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{{#Wiki_filter:Technical Specification 5.6.5d Thomas N Weber                                       Mail Station 7636 Palo Verde Nuclear             Department Leader,         Tel. 623-393-5764       PO Box 52034 Generating Station             Regulatory Affairs         Fax 623-393-5442         Phoenix, Arizona 85072-2034 102-06095-TNW/REB/CJS November 17, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
{{#Wiki_filter:Technical Specification 5.6.5d Thomas N Weber Mail Station 7636 Palo Verde Nuclear Department Leader, Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-06095-TNW/REB/CJS November 17, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001


==Dear Sirs:==
==Dear Sirs:==
==Subject:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Revised Core Operating Limits Reports (COLRs), Units 1, 2 and 3 Pursuant to PVNGS Technical Specification, Section 5.6.5, enclosed are the revised Core Operating Limits Reports (COLRs). Unit 1 - Revision 20, Unit 2 - Revision 16, and Unit 3 - Revision 19, were made effective October 29, 2009. These revisions include changes resulting from License Amendment No. 174, dated August 26, 2009.
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Revised Core Operating Limits Reports (COLRs), Units 1, 2 and 3 Pursuant to PVNGS Technical Specification, Section 5.6.5, enclosed are the revised Core Operating Limits Reports (COLRs). Unit 1 - Revision 20, Unit 2 - Revision 16, and Unit 3 - Revision 19, were made effective October 29, 2009. These revisions include changes resulting from License Amendment No. 174, dated August 26, 2009.
By copy of this letter and the enclosures, these COLR revisions are being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector. This letter does not make any commitments to the NRC. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
By copy of this letter and the enclosures, these COLR revisions are being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector. This letter does not make any commitments to the NRC. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, TNW/RAS/CJS/gat -PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 20 -PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 16 -PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 19 cc:       E. E. Collins Jr.       NRC Region IV Regional Administrator J. R. Hall               NRC NRR Project Manager R. I. Treadway           NRC Senior Resident Inspector for PVNGS A member of the STARS   (Strategic Teaming and Resource Sharing) Alliance Callaway " Comanche Peak " Diablo Canyon " Palo Verde " San Onofre " South Texas             " Wolf Creek/(   (
Sincerely, TNW/RAS/CJS/gat -PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 20 -PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 16 -PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 19 cc:
 
E. E. Collins Jr.
Enclosure 1 PVNGS Unit I Core Operating Limits Report (COLR)
NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway " Comanche Peak " Diablo Canyon " Palo Verde " San Onofre " South Texas " Wolf Creek/(
(
PVNGS Unit I Core Operating Limits Report (COLR)
Revision 20
Revision 20


PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 Effective October 29, 2009 Responsible Engineer             Napier,                C Digitally signed by Napier, 1 Joseph J(Z71881)
UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 Effective October 29, 2009 Responsible Engineer C Digitally signed by Napier,
Date                                                           DN: cn=Napier, Joseph J Joseph J                I(4I Z71881)
: Napier, 1 Joseph J(Z71881)
                                                          ýl Reason: I am the author of tf 86bZment
Date DN: cn=Napier, Joseph J I(4I Z71881)
                                                              -this' (Z7188A)V.'                 Date 2009.10.27 16:17:19 n eDigitally signed by Bodnar, Independent Reviewer             Bodnar,d1                   Walter S(Z06432)
Joseph J ýl Reason: I am the author of tf  
Date                                                           DN: cn=Bodnar, Walter DateW alter S               (zo           dnart6er2S W Reason: I have reviewed
-this' 86bZment (Z7188A)V.'
                                                              -this document (Z06432ý )                   Date: 2009.10.27 16:22:54 0-7'00o
Date 2009.10.27 16:17:19 n e Digitally signed by Bodnar, Independent Reviewer
                                                            *". Digitally signed by Rowland,
: Bodnar, d1 Walter S(Z06432)
                                                =    !
Date DN: cn=Bodnar, Walter DateW alter S (zo dnart6er2S W Reason: I have reviewed
Responsible Section Leader       Rowland                     James W(Zbyown,
-this document (Z06432ý )
                                                            " DN: n=Rowland, James W Date                                                 I /(Z80533)
Date: 2009.10.27 16:22:54 0-7'00o
James vv ./IýReason:                   am approving this document as temporary R*"Reioad-Anrlysis SL (Z8053
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                                                    .. X       Date: 20096"10.27 17:04:16
*". Digitally signed by Rowland, Responsible Section Leader Rowland James W(Zbyown,
                                                                -0700' Page 1 of 26
" DN: n=Rowland, James W Date I /(Z80533)
James vv /IýReason:
am approving this document as temporary R*"Reioad-Anrlysis SL (Z8053 X Date: 20096" 10.27 17:04:16
-0700' Page 1 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT         Revision 20 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             8 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed           8 3.1.4 Moderator Temperature Coefficient (MTC)                       8 3.1.5 Control Element Assembly (CEA) Alignment                       8 3.1.7 Regulating CEA Insertion Limits                               8 3.1.8 Part Strength CEA Insertion Limits                             9 3.2.1 Linear Heat Rate (LHR)                                         9 3.2.3 Azimuthal Power Tilt (Tq)                                     9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR)                   9 3.2.5 Axial Shape Index (ASI)                                       10 3.3.12 Boron Dilution Alarm System (BDAS)                           10 3.9.1 Boron Concentration                                           10 Page 2 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 8
3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8
3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8
3.1.7 Regulating CEA Insertion Limits 8
3.1.8 Part Strength CEA Insertion Limits 9
3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT           Revision 20 List of Figures Description Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature                     11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature                     12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2                         13 Figure 3.1.5-1 Core Power Limit After CEA Deviation                           14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power                       15 (COLSS in Service)
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 List of Figures Description Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power                       16 (COLSS Out of Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power         17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power                       18 (COLSS in Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both                   19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core                   20 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)
Operable)
Operable)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core                   21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 26
Page 3 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT           Revision 20 List of Tables Description                                                                 Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron               22 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               23 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               24 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               25 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               26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                     Revision 20 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 Unit 1 Technical Specifications.
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Unit 1 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 26
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 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                             Revision 20 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents::
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents::
Title                             Report No.       Rev       Date     Sump CE Method for Control Element Assembly                 CENPD-         N.A. January     N.A.
Title Report No.
Ejection Analysis                                       0190-A                   1976 (13-N001-1301-01204-1)
Rev Date Sump CE Method for Control Element Assembly CENPD-N.A.
The ROCS and DIT Computer Codes for                     CENPD-         N.A. April       N.A.
January N.A.
Nuclear Design                                         266-P-A                 1983 (13-N001-1900-01412-0)
Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)
Modified Statistical Combination of                     CEN-           01-P-A   May         N.A.
The ROCS and DIT Computer Codes for CENPD-N.A.
Uncertainties                                           356(V)-P-A               1988 (13-N001 -1303-01747-2)
April N.A.
System 8 0 TM Inlet Flow Distribution                   Enclosure       N.A. February     1-P (13-N001 -1301-01228-0)                                 1-P to LD-               1993 82-054 Calculative Methods for the CE Large Break             CENPD-         N.A. March       4-P-A LOCA Evaluation Model for the Analysis of CE           132                     2001 and W Designed NSSS (13-NOO1- 1900-01192-3)
Nuclear Design 266-P-A 1983 (13-N001-1900-01412-0)
Calculative Methods for the CE Small Break             CENPD-         N.A. April       2-P-A LOCA Evaluation Model                                   137-P                   1998 (13-NOO - 1900-01185-3)
Modified Statistical Combination of CEN-01-P-A May N.A.
Fuel Rod Maximum Allowable Pressure                     CEN-372-       N.A. May         N.A.
Uncertainties 356(V)-P-A 1988 (13-N001 -1303-01747-2)
(13-NOO 1-0201-00026-1)                                 P-A                     1990 Arizona Public Service Company PWR Reactor             NFM-005         N.A. January     N.A.
System 8 0 TM Inlet Flow Distribution Enclosure N.A.
Physics Methodology Using                                                       2006 CASMO-4/SIMULATE-3 (NFM-005)
February 1-P (13-N001 -1301-01228-0) 1 -P to LD-1993 82-054 Calculative Methods for the CE Large Break CENPD-N.A.
Technical Description Manual for the CENTS             CE-NPD         2       March       N.A.
March 4-P-A LOCA Evaluation Model for the Analysis of CE 132 2001 and W Designed NSSS (13-NOO1-1900-01192-3)
CodeVolume 1                                           282-P-A                 2005 (CENTS-TD MANUAL-VOL 1)                                 Vols. 1 Technical Description Manual for the CENTS             CE-NPD         2       March       N.A.
Calculative Methods for the CE Small Break CENPD-N.A.
