke (Z11200)
Date: 2022.10.19 11:24:25 -07'00'
Revision 30 Page 2 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1
Table of Contents 2
List of Figures 3
List of Tables 4
Affected Technical Specifications 5
Analytical Methods 6
Core Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 4.2.1 Fuel Assemblies 13
Revision 30 Page 3 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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)
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)
Revision 30 Page 4 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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
Revision 30 Page 5 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements of Technical Specifications 4.2.1 and 5.6.5. The Core Operating Limits have been developed using the NRC approved meth-odologies specified in Section 5.6.5 b of the Palo Verde Technical Specifications.
AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC) 3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR) 3.2.3 Azimuthal Power Tilt (Tq) 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 3.2.5 Axial Shape Index (ASI) 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 4.2.1 Fuel Assemblies
Revision 30 Page 6 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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#a Report No.
Revision /
Supplement Date Title Fuel Applicability 1
CENPD-0190-A N.A. / N.A.
January 1976 CE Method for Control Element Assem-bly Ejection Analysis (N001-1301-01204)
CENPD-266-P-A N.A. / N.A.
April 1983 The ROCS and DIT Computer Codes for Nuclear Design (N001-1900-01412)
NUREG-0852 N.A. / N.A.
November 1981 Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470 Westinghouse Framatome 3
N.A. / 1 March 1983 Westinghouse Framatome 3
N.A. / 2 September 1983 Westinghouse Framatome 3
N.A. / 3 December 1987 Westinghouse Framatome 4
CEN-356(V)-
P-A 01-P-A / N.A.
May 1988 Modified Statistical Combination of Uncertainties (N001-1303-01747)
Westinghouse Framatome 4 -P to LD-82-054 N.A. / 1-P February 1993 System 80TM Inlet Flow Distribution (N001-1301-01228)
CENPD-132 P N.A. / N.A.
August 1974 Calculative Methods for the C-E Large Break LOCA Evaluation Model Westinghouse 5
CENPD-132P N.A./ 1 February 1975 Calculational Methods for the C-E Large Break LOCA Evaluation Model Westinghouse 5
CENPD-132-P N.A. / 2-P July 1975 Calculational Methods for the C-E Large Break LOCA Evaluation Model Westinghouse 5
CENPD-132 N.A. / 3-P-A June 1985 Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS Westinghouse 5
CENPD-132 N.A. / 4-P-A Rev. 1 March 2001 Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-1900-01192)
Revision 30 Page 7 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 5
CENPD-132-P-A N.A. / 4-P-A Addendum 1-P-A August 2007 Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-0205-00046)
CENPD-132 N.A. /
SUPP 4-P-A APP A-Rev. 004 December 2008 Revision 4 to the Supplement to Appen-dix A of CENPD-132 Supplement 4-P-A (N001-0205-00229)
CENPD-137-P N.A. / N.A.
August 1974 Calculative Methods for the C-E Small Break LOCA Evaluation Model Westinghouse 6
CENPD-137 N.A. / 1-P January 1977 Calculative Methods for the C-E Small Break LOCA Evaluation Model Westinghouse 6
CENPD-137 N.A. / 2-P-A April 1998 Calculative Methods for the ABB C-E Small Break LOCA Evaluation Model (N001-1900-01185)
N.A.
N.A. / N.A.
June 13, 1975 Letter: O.D. Parr (NRC) to F. M. Stern (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
N.A.
N.A. / N.A.
September 27, 1977 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.
CEN-372-P-A N.A. / N.A.
May 1990 Fuel Rod Maximum Allowable Pressure (N001-0201-00026)
Westinghouse 10 N.A.
N.A. / N.A.
April 10, 1990 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.
Westinghouse 11 NFM-005 1 / N.A.
August 2007 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
Westinghouse Framatome 12 CENPD-282-P-A Vols. 1 2 / N.A.
March 2005 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)
Westinghouse Framatome 12 CENPD-282-P-A Vols. 2 2 / N.A.