Code Volume 2                                           282-P-A                 2005 (CENTS-TD MANUAL-VOL 2)                                 Vols. 2 Page 6 of 26
April 2-P-A LOCA Evaluation Model 137-P 1998 (13-NOO -1900-01185-3)
Fuel Rod Maximum Allowable Pressure CEN-372-N.A.
May N.A.
(1 3-NOO 1-0201-00026-1)
P-A 1990 Arizona Public Service Company PWR Reactor NFM-005 N.A.
January N.A.
Physics Methodology Using 2006 CASMO-4/SIMULATE-3 (NFM-005)
Technical Description Manual for the CENTS CE-NPD 2
March N.A.
CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1)
Vols. 1 Technical Description Manual for the CENTS CE-NPD 2
March N.A.
Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2)
Vols. 2 Page 6 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                 Revision 20 Title                         Report No. Rev   Date     Suppi Technical Description Manual for the CENTS         CE-NPD     2     March       N.A.
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 Title Report No.
CodeVolume 3                                       282-P-A           2005 (CENTS-TD MANUAL-VOL 3)                             Vols. 3 Implementation of ZIRLOTM Cladding Material         CENPD-     0     November     N.A.
Rev Date Suppi Technical Description Manual for the CENTS CE-NPD 2
in CE Nuclear Power Fuel Assembly Designs           404-P-A           2001 (13-NOO1 -1900-01329-0)
March N.A.
HERMITE, A Multi-Dimensional Space-Time             CENPD-           July Kinetics Code for PWR Transients                   188-A             1976 (HERMITE-TOPICAL)
CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3)
TORC Code, A Computer Code for Determin-           CENPD-           April ing the Thermal Margin of a Reactor Core           161-P-A           1986 (NOO1-1301-01202)
Vols. 3 Implementation of ZIRLOTM Cladding Material CENPD-0 November N.A.
CETOP-D Code Structures and Modeling Meth-         CEN-             September ods for San Onofre Nuclear Generating Station       160(S)-P         1981 Units 2 and 3, (NOO1-1301-01185)
in CE Nuclear Power Fuel Assembly Designs 404-P-A 2001 (13-NOO1 -1900-01329-0)
CPC Methodology Changes for the CPC                 CEN-3 10-   0     April Improvement Program, (N001-1303-02283)             P-A               1986 Loss of Flow, C-E Methods for Loss of Flow         CENPD-     0     June Analysis, (NOO1-1301-01203)                         183-A             1984 Methodology for Core Designs Containing             CENPD-     0     August Erbium Burnable Absorbers                           382-P-A           1993 (NOO1-0201-00035)
HERMITE, A Multi-Dimensional Space-Time CENPD-July Kinetics Code for PWR Transients 188-A 1976 (HERMITE-TOPICAL)
Verification of the Acceptability of a 1-Pin Bur-   CEN-386-   0     August nup Limit of 60 MWD/kgU for Combustion             P-A               1992 Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)
TORC Code, A Computer Code for Determin-CENPD-April ing the Thermal Margin of a Reactor Core 161-P-A 1986 (NOO1-1301-01202)
CETOP-D Code Structures and Modeling Meth-CEN-September ods for San Onofre Nuclear Generating Station 160(S)-P 1981 Units 2 and 3, (NOO1-1301-01185)
CPC Methodology Changes for the CPC CEN-3 10-0 April Improvement Program, (N001-1303-02283)
P-A 1986 Loss of Flow, C-E Methods for Loss of Flow CENPD-0 June Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Containing CENPD-0 August Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)
Verification of the Acceptability of a 1-Pin Bur-CEN-386-0 August nup Limit of 60 MWD/kgU for Combustion P-A 1992 Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)
Page 7 of 26
Page 7 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                           Revision 20 The cycle-specific operating limits for the specifications listed are presented below.
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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.
3.1.1 - 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.
3.1.2 - 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.
Line 92: Line 124:
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 limitsi shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).
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 limitsi shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).
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 hours.
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 hours.
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:
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.
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
b) Regulating Group 5 position is maintained at least 10 inches lower than Page 8 of 26
b) Regulating Group 5 position is maintained at least 10 inches lower than Page 8 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                           Revision 20 Regulating Group 4 position.
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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).
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 - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 Fully withdrawn - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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.
Line 109: Line 141:
Page 9 of 26
Page 9 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                           Revision 20 3.2.5 - Axial Shape Index (ASI)
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
COLSS OPERABLE
COLSS OPERABLE
        -0.18*< ASI
-0.18*< ASI
* 0.17 for power > 50%
* 0.17 for power > 50%
        -0.28 < ASI < 0.17 for power >20% and < 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
COLSS OUT OF SERVICE (CPC)
COLSS OUT OF SERVICE (CPC)
        -0.10 < ASI < 0.10 for power >20%
-0.10 < ASI < 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
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.
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 _&#x17d;3000 ppm.
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 _&#x17d; 3000 ppm.
Page 10 of 26
Page 10 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                   Revision 20 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7   .                                                        .........                    ...        ..  ....  ......... (50050) 5 ....................------.--        ................--........................        ---  --......  ...................... . .......
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7  
......... (50050) 5....................-
REGION OF ACCEPTABLE OPERATION z
REGION OF ACCEPTABLE OPERATION z
z Z*3   -- --- --. . . .......
z Z* 3 REGION !OF UNACCEPTABLE OPERATION 0
REGION !OF UNACCEPTABLE OPERATION 0
0 100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 11 of 26
0                       100                         200                           300                   400                         500                        600 COLD LEG TEMPERATURE ('F)
Page 11 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                     Revision 20 I
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 I
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 .........          .........          I (500,6.5)i 6
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7
REGION OF ACCEPTABLE ............... OPERATION--:-
6 5
  . 4 (350,4.0) z 03 REGION OF UNACCEPTABLE 2                                            .................. -
. 4 z
I.....................
03 2
OPERATION 0                                        +/- . .l l .l . .l .ll l l .m .ll l                   l ..
0 I
                                                                                                  . l .l       l .
REGION OF ACCEPTABLE
                                                                                                              . .. l ll..
............... OPERATION--:-
0                   100               200                     300           400                   500            600 COLD LEG TEMPERATURE ('F)
+/-
Page 12 of 26
(500,6.5)i (350,4.0)
REGION OF UNACCEPTABLE I.....................
OPERATION
. l l
l l
l l
l m
l l
l l
l  
....l l l ll..  
..l 0
100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                                       Revision 20 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5
                                  ' mI    . . . .. I.--
-1.0.........-
                                          ..-          . . -. - - - ---- - - -                I. .. ..          . . .        .. . .. .I..  . . . . . .. .. ...
o z
                                                                                                                                            . ....                    . . . I.        . .
                                  ."!........          i.....                    (50%,0.0)
(100%,-0.2 o
  -1.0 .........-
U z
  -1.5  ............                  ..........................                            -CAREA                  OF ..................................................
W 0.
W 0.
<-                                                                           ACCEPTABLE 0
U 0
  -2.0                                                                     *:OPERATION F-0
F-0 0
                        -----------.   --. ----------............... I'............. ---.............I............ ..I..........................................
-1.5
0  -2.5
-2.0 m
  -3.0                  .. . . . .. .. . .. .. . .. .. . . . .. . .. -. -          . -
I
  -3.5
..... I....
  -4.0 4...........
I.
                        .. . .       i..
I
                                        --        . . i..
... I.
                                                        ---  ------I.                   . . .--   . ----    . ----
."!........ i.....
                                                                                                                  . .i... --  . .----                              ------        --. .- -
(50%,0.0)
  -4.5 0             10             20               30                 40                   50                     60                 70             80                 90           100 CORE POWER LEVEL
(100%,-0.2
-CAREA OF..................................................
ACCEPTABLE
:OPERATION
----------............... I'............. ---............. I.............. I..........................................
i....
i..
I.
i..  
-2.5
-3.0
-3.5
-4.0 4...........
-4.5 0
10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
(% OF RATED THERMAL POWER)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit .......
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit.......
Page 13 of 26
Page 13 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                   1tevision 20 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*                                       ASt 20 16 5100% to
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 1
                                                                          >80% RTP 15                                                                                15 z
FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
12           12 :580% to
tevision 20 ASt 20 15 z
                                                                          >70% RTP I 0 10                                                                                10 8                 8   -70% to
0 16 5100% to
                                                                          >45% RTP 5                                                                                5
>80% RTP 12 12
                                                                          -<45%RTP
:580% to
                                          -i 0
>70% RTP 8
i 0          10             20         30             40           50         60 TIME AFTER DEVIATION, MINUTES
8  
* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT I
-70% to
REQUIRED.
>45% RTP
Page 14 of 26
-<45% RTP 15 10 5
I 10 5
-i i
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.
Page 14 of 26 I


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                 Revision 20 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 0.9 -                                   -(SEE FOOTNOTE IN SECTION 31.;7.......-.-
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 0.9 -
FOR APPLICABILITY FOLLOWING 0.8 -
0.8 -
0.7                                    -GRP 4-POS-= (-12-.5-xFRAC.PWR)-+-25-5--
0.7 0.6 05 0T.
GRP 5 POS = (172.5:'x FRAC. PWR) - 64.5 0.6 0!
0 L
I .......................................
0.3 0.2 0!
                                                            ---              ........I          .......                     .......... .
Uz.
05 Uz.
-(SEE FOOTNOTE IN SECTION 31.;7.......-.-
0T.
FOR APPLICABILITY FOLLOWING
0 L  0.3 0.2                                    I 0.1 -
-GRP 4-POS-= (-12-.5-xFRAC.PWR)-+-25-5--
O0 GROUP5                           GROUP3                                           GROUP I I I   I   I     I     I     I     I   I     I       I         I         I         I         I       I       I       I FW* 120 90   60     30 0 FW* 120 90             60     30 0 FW* 120 90                                   60       30       0 GROUP 4                               GROUP 2 F)&#xfd;C* 1       P0OTI 34o           FIN           1C0           6W0 31DRW CEA POSITION (INCHES WITHDRAWN)
GRP 5 POS = (172.5:'x FRAC. PWR) - 64.5 I  
........ I 0.1 -
I O0 GROUP5 GROUP3 GROUP I I
I I
I I
I I
I I
I I
I I
I I
I I
I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP 4 GROUP 2 F)&#xfd;C*
1 P0 OTI 34o FIN 1C0 6W0 31DRW CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 15 of 26
Page 15 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                         Revision 20 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 1 0.8 0.7 0.6 05 0.4 0
                          .. .........iI--------  ....!--  ......
U 0.3 0.2 0.1
                                                                                                    ..-  --  ------  ----          .i. . . . ....*
J . . .i. .....
0.9 1 0.8         .............
                                                                  -.........      .(SEE FOOTNOTE-iN SEC-TION-3;[;7.........7 FOR APPIACABILITY FOLLOWING A: REACTOR CUTBACK) 0.7 0
0.6                       ------                      -        ----GRP-4POS-=(-250.9-X-FRAC.-PWR" +-9.82---
GRP 'PWOS = (250.9 i FRAC. PWR)- 80.18 05
                      . .... ....i.....    ... -- . . .
zz                              z 0.4 0
U 0.3
                                                    ...z,.........                                                              ---
                                      &#xa3;        ,
0.2
                                                                                                    --  .--  .I...........
0.1
('n
('n
            'J, GROUP5                                               GROUP3                                     GROUP I I   I   I         I         I I               I         I       I     I     I- I         I       I     I     I         I I FW* 120   90     60         30 0OFW* 120 90                             60   30   0 FW* 120           90     60       30       0 GROUP 4                                           GROUP 2 F         X%*
...........i....!......
10                   0       3         g Ft       It   L0O 6+0           t CEA POSITION (INCHES WITHDRAWN)
I --------
J....... i.....
.i............ *
.(SEE FOOTNOTE-iN SEC-TION-3;[;7.........7 FOR APPIACABILITY FOLLOWING A: REACTOR CUTBACK) 0
----GRP-4POS-=(-250.9-X-FRAC.-PWR" +-9.82---
GRP 'PWOS = (250.9 i FRAC. PWR)- 80.18
...... i.....
z zz
.z,........
.I...........
&#xa3;
'J, GROUP5 GROUP3 GROUP I I
I I
I I I I
I I
I I-I I
I I
I I I FW* 120 90 60 30 0OFW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP 4 GROUP 2 F
X%*
10 0
3 g Ft It L0O 6+0 t
CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 16 of 26
Page 16 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                     Revision 20 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 - -----------    ---------                  .....................          -----  -- ----            ...........................
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 20 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 z
20.0 . ...........    ...........                -----------                    ..........                    ---------------------  --------
z r-
30.0 . ......................                                  ---------------- .............                .............................
,.nF-0Z u) z
40.0 . ...........    ----------                                                .............                          ------------- --------
!TRANSIENT INSERTION LIMIT (75.0:INCHES) 80.0 90.0 IO............
z    50.0 - -----------    ----------                                  .............  -------------                          ............. ........
OT..........I UNACCEPTABLE L......:.............
60.. ...........   ......                                     ............. .............
......... OPERATION..................
0Z  70.0  .......................
RESTRICTED I
                                                                                      !TRANSIENT INSERTION LIMIT (75.0:INCHES) u)                                                                                                    I         I           I               I F-
I I
,.n 80.0 zz OT..........I
I 100.0 110.0 120.0 130.0 140.0 150.0 1.(
                          ............. ---      IO ............
.6 LONG TERM STEADY STATE INSERTION:LIMITSI (112.5 INCHES)
r-  90.0                                                                                  ......... OPERATION ..................
.............. i..............................
UNACCEPTABLE                                                                RESTRICTED 100.0 L-- . --
I ------------
110.0
OPERATION ACCEPTABLE I..
                                              ..............i...... -------                                    I------------
I.
                                                                                            .6        ...
I I-..
120.0 LONG TERM STEADY STATE INSERTION:LIMITSI (112.5 INCHES) 130.0 OPERATION ACCEPTABLE 140.0
J 1..
              . . . . I ....-          . -.I .   . .-.. I       I-..   - ..-. J 1.- . . ..-      -..                  I   ...   . I . . . .
I...
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 17 of 26
I.
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 17 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                                           Revision 20 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0   --   -- -                -RE G I O N OF --------------
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 F-0
UNACCEPTABLE OPERATION F-0  10.0                              .. . .. .. . . . . . . . . .. . . . . . . . . .. .. . .. .. . . . . . . . . . . . . . . . . .... .. . . . .. . . . . . . . .. . . .. . .. .. . .. . ..-
:z-10.0 REGION OF
:z-5.0 REGION OF WLCEPTABLE OPERATION 0.u -
-R E G I O N O F --------------
20.0 30.0   40.0       50.0                     60.0                           70.0                             80.0                           90.0                         100.0 CORE POWER LEVEL
UNACCEPTABLE OPERATION 5.0 WLCEPTABLE OPERATION 0.u -
20.0 30.0 40.0 50.0 60.0 70.0 CORE POWER LEVEL 80.0 90.0 100.0
(% OF RATED THERMAL POWER)
(% OF RATED THERMAL POWER)
Page 18 of 26
Page 18 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                       Revision 20 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 0
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 20 25 20......
20 ......          ----------
0 E0 15 I-
                                                                                            /...
/...
15 I-                                                     ....................
101-5 0
E0 101-         ....................
5           ....................
:(80,5)
:(80,5)
(70,0):
(70,0):
11                 Illlllll 0            I I   I 50                   60                       70                           80       90        100 CORE POWER LEVEL
11 I
(% OF RATED THERMAL POWER)
I I
Page 19 of 26
Illlllll 50 60 70 80 CORE POWER LEVEL
(% OF RATED THERMAL POWER) 90 100 Page 19 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                         Revision 20 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5   .. .......         !.........           I                , ,&deg; , ,o., ,,l.. .l,,   .  ... l...    ...  ...      . ...    .. ..
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 2.3 I
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0,06,2.38)                               (0.1,2.3 8):
z 0
                                                                                                                                                  ...i ...... ........
2.2 2.1
2.3
(-0.1,2.28)
(-0.1,2.28) z 2.2 ACCEPT~ABLE OPERATION POWER AT OR ABOVE 90%
(... 1193)............
0 AT LEAST 1 CEAC OPERABLE IN 2.1                                            ....EACH OPER-ABILE-CPC CHtANNELA'-......                                                            ----------------..
,,&deg;,,,,l
,o.  
..l,,
l...
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0,06,2.38)
(0.1,2.3 ACCEPT~ABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN
....EACH OPER-ABILE-CPC CHtANNELA'-......
(0.05,2.00)
(0.05,2.00)
        ..........     (... 1193)............     ................. I................. ............. * ' ........           "*0. 12 .01 2.0 UNACCEPTABLE
................. I.............................. * '........  
                                                  ......... ............. OP E RAT ION ....................................
"*0. 12.01 UNACCEPTABLE
1.9
...................... O P E R A T IO N....................................
                                                  . . . . . . . .. I . . . . . . .. . I .. . . . . . . I .. . . . . . . . ! . .       .     .
......... I......... I........
1.8 i fl i i i fl i 1I i
I......... !.
* i i ..... II                                                                                                        i iI .. . . . I l iI
8):
    -0.20             -0.15                 -0.10               -0.05                 0.00           0.05               0.10                   0.15                 0.20 CORE AVERAGE ASI Page 20 of 26
...i..............