March 2005 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
Westinghouse Framatome T.S Ref#a Report No.
Revision /
Supplement Date Title Fuel Applicability
Revision 30 Page 8 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 12 CENPD-282-P-A Vols. 3 2 / N.A.
March 2005 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)
Westinghouse Framatome 12 CENPD-282-P-A Vols. 4 2 / N.A.
March 2005 Technical Description Manual for the CENTS Code Volume 4 (CENTS-TD MANUAL-VOL 4)
Westinghouse Framatome 13 CENPD-404-P-A 0 / N.A.
November 2001 Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (N001-1900-01329)
Westinghouse 13 CENPD-404-P-A Addendum 1-A 0 / N.A.
July 2006 Optimized ZIRLOTM (N001-0203-00611)
Westinghouse 13 CENPD-404-P-A Addendum 2-A 0 / N.A.
October 2013 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOTM (N001-0205-00006)
Westinghouse 14 CENPD-188-A N.A. / N.A.
July 1976 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)
Westinghouse Framatome 15 CENPD-161-P-A N.A. / N.A.
April 1986 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (N001-1301-01202)
Westinghouse 16 CEN-160(S)-P 1-P / N.A.
September 1981 CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (N001-1301-01185)
Westinghouse Framatome 17 N.A.
N.A. / N.A.
September 29, 2003 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)
Westinghouse Framatome T.S Ref#a Report No.
Revision /
Supplement Date Title Fuel Applicability
Revision 30 Page 9 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 17 N.A.
N.A. / N.A.
November 16, 2005 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).
Westinghouse Framatome 18 CEN-310-P-A 0 / N.A.
April 1986 CPC Methodology Changes for the CPC Improvement Program (N001-1303-02283)
Westinghouse Framatome 19 CENPD-183-A 0 / N.A.
June 1984 Loss of Flow, C-E Methods for Loss of Flow Analysis (N001-1301-01203)
Westinghouse Framatome 20 CENPD-382-P-A 0 / N.A.
August 1993 Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (N001-0201-00035)
Westinghouse 21 CEN-386-P-A 0 / N.A.
August 1992 Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)
Westinghouse 22 WCAP-16500-P-A 0 / N.A.
August 2007 CE 16x16 Next Generation Fuel Core Reference Report (N001-0203-00614)
Westinghouse 22 WCAP-16500-P-A 0 / 1 Rev 1 December 2010 Application of CE Setpoint Methodol-ogy for CE 16x16 Next Generation Fuel (NGF)
(N001-0205-00063)
Westinghouse Framatome 22 WCAP-16500-P-A 0 / 2-P-A June 2016 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 (N001-0205-00048)
Westinghouse 23 WCAP-14565-P-A 0 / N.A.
October 1999 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (N001-0205-00002)
Westinghouse Framatome 23 WCAP-14565-P-A, Addendum 1-A 0 / N.A.
August 2004 Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (N001-0205-00003)
Westinghouse T.S Ref#a Report No.
Revision /
Supplement Date Title Fuel Applicability
Revision 30 Page 10 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 23 WCAP-14565-P-A, Addendum 2-P-A 0 / N.A.
April 2008 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 (N001-0205-00004)
Westinghouse 24 CENPD-387-P-A 0 / N.A.
May 2000 ABB Critical Heat Flux Correlations for PWR Fuel (N001-0205-00042)
Westinghouse 25 WCAP-16523-P-A 0 / N.A.
August 2007 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup-ported Mixing Vanes (N001-0203-00615)
Westinghouse 26 WCAP-16072-P-A 0 / N.A.
August 2004 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (N001-0205-00226)
Westinghouse 27 EMF-2103P-A 3 / N.A.
June 2016 Realistic Large Break LOCA Methodol-ogy for Pressurized Water Reactors Framatome 28 EMF-2328(P)(A) 0 / N.A.
March 2001 PWR Small Break LOCA Evaluation Model, S-RELAP5 Based Framatome 28 EMF-2328(P)(A) 0 / 1(P)(A)
December 2016 PWR Small Break LOCA Evaluation Model, S-RELAP5 Based Framatome 29 BAW-10231P-A 1 / N.A.