2.0 1.9 1.8 I
i fl i i i fl i 1 I i
* i i..... I i i I..... I l i I
-0.20  
-0.15  
-0.10  
-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                                 Revision 20 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   IIgDHllll             Illl                                                                                                         l'    'r  '    '    .   ,  .,  i ACCEPTABLE :OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5  I
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 IIgDHllll Illl 3.5 I 3.4 z
                                              ... . ...---        --  ---  --  --  --  -----    ---B:E.................  ........
u C..)
IN ANY OPERABLE CPC CHANNEL
3.3 ACCEPTABLE :OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE B:E IN ANY OPERABLE CPC CHANNEL
( 1,3.4 1) 3.4  - ---------------    : .........
(-0.i.3.27)
z 3.3  - ---------------      .........
UNACCEPTABLE OPERATION
u                                              (-0.i.3.27)
( 1, 3.4 1) l'
C..)
'r i
3.2 P--
3.2 P--
UNACCEPTABLE OPERATION 3.1 - --------------
3.1 3.0 1.
m .. .. .. .... .. .. .. .. I .
1..
                                          . . . . . .. .. 1                                            . I .. . . . . . .  . I .. . .
.. I.
3.0 ..   . . .
I..
                  . ..           1 .. ..                                               . .
I..  
                                                                                          . . . . . ..                                . . . ..    . 1 . 1 . . . ..    . . . .. . . .
......... m.........
        -0.20               -0.15                 -0.10                       -0.05                   0.00               0.05             0.10                   0.15             0.20 CORE AVERAGE ASI Page 21 of 26
. 1. 1.....  
 
-0.20  
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                  Revision 20 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                  Number of Operating Charging Pumps MODE                      0              1          2            3 3                    12 hours      0.5 hours    ONA          ONA 4 not on SCS          12 hours      0.5 hours    ONA          ONA 5 not on SCS          8 hours      0.5 hours    ONA          ONA 4 & 5 on SCS            ONA            ONA        ONA          ONA Notes:    SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26
-0.15  
-0.10  
-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                 Revision 20 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 &#x17d; Keff > 0.97 OPERATIONAL                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours         1 hour    0.5 hours     ONA 4 not on SCS         12 hours       1.5 hours    0.5 hours     ONA 5 not on SCS           8 hours       1.5 hours    0.5 hours     ONA 4 & 5 on SCS           8 hours      0.5 hours      ONA         ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                 Revision 20 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 &#x17d; Keff> 0.96 OPERATIONAL                 Number of Operating Charging Pumps MODE                     0               1         2           3 3                     12 hours       2.5 hours   1 hour        ONA 4 not on SCS         12 hours       2.5 hours   1 hour      0.5 hours 5 not on SCS           8 hours       2.5 hours   1 hour      0.5 hours 4 & 5 on SCS           8 hours         1 hour    ONA           ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 &#x17d; Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                 Revision 20 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                 Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours       3 hours     1 hour     0.5 hours 4 not on SCS         12 hours       3.5 hours   1.5 hours  0.75 hours 5 not on SCS           8 hours       3.5 hours   1.5 hours  0.75 hours 4 & 5 on SCS           8 hours       1.5 hours  0.5 hours      ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 &#x17d; Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26


PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                   Revision 20 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                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours       4 hours     1.5 hours     1 hour 4 not on SCS         12 hours       4.5 hours     2 hours     1 hour 5 not on SCS           8 hours       4.5 hours     2 hours     1 hour 4 & 5 on SCS           8 hours       2 hours     0.75 hours    ONA 6                    24 hours      1.5 hours       ONA        ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 3 hours 1 hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26


Enclosure 2 PVNGS Unit 2 Core Operating Limits Report (COLR)
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6
24 hours 1.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26 PVNGS Unit 2 Core Operating Limits Report (COLR)
Revision 16
Revision 16


O'Connor,                                   ,
Digitally signed by O'Connor, Tina O'Connor,  
Digitally signed by O'Connor, Tina M(Z06952)
, M(Z06952)
Ti na M ~                                  J n6ason:oi2 SODN- cn=O'Connor, Tina M (Z06952) attest to the accuracy
SODN-cn=O'Connor, Tina M Ti na M ~
[7Cic(*                 rQ         ,/-       nd integrity of this document (Z0695                               '2       Date: 2009.10.28 05:57:33 -07'00' PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
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UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 Effective 10/29/2009 Responsible Engineer               Foste r,                          lDigitally signed by Foster, Date
[7Cic(*
rQ  
,/-
nd integrity of this document (Z0695  
'2 Date: 2009.10.28 05:57:33 -07'00' PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 Effective 10/29/2009 Responsible Engineer lDigitally signed by Foster, Foste r,
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Date DN: cn=Foster, Glenn A Glenn. A  
G         le
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/--,m,,*
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                                                                ,* ),,&#xfd;_document, Date: 2009.10.27 16:10:17 (Z. 3 5. 83                             -07'00' Independent Reviewer                   -,                            .*  Digitally signed by Delorenzi,;                         Delorenzi, Mark J(Z01931)
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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT         Revision 16 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           8 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed         8 3.1.4 Moderator Temperature Coefficient (MTC)                       8 3.1.5 Control Element Assembly (CEA) Alignment                     8 3.1.7 Regulating CEA Insertion Limits                               8 3.1.8 Part Strength CEA Insertion Limits                           9 3.2.1 Linear Heat Rate (LHR)                                       9 3.2.3 Azimuthal Power Tilt (Tq)                                     9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR)                 9 3.2.5 Axial Shape Index (ASI)                                     10 3.3.12 Boron Dilution Alarm System (BDAS)                         10 3.9.1 Boron Concentration                                         10 Page 2 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 8
3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8
3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8
3.1.7 Regulating CEA Insertion Limits 8
3.1.8 Part Strength CEA Insertion Limits 9
3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT           Revision 16 List of Figures Description                                                                 Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature                     11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature                     12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2                         13 Figure 3.1.5-1 Core Power Limit After CEA Deviation                           14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power                       15 (COLSS in Service)
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power                       16 (COLSS Out of Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power         17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power                       18 (COLSS in Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both                   19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core                   20 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)
Operable)
Operable)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core                   21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 26
Page 3 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT           Revision 16 List of Tables Description                                                                 Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron               22 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               23 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               24 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               25 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               26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                     Revision 16 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 Unit 2 Technical Specifications.
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Unit 2 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 26
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 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                           Revision 16 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
Title                         Report No.       Rev         Date       SuWpl ement
Title Report No.
: 1) CE Method for Control Element Assem-             CENPD-        N.A.      January      N.A.
Rev N.A.
bly Ejection Analysis (NOO-1301-01204-1)             0190-A                    1976
Date January 1976
: 2) The ROCS and DIT Computer Codes for               CENPD-        N.A. April 1983      N.A.
: 1) CE Method for Control Element Assem-bly Ejection Analysis (NOO-1301-01204-1)
Nuclear Design (NOO1-1900-01412-0)               266-P-A
: 2) The ROCS and DIT Computer Codes for Nuclear Design (NOO1-1900-01412-0)
: 3) Modified Statistical Combination of             CEN-        01-P-A    May 1988        N.A.
: 3) Modified Statistical Combination of Uncertainties (NOO1-1303-01747-2)
Uncertainties (NOO1-1303-01747-2)            356(V)-P-A    (ARI)    (April 1996)
: 4) System 80 TM Inlet Flow Distribution (NOO1-1301-01228-0)
: 4) System 8 0 TM Inlet Flow Distribution         Enclosure      N.A.      February        1-P (NOO1-1301-01228-0)                     1-P to LD-                  1993 82-054
: 5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (NOOl-1900-01192-3)
: 5) Calculative Methods for the CE Large           CENPD-        N.A. March 2001      4-P-A Break LOCA Evaluation Model for the                 132 Analysis of CE and W Designed NSSS (NOOl-1900-01192-3)
: 6) Calculative Methods for the CE Small Break LOCA Evaluation Model (NOO1-1900-01185-3)
: 6) Calculative Methods for the CE Small             CENPD-        N.A. April 1998    2-P-A Break LOCA Evaluation Model                     137-P (NOO1-1900-01185-3)
: 7) Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026-1)
: 7) Fuel Rod Maximum Allowable Pressure             CEN-372-      N.A.      May 1990      N.A.
: 8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
(NOO1-0201-00026-1)                         P-A
: 9) Technical Description Manual for the CENTS CodeVolume 1 (CENTS-TD MANUAL-VOL 1)
: 8) Arizona Public Service Company PWR             NFM-005        N.A.      January      N.A.
: 10) Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
Reactor Physics Methodology Using                                           2006 CASMO-4/SIMULATE-3 (NFM-005)
: 11) Technical Description Manual for the CENTS CodeVolume 3 (CENTS-TD MANUAL-VOL 3)
: 9) Technical Description Manual for the           CE-NPD          2    March 2005      N.A.
CENPD-0190-A CENPD-266-P-A SuWpl ement N.A.
CENTS CodeVolume 1                       282-P-A (CENTS-TD MANUAL-VOL 1)                         Vols. I
N.A.
: 10) Technical Description Manual for the           CE-NPD          2    March 2005      N.A.
N.A.
CENTS Code Volume 2                       282-P-A (CENTS-TD MANUAL-VOL 2)                         Vols. 2
April 1983 CEN-356(V)-P-A Enclosure 1-P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A 01-P-A (ARI)
: 11) Technical Description Manual for the           CE-NPD          2     March 2005      N.A.
N.A.
CENTS CodeVolume 3                        282-P-A (CENTS-TD MANUAL-VOL 3)                        Vols. 3 Page 6 of 26
May 1988 (April 1996)
February 1993 N.A.
1-P N.A.
March 2001 4-P-A N.A.
April 1998 2-P-A N.A.
May 1990 N.A.
NFM-005 N.A.
January 2006 N.A.
CE-NPD 282-P-A Vols. I CE-NPD 282-P-A Vols. 2 CE-NPD 282-P-A Vols. 3 2
March 2005 2
March 2005 2
March 2005 N.A.
N.A.
N.A.
Page 6 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT               Revision 16 Title                       Report No. Rev  Date        Sumel ement
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 Title
: 12) Implementation of ZIRLOTM Cladding           CENPD-    0  November      N.A.
: 12) Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (NO01-1900-01329-0)
Material in CE Nuclear Power Fuel           404-P-A        2001 Assembly Designs (NO01-1900-01329-0)
: 13) HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients
: 13) HERMITE, A Multi-Dimensional                 CENPD-        July 1976 Space-Time Kinetics Code for PWR Transients 188-A                            I
: 14) TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core.
: 14) TORC Code, A Computer Code for               CENPD-        April 1986 Determining the Thermal Margin of a           161-P-A Reactor Core.
: 15) CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOO 1-1301-01185)
: 15) CETOP-D Code Structures and Model-             CEN-        September ing Methods for San Onofre Nuclear           160(S)-P        1981 Generating Station Units 2 and 3 (NOO 1-1301-01185)
: 16) CPC Methodology Changes for the CPC Improvement Program (NOO1-1303-02283)
: 16) CPC Methodology Changes for the CPC           CEN-3 10-  0    April Improvement Program (NOO1-1303-                 P-A          1986 02283)
: 17) Loss of Flow, C-E Methods for Loss of Flow Analysis (NOO1-1301-01203)
: 17) Loss of Flow, C-E Methods for Loss of                   0    June Flow Analysis (NOO1-1301-01203)
: 18) Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (NOO 1-0201-00035)
CENPD-183-A          1984              I
: 19) Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (NO0 1-0201-00042)
: 18) Methodology for Core Designs Contain-         CENPD-    0  August ing Erbium Burnable Absorbers (NOO 1-         382-P-A        1993 0201-00035)
Report No.
: 19) Verification of the Acceptability of a 1-     CEN-386-  0  August Pin Burnup Limit of 60 MWD/kgU for             P-A          1992 Combustion Engineering 16 x 16 PWR Fuel (NO0 1-0201-00042)
CENPD-404-P-A CENPD-188-A CENPD-161-P-A Rev Date Sumel ement 0
Page 7 of 26
November 2001 July 1976 April 1986 N.A.
I CEN-160(S)-P September 1981 April 1986 CEN-3 10-P-A CENPD-183-A CENPD-382-P-A CEN-386-P-A 0
0 0
0 June 1984 I
August 1993 August 1992 Page 7 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                           Revision 16 The cycle-specific operating limits for the specifications listed are presented below.
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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.
3.1.1 - 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.
3.1.2 - 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)
3.1.4 - Moderator Temperature Coefficient (MTC)
Line 385: Line 545:
Page 8 of 26
Page 8 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                           Revision 16 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).
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 Fully withdrawn - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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)
3.2.1 - Linear Heat Rate (LHR)
Line 397: Line 557:
Page 9 of 26
Page 9 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                           Revision 16 3.2.5 - Axial Shape Index (ASI)
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
COLSS OPERABLE
COLSS OPERABLE
        -0.18*< ASI *0.17 for power > 50%
-0.18*< ASI *0.17 for power > 50%
        -0.28 < ASI < 0.17 for power >20% and < 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
COLSS OUT OF SERVICE (CPC)
COLSS OUT OF SERVICE (CPC)
        -0.10 < ASI < 0.10 for power >20%
-0.10 < ASI < 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
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.
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.
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 10 of 26
Page 10 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                           Revision 16 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 .. .          ..        ,, , ,            , .. . . .        . . . ..            . . . . . . . .. . . . ,. ,. ..  .
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7..
REGION OF ACCEPTABLE/
REGION OF ACCEPTABLE/
OPERATION z
OPERATION z
z REGIONOF
z REGIONOF UNACCEPTABLE
                                                                        ---- ---              ------ ---i:*
........ i:
UNACCEPTABLE OPERATION (350,1::.0) o                   100                     200             300               400                   500             600 COLD LEG TEMPERATURE ('F)
OPERATION (350,1::.0) o 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F)
Page 11 of 26
Page 11 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                               Revision 16 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7I (51 6                                                                         -------------            . ......
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7I (51 6
REGION OF ACCEPTABLE-5    ............... OP E l A TIAo N...,..--..-- ............--...........-------------
5 4
4 Zg4                                                                          (350,4.0) z 03      Z 0
z 03 2
0 REGION OF ACCEPTABLE-
............... O P E l A TIA o N...,..--..--
g4 Z
Z 0
3
[-,
[-,
                                                                  'REGION OF UNACCEPTABLE 2                                                ............. ........................
(350,4.0)
T I --                                    ..........
'REGION OF UNACCEPTABLE T I OPERATION
OPERATION 0    .l.ll.l.liL1L       i .1                     .  .  .  .                                          . . . ...... J.
.l.ll.l.liL1L i.1 J.  
                                                                                                                            . . .L..
...L..
0                   100               200               300                       400             500                      600 COLD LEG TEMPERATURE ('F)
0 100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26
Page 12 of 26 3


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                                                                                             Revision 16 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5 0.0
      -                   "%0.
-0.5
                              '&#xfd; ,:' . ..                       * .*' " ' . .' ..... i.. .                                                            . ., . ., . .
-1.
0.0                                                                                                                                                                        (100%,-o.
z o
  -0.5    ............................
-1.5 0
  -1.
U
z o -1.5  ..................                                        ............. MTC..............
-2.0 1
                                                                                              - A R EA O F-                       ...................................................
-2.5
0
-3.0 0
                                                                                    -ACCEPTABLE U
-3.5
OPEPATION
-4.0
  -2.0 1 -2.5
-4.5
                                -------------..                                          -. -. .- -. -. . . . . . . . . I,--
"%0.  
< -3.0 0        -0%,-3.4)
'&#xfd; '...
  -3.5  -  -- --                                                                                            ------------.......-                                  -----------
*.* ' " '..'..... i...
  -4.0                                                                                                                                                                                                                  I
(100%,-o.
                                                                          .                . . . . i.--    . .-------
M TC..............
  -4.5    I I ml 0                   10             20                     30             40                   50             60                 70               80                 90                       100 CORE POWER LEVEL
A R E A O F-  
-ACCEPTABLE OPEPATION I,--  
-0%,-3.4)
.... i....
I I I m l 0
10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
(% OF RATED THERMAL POWER)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit ........
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit........
Page 13 of 26
Page 13 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                               Revision 16 FIGURE 3.1.5-1 CORE POXVER REDUCTION AFTER CEA DEVIATION*
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.5-1 CORE POX 92 15 z0 r-ug~
92    .........                                                                                                              20          ...
0-VER REDUCTION AFTER 16 -100% to
16 -100% to
>80% RTP 1
                                                                                                                >80% RTP 15                                                                                                                          15 z0 r-  -
: 12.
1          .    . 12. 80% to ug~
80% to
                                                                                                                >70% RTP 1o 9---- ---  ........- ---      7-----
>70% RTP 9----
10 8     -70% to
7-----
                                                                                                                >45% RTP 6
1o CEA DEVIATION*
5                                                                                  ----------------
20 15 10 5
8  
-70% to
>45% RTP 6
5
5
:!&#xfd;45% RTP
:!&#xfd;45% RTP 0
          -                0-0                                                                   ................                    ...................
I I
I
1.1......I.......................................
              . . . . . . . . . 1 . 1 . . . . . . II . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
0 10 20 30 40 TIME AFTER DEVIATION, MINUTES 50 60
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.
* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT I
I Page 14 of 26
REQUIRED.
Page 14 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                               Revision 16 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
            , r, I.U 0.9                       -- -----
, r, I.U 0.9 0.8 0.7 R
                                            ----- --------              (SEEFOO.TNOT-E IN SEACTI N -31.7---------
0.6 0.5 0
z 0.4 0
0.3 0.2 0.1 00l (SEE FOO.TNOT-E IN SEACTI N -31.7---------
FOR XPPLICA&#xfd;BILi'1Y FOLLOWIMNG::
FOR XPPLICA&#xfd;BILi'1Y FOLLOWIMNG::
0.8                                                          A REACTOR CUTBACK)                               ..................
A REACTOR CUTBACK)  
0.7                                  .      .....        . ....  -RP-4-POS=-(72-5--xFRA*C.-PWR)                           +-25..
-RP-4-POS=-(72-5--xFRA*C.-PWR)  
R                                                                GRP 5 POS = (*72.5::x FRAC. PWR                               -64.5
+-25..
        <    0.6 z.
GRP 5 POS = (*72.5::x FRAC. PWR -64.5
0.5        J1 0
: z.....
z   0.4 0
J1 e*
0.3    .. .  .....................................                                                                      ....... ........
* m
0.2    -    . . ,.-          -...............                                                    .--------  .---- - ...............
:e J
e* ! *
GROUP 5 GROUP 3 GROUP I I
* m:        :e : *    !          :          :      :          :                  :          J 0.1 00l GROUP 5                                             GROUP 3                                       GROUP I I   I     I         I         I I             I       I   I     I       I         I       I         I I               I       I   I FW* 120 90           60       30         0 FW* 120           90   60     30         0 FW* 120                 90       60       30   0 GROUP 4                                     GROUP 2 Ft 1A0 9P0 6OS 3ITO                             FN W*ITHD                   6A0      3+0 CEA POSITION (INCHES WITHDRAWN)
I I
I I I I
I I
I I
I I
I I I
I I
FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP 4 GROUP 2 Ft 1A0 9P0 6OS 3ITO FN W*ITHD 6A 0
3+0 CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 15 of 26
Page 15 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                                               Revision 16 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8                         -....
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 0.7 2
                                          --------          -----  .....           .(SEE-FOOTNO-T-EIN SECTInON 3i7.1-.7                                             --
0.6 0.5 0
FOR APPLICABILITY FOLLOWI'NG
z 0.4 0p U.J
                              . ....                              i ........ ........ A: --
&#xa3; 0.3 0.2 0.1 nf
                                                                  ......                     -- ........ .......CUTBACK)
.(SEE-FOOTNO-T-EIN SECTInON 3i7.1-.7 FOR APPLICABILITY FOLLOWI'NG A: REACTOR CUTBACK)
REACTOR                                    i .......i ...... *.......... *.....
PGRP4POS-=(250.9-jcFRA-C.PWRt+-9.82-aGRP 5,P08 (250.9 i FRAC. PWR) -80.18 i
0.7 2
ii i
ii              :                        i                                                            :        i
...... i................  
        <  0.6                                                          PGRP4POS-=(250.9-jcFRA-C.PWRt+-9.82-aGRP                                                  5,P08        (250.9 i FRAC. PWR)                          -80.18 0.5                              P:
.......................................... i.......i.......*........ *.....
0                                                                                                                                                  .......   ......
.I-I P:
0.4                I        .I-z 0
. m - --:...... -- --
p
i GROUP5 GROUP 3 GROUP 1 I
        &#xa3;    U.J 0.3        . ... m *- --:.. ... . ------      i ........
I I
0.2 0.1 nf GROUP5 I         I           I       I           I     I     I GROUP I I 3I                  I       I         I       GROUP 1 I I             I         I       I FW* 120 90                       60         30 0 FW* 120 90                         60     30 0 FW* 120 90                             60         30       0 GROUP 4                                       GROUP 2 Ft*               A POSII 6N0           N3Co CEA POSITION (INCHES WITHDRAWN)
I I
H FWIt HD                      6+A
I I I I
I I
I I
I I I
I I
FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP 4 GROUP 2 Ft*
A POSII 6N0 N3Co H FWIt HD 6+A CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 16 of 26
Page 16 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                                                             Revision 16 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 40.0 50.0 rti 60.0 Z
  "  40.0 50.0 rti 60.0 Z     70.0                                     *TRANSIEN                                                           T INSERTION, LIMIIT (75.0 INCHES}
70.0 0
0 o    80.0
o 80.0 u
<                                      ERA.TIO.N
90.0 z
                                          ..............           .          .                                  O---------
100.0 110.0 120.0 130.0 140.0 1*O 0
P-E-RATIO   ---------    N ........................
*TRANSIEN T INSERTION, LIMIIT (75.0 INCHES}
u 90.0 UNACCEPTABLE                                                                         RESTRICTED z    100.0
E..............
"    110.0
RA.TIO.N.
                    ----. . .b ... ..A......        IO        N .. -...i....... ...i........... ..OP R ..T. ..-
O ---------
                                                            .....                                                                          O .---    ....
P-E-RATIO N........................
LONG TERM         UN STEADY                       STATE INSERTIONLIMITSEI RTINACCEPTABLE                                      kSRCE (112.5 INCHESM P               ............- -I   ..-...---... . ..............
UNACCEPTABLE RESTRICTED LONG TERM STEADY STATE INSERTIONLIMITSEI (112.5 INCHESM P  
L........................ .............
............ - -I L...........
120.0
b A I O N
            . . . . . . . . . . . ... ............ ::........---          .--. i---
.....i.......i...  
130.0 140.0
.......... O P R T O ---
                            .I .... . . . . l..
UN RTINACCEPTABLE kSRCE
                                                  . . .     . . . -. ----. .--  l.. -. --
.......................... ::..........i.......................  
                                                                                        . ----  Ii.. --- ---. ......        . . ... .....    . . I -------- -----    ----
..I
1*O
: l....
    *VmV0 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 17 of 26
l..
i..
I
.. I ---  
*VmV 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 17 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                     Revision 16 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0                                                                               I 1 15.0     ----------
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 e-0 F-10.0
:---.........  ........ ........ ...R EG ION O F .............---           ...............
................... R E G IO N O F.............---
UNACCEPTABLE OPERATION e-0  10.0                                            --- ---- --  ... ... ----- -----
UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPEl I I 1
F-5.0 REGION OF ACCEPTABLE OPElRATION
I 1 5.0 RATION
            ,                I I              .                      1   , , , .
(~ fl I 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 CORE POWER LEVEL
(~ fl I 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)
(% OF RATED THERMAL POWER)
Page 18 of 26
Page 18 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                 Revision 16 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95,20) 20 -
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 16 25 20 -
0 15  ...........  -----------
0 z
z 10 -
0 z
0 z
                                                      .... --- - (80 )..........................................
15 10 -
5               -----------
( 70,0)
( 70,0) 0      .      . .  .      . .  .    .      .  .  . I   1 I   .    .          .    .    .    .
(95,20)
50                   60                 70               80                   90                        100 CORE POWER LEVEL
(8 0 )..........................................
(%OF RATED THERMAL POWER)
5 0
Page 19 of 26
I 1
 
I 50 60 70 80 CORE POWER LEVEL
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                                                    Revision 16 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5    i-I-Iwl        S.. ...    ...    . . ........              .....    ....      .......        ..    ...    ....  .. IV    l  ll    l  I  l  l  ~l ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 ------------    . ..................        ......... --.. --
(% OF RATED THERMAL POWER) 90 100 Page 19 of 26
(006,2 38)(01,3)                              (0-1,2.38)::
2.3  ------------  .................
(-0.1 2.28) 2.2              .......  .......    ......- ........ ......... :.....................................................          ----------------- --------------
I      ACCEPTABLE I                          OPERATION z                                              ll    POWER AT OR ABOVE 9W%
AT LEAST 1 CEAC OPERABLE IN u
2.1                    --....-..-------..... -EACH OPERABLE CPC-CIIANNEL" ------------                                                                ..............
S((.0,0,2.00) 2.0                                                                                                                                &#xfd;G.-I 1-00y ..............
(119 3)                    $            &deg;          UNACCEPTARLE 1.9                                ..            . ............ O PER AT ION ---.................. .................                                --------------
1.8 L
    -0.2.0        -0.15                -0.10                    -0.05              0.00                0.05                  0.10                0.15          0.20 CORE AVERAGE ASI Page 20 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                                                                                   Revision 16 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      ----------
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 2.3 i-I-Iwl z
IN ANY OPERABLE CPC CHANNEL 3.................          -----                  r (00(3 4- 1) --
u 2.2 2.1 S.....
                                              ....................                                              0.1,3.41)::
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (006,2 38)(01,3)
0.--------41) 3.3  ................                                                                                       -----
(-0.1 2.28)
0.)
I ACCEPTABLE OPERATION I
(-0.03.27) 3.................      ....- . ......
ll POWER AT OR ABOVE 9W%
UNACCEPTAB&#xfd;LE OPERATION 3.1   ----------------                                                                                        ----------  ..........
AT LEAST 1 CEAC OPERABLE IN
                                  .I 3.0        .... ......... ...1.1 ... ......... ......... ......                                                          ........
-EACH OPERABLE CPC-CIIANNEL" S((.0,0,2.00)
      -0.20      -0.15     -0.10             -0.05         0.00                   0.05               0.10           0.15       0.20 CORE AVERAGE ASI Page 21 of 26
(119 3)  
&deg; UNACCEPTARLE
............ O PE R A T IO N ---..................
IV l ll l
I l
l ~ l (0-1,2.38)::
&#xfd;G. -I 1-00y..............
2.0 1.9 1.8 L
-0.2.0
-0.15  
-0.10  
-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                 Revision 16 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                  Number of Operating Charging Pumps MODE                      0               1         2           3 3                     12 hours      0.5 hours    ONA          ONA 4 not on SCS          12 hours      0.5 hours    ONA          ONA 5 not on SCS          8 hours      0.5 hours    ONA          ONA 4 & 5 on SCS            ONA            ONA        ONA          ONA Notes:    SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 3.5 3.4 0.)
3.3 ACCEPTABLE ::OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL r (00(3 4-1) --
0.--------41)
(-0.03.27)
UNACCEPTAB&#xfd;LE OPERATION
.I 0.1,3.41)::
3.2 3.1 3.0
.......1.1...................
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                 Revision 16 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 &#x17d; Keff > 0.97 OPERATIONAL                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours         1 hour    0.5 hours     ONA 4 not on SCS         12 hours       1.5 hours    0.5 hours     ONA 5 not on SCS           8 hours       1.5 hours    0.5 hours     ONA 4 & 5 on SCS           8 hours      0.5 hours      ONA         ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                   Revision 16 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 &#x17d; Keff> 0.96 OPERATIONAL                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours       2.5 hours     1 hour        ONA 4 not on SCS         12 hours       2.5 hours     1 hour      0.5 hours 5 not on SCS           8 hours       2.5 hours     1 hour      0.5 hours 4 & 5 on SCS           8 hours         1 hour      ONA           ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 &#x17d; Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                 Revision 16 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 &#x17d; Keff> 0.95 OPERATIONAL                 Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours       3 hours     1 hour     0.5 hours 4 not on SCS         12 hours       3.5 hours   1.5 hours  0.75 hours 5 not on SCS           8 hours       3.5 hours   1.5 hours  0.75 hours 4 & 5 on SCS           8 hours       1.5 hours  0.5 hours      ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 &#x17d; Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26


PVNGS UNIT 2 CORE OPERATING LIMITS REPORT                   Revision 16 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                   Number of Operating Charging Pumps MODE                     0               1           2             3 3                     12 hours       4 hours     1.5 hours     1 hour 4 not on SCS         12 hours       4.5 hours     2 hours       1 hour 5 not on SCS           8 hours       4.5 hours     2 hours       1 hour 4 & 5 on SCS           8 hours       2 hours   0.75 hours      ONA 6                    24 hours      1.5 hours     ONA          ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 &#x17d; Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 3 hours 1 hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26


Enclosure 3 PVNGS Unit 3 Core Operating Limits Report (COLR)
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6
24 hours 1.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26 PVNGS Unit 3 Core Operating Limits Report (COLR)
Revision 19
Revision 19


PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 Effective Date: October 29, 2009 Responsible Daes   bN Engineer                  apier,                       !Digitally     signed by Napier, JosephJ DNs o Napier, Joseph J(Z71881)
UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 Effective Date: October 29, 2009 Responsible Engineer Daes bN
J/       Reason: I am the author of this doc~ument&#xfd; (Z7 188                      )"*       Dte: 200&#xfd;1,0.27 16:14:33-07'00' Independent Reviewer             B odnar,                             fDigitealysigned  by Bodnar, Walter Date                             Da        lter                S  ,,s'z06432)
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PVNGS UNIT 3 CORE OPERATING LIMITS REPORT         Revision 19 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           8 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed         8 3.1.4 Moderator Temperature Coefficient (MTC)                       8 3.1.5 Control Element Assembly (CEA) Alignment                     8 3.1.7 Regulating CEA Insertion Limits                               8 3.1.8 Part Strength CEA Insertion Limits                           9 3.2.1 Linear Heat Rate (LHR)                                       9 3.2.3 Azimuthal Power Tilt (Tq)                                     9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR)                 9 3.2.5 Axial Shape Index (ASI)                                     10 3.3.12 Boron Dilution Alarm System (BDAS)                         10 3.9.1 Boron Concentration                                         10 Page 2 of 26
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 8
3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8
3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8
3.1.7 Regulating CEA Insertion Limits 8
3.1.8 Part Strength CEA Insertion Limits 9
3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT           Revision 19 List of Figures Description                                                                 Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature                     11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature                     12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2                         13 Figure 3.1.5-1 Core Power Limit After CEA Deviation                           14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power                       15 (COLSS in Service)
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power                       16 (COLSS Out of Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power         17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power                       18 (COLSS in Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both                   19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core                   20 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)
Operable)
Operable)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core                   21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 26
Page 3 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT           Revision 19 List of Tables Description                                                                 Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron               22 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               23 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               24 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               25 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               26 Dilution Detection as a Function of Operating Charging Pumps
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps
        'and Plant Operational Modes for Keff< 0.95 Page 4 of 26
'and Plant Operational Modes for Keff< 0.95 Page 4 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                     Revision 19 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 Unit 1 Technical Specifications.
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Unit 1 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 26
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 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                             Revision 19 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
Title                             Report No.       Rev       Date     Supl CE Method for Control Element Assembly                 CENPD-         N.A.     January     N.A.
Title Report No.
Ejection Analysis                                     0190-A                   1976 (13-NOO1-1301-01204-1)
Rev Date Supl CE Method for Control Element Assembly CENPD-N.A.
The ROCS and DIT Computer Codes for                   CENPD-         N.A.     April       N.A.
January N.A.
Nuclear Design                                         266-P-A                 1983 (13-N001-1900-01412-0)
Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1)
Modified Statistical Combination of                   CEN-           01-P-A   May         N.A.
The ROCS and DIT Computer Codes for CENPD-N.A.
Uncertainties                                         356(V)-P-A               1988 (13-NOO1 - 1303-01747-2)
April N.A.
System 8 0 TM Inlet Flow Distribution                 Enclosure       N.A. February     1-P (13-NOO1-1301-01228-0)                                 1-P to LD-               1993 82-054 Calculative Methods for the CE Large Break             CENPD-         N.A. March       4-P-A LOCA Evaluation Model for the Analysis of CE.         132                     2001 and W Designed NSSS (13-NOO1 - 1900-01192-3)
Nuclear Design 266-P-A 1983 (13-N001-1900-01412-0)
*Calculative Methods for the CE Small Break             CENPD-         N.A. April       2-P-A LOCA Evaluation Model                                 137-P                   1998 (13-NO1 - 1900-01185-3)
Modified Statistical Combination of CEN-01-P-A May N.A.
Fuel Rod Maximum Allowable Pressure                   CEN-372-       N.A. May         N.A.
Uncertainties 356(V)-P-A 1988 (13-NOO1 -1303-01747-2)
(13-NOO1-0201-00026-1)                                 P-A                     1990 Arizona Public Service Company PWR Reactor             NFM-005         N.A. January     N.A.
System 8 0 TM Inlet Flow Distribution Enclosure N.A.
Physics Methodology Using                                                       2006 CASMO-4/SIMULATE-3 (NFM-005)
February 1-P (13-NOO1-1301-01228-0) 1-P to LD-1993 82-054 Calculative Methods for the CE Large Break CENPD-N.A.
Technical Description Manual for the CENTS             CE-NPD         2       March       N.A.
March 4-P-A LOCA Evaluation Model for the Analysis of CE.
CodeVolume 1                                           282-P-A                 2005 (CENTS-TD MANUAL-VOL 1)                               Vols. 1 Technical Description Manual for the CENTS             CE-NPD         2       March       N.A.
132 2001 and W Designed NSSS (13-NOO1 -1900-01192-3)
Code Volume 2                                         282-P-A                 2005 (CENTS-TD MANUAL-VOL 2)                               Vols. 2 Page 6 of 26
* Calculative Methods for the CE Small Break CENPD-N.A.
April 2-P-A LOCA Evaluation Model 137-P 1998 (13-NO1 -1900-01185-3)
Fuel Rod Maximum Allowable Pressure CEN-372-N.A.
May N.A.
(13-NOO1-0201-00026-1)
P-A 1990 Arizona Public Service Company PWR Reactor NFM-005 N.A.
January N.A.
Physics Methodology Using 2006 CASMO-4/SIMULATE-3 (NFM-005)
Technical Description Manual for the CENTS CE-NPD 2
March N.A.
CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1)
Vols. 1 Technical Description Manual for the CENTS CE-NPD 2
March N.A.
Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2)
Vols. 2 Page 6 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                 Revision 19 Title                         Report No. Rev   Date     Suppi Technical Description Manual for the CENTS         CE-NPD     2     March       N.A.
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 Title Report No.
CodeVolume 3                                       282-P-A           2005 (CENTS-TD MANUAL-VOL 3)                             Vols. 3 Implementation of ZIRLOTM Cladding Material         CENPD-     0     November     N.A.
Rev Date Suppi Technical Description Manual for the CENTS CE-NPD 2
in CE Nuclear Power Fuel Assembly Designs           404-P-A           2001 (13-NOO -1900-01329-0)
March N.A.
HERMITE, A Multi-Dimensional Space-Time             CENPD-           July Kinetics Code for PWR Transients                   188-A             1976 (HERMITE-TOPICAL)
CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3)
TORC Code, A Computer Code for Determin-           CENPD-           April ing the Thermal Margin of a Reactor Core           161-P-A           1986 (NOO-1301-01202)
Vols. 3 Implementation of ZIRLOTM Cladding Material CENPD-0 November N.A.
CETOP-D Code Structures and Modeling Meth-         CEN-             September ods for San Onofre Nuclear Generating Station       160(S)-P         1981 Units 2 and 3, (N001-1301-01185)
in CE Nuclear Power Fuel Assembly Designs 404-P-A 2001 (13-NOO -1900-01329-0)
CPC Methodology Changes for the CPC                 CEN-3 10-   0     April Improvement Program, (NOO1-1303-02283)             P-A               1986 Loss; of Flow, C-E Methods for Loss of Flow         CENPD-     0     June Analysis,. (NOO1-1301-01203)                       183-A             1984 Methodology for Core Designs Containing             CENPD-     0     August Erbium Burnable Absorbers                           382-P-A           1993 (N001-0201-00035)
HERMITE, A Multi-Dimensional Space-Time CENPD-July Kinetics Code for PWR Transients 188-A 1976 (HERMITE-TOPICAL)
Verification of the Acceptability of a 1-Pin Bur-   CEN-386-   0     August nup Limit of 60 MWD/kgU for Combustion             P-A               1992 Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)
TORC Code, A Computer Code for Determin-CENPD-April ing the Thermal Margin of a Reactor Core 161-P-A 1986 (NOO-1301-01202)
CETOP-D Code Structures and Modeling Meth-CEN-September ods for San Onofre Nuclear Generating Station 160(S)-P 1981 Units 2 and 3, (N001-1301-01185)
CPC Methodology Changes for the CPC CEN-3 10-0 April Improvement Program, (NOO1-1303-02283)
P-A 1986 Loss; of Flow, C-E Methods for Loss of Flow CENPD-0 June Analysis,. (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Containing CENPD-0 August Erbium Burnable Absorbers 382-P-A 1993 (N001-0201-00035)
Verification of the Acceptability of a 1-Pin Bur-CEN-386-0 August nup Limit of 60 MWD/kgU for Combustion P-A 1992 Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)
Page 7 of 26
Page 7 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                           Revision 19 The cycle-specific operating limits for the specifications listed are presented below.
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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.
3.1.1 - 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.
3.1.2 - 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.
Line 642: Line 909:
The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.
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.
3.1.5 - 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 limitsI 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 withdrawn 3 while in Modes 1 and 2 (except whileperforming SR 3.1.5.3).
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 limitsI 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 withdrawn3 while in Modes 1 and 2 (except whileperforming SR 3.1.5.3).
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, and4) 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 hours.
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, and4) 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 hours.
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:
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.
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
b)' Regulating Gro up 5 position is maintained at least 10 inches lower than Page 8 of 26
b)' Regulating Gro up 5 position is maintained at least 10 inches lower than Page 8 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                           Revision 19 Regulating Group 4 position.
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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).
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   - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 Fully withdrawn - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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)
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit of 13.1 kW/ft shall be maintained.
The linear heat rate limit of 13.1 kW/ft shall be maintained.
Line 661: Line 928:
Page 9 of 26
Page 9 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                           Revision 19 3.2.5 - Axial Shape Index (ASI)
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
COLSS OPERABLE
COLSS OPERABLE
        -0.18 < ASI < 0.17 for power > 50%
-0.18 < ASI < 0.17 for power > 50%
        -0.28 < ASI < 0.17 for power >20% and < 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
COLSS OUT OF SERVICE (CPC)
COLSS OUT OF SERVICE (CPC)
        -0.10 < ASI < 0.10 for power >20%
-0.10 < ASI < 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
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.
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.
Line 673: Line 940:
Page 10 of 26
Page 10 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                 Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7
6   . . . . . . . --
6 5
                                                                                        . . . . . (. 5. 0 . . .    .. .    ...
03 2
5
0
* REGION OF(00)
( 5 0 REGION OF(00)
ACCEPTABLE-OPERATION
ACCEPTABLE-OPERATION
                                            .         ...........*....... ................I........   ........ ...........
~REGION :OF
03
*UNACCEPTABLE
                                                                          -                  ~REGION :OF
*OPERATION (350,1:.0)
                                                                                            *UNACCEPTABLE 2
...........*.......................I...........................
                                                                                              *OPERATION                          -
0 100 200 300 400 COLD LEG TEMPERATURE (fF) 500 600 Page 11 of 26
(350,1:.0) 0 0                100                   200               300                     400                   500              600 COLD LEG TEMPERATURE (fF)
Page 11 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                             Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7
6 5
REGION OF ACCEPTABLE
-OPERATION..I_.
2 z
0 4
3 2
0 (350,4.0)
REGION OF UNACCEPTABI OPERATION I...
(500,6.5):
(500,6.5):
6 REGION OF ACCEPTABLE 5        -OPERATION..I_.
LE 0
2 4
100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26
(350,4.0) z 0 3 REGION OF UNACCEPTABILE 2
OPERATION
                                      ------            I. . .
0  .............................                        ...........
0        100       200       300               400                   500              600 COLD LEG TEMPERATURE ('F)
Page 12 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                                                                 Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.L                                                                                       .........................
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0
                                    ''"."          0....                                            :........
[.-
                                        - i*   (                                                     ::                      ......    .......                      .00O%,Q
U L-.
(..
W 0
i.------------
[.-
                                .... ... i .......... ..........                       .....                        ...........    ......-        ------
0 0.5 0.0
0.0 i                                                               (100%.-0.2
-0.5
    -0.5
-1.0
    -1.0 0
-1.5
[.-        . .. ........ ----        .............----
-2.0
                                                    ---    ...... ............. &#xfd;MT-C-AR EA--O F ...................................................
-2.5
    -1.5 ACCEPTABLE W
-3.0 0....  
U
- ( i*
    -2.0 L-.
(..  
    -2.5 0
.00O%,Q
[.-        .. . . . . . . . . . . . . . . ........ ... . -            .-.-.--  .....
: i........
                                                                                    --  i-....
i....................
                                                                                      ..- .... i---- ..................-.-------..
i (100%.-0.2
    -3.0 0
................... &#xfd;M T -C -A R E A --O F...................................................
    -3.5                                             (0100%,4.2
ACCEPTABLE
    -4.0
............................ i....
              --    .        . ..... . I . . . . . i...                . .---
i (0100%,4.2 I....
    .a 5
i...
    -45 0               10               20                     30                   40         50                   60         70             80             90           100 CORE POWER LEVEL
L
(%OF RATED THERMAL POWER)
-3.5
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit ........
-4.0
.a 5
-45 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 13 of 26
Page 13 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                               Revision 19 I
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 I
FIGURE 3.1.5- 1 CORE POWER REDUCTION AFTER CEA DEVIATION*
FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
A    I     .. . r..
I r..
rn
rn  
                    .. .-r-r-T-rrr T.........           - 1 1 T r...... Ir[n[rs 20 1111rrrIr 15                                                                           15 0m t0                                                                           t0 5                                                                           5 0
-r-r-T-rrr T.........
0           10             20         30     40       50             60 TIME AFTER DEVIATION, MINUTES
1111rrrIr 1
1 T r Ir[n[rs 20 A
15 0m 15 t0 t0 5
5 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.
* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
Page 14 of 26
Page 14 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                     Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) m