January 2004 COPERNIC Fuel Rod Design Computer Code Framatome 30 BAW-10241P-A 2 / N.A.
September 2020 BHTP DNB Correlation Applied with LYNXT (N001-0206-00200)
Framatome 31 EPRI-NP-2511-CCM-A Mod 02 / N.A.
Volume 1-4 (February 2017)
VIPRE-01: A Thermal Hydraulic Analy-sis Code for Reactor Cores Westinghouse Framatome 31 Mod 02 / N.A.
Volume 5 (March 1988)
VIPRE-01: A Thermal Hydraulic Analy-sis Code for Reactor Cores Westinghouse Framatome
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 T.S Ref#a Report No.
Revision /
Supplement Date Title Fuel Applicability
Revision 30 Page 11 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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.
Revision 30 Page 12 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and
>145.25 (RSPT indication). No further CEA withdrawal above FW is required for CEAs to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit shall be maintained in accordance with core burnup:
13.1 kW/ft for burnup < 450 EFPD 12.1 kW/ft for burnup 450 EFPD 3.2.3 - Azimuthal Power Tilt (Tq)
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.
3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)
COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.
Revision 30 Page 13 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 AS 0.17 for power > 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 ASI 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 3000 ppm.
4.2.1 - Fuel Assemblies The Reactor Core contains the following fuel types:
Westinghouse CE16STD with ZIRLO' cladding Westinghouse CE16NGF with Optimized ZIRLO' cladding No lead test assemblies Refer to the ANALYTICAL METHODS Table for the methods applicable to a particular fuel type.
Revision 30 Page 14 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 1.0)
(500, 5.0)
Revision 30 Page 15 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 4.0)
(500, 6.5)
Revision 30 Page 16 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT
-4.5
-4.0
-3.5
-3.0
-2.5
-2.0
-1.5
-1.0
-0.5 0.0 0.5 0
10 20 30 40 50 60 70 80 90 100 MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 MTC AREA OF ACCEPTABLE OPERATION (0%,0.5)
(100%,0)
(50%, 0.0)
(100%,-0.2)
(0%,-4.4)
(100%,-4.4)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit
Revision 30 Page 17 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
5 10 15 20 0
10 20 30 40 50 60 MINIMUM REQUIRED POWER REDUCTION
(% OF RATED THERMAL POWER)
TIME AFTER DEVIATION, MINUTES FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20 100% to
>80% RTP 16 12 8
4 0
15 80% to
>70% RTP 12 9
6 3
10 70% to
>45% RTP 8
6 4
2 5
45% RTP 4
3 2
1
- 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
Revision 30 Page 18 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
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%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 30 Page 19 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER 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:
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%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 30 Page 20 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN)
FRACTION OF RATED THERMAL POWER FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION RESTRICTED LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES)
TRANSIENT INSERTION LIMIT (75.0 INCHES)
(50% RATED THERMAL POWER)
Revision 30 Page 21 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0.0 5.0 10.0 15.0 20.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 AZIMUTHAL POWER TILT (%)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)
REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION
Revision 30 Page 22 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
5 10 15 20 25 50 60 70 80 90 100 COLSS DNBR POWER OPERATION LIMIT REDUCTION
(% OF RATED THERMAL POWER)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)
(80, 5)
(70, 0)
Revision 30 Page 23 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)
(-0.1, 1.93)
(-0.1, 2.28)
(0.06, 2.38)
(0.05, 2.00)
(0.1, 2.38)
(0.1, 2.00)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 30 Page 24 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 3.0 3.1 3.2 3.3 3.4 3.5 3.6
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI 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)
(-0.1, 3.27)
(0.0, 3.41)
(0.1, 3.41)
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 30 Page 25 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 30 Page 26 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 30 Page 27 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 30 Page 28 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 30 Page 29 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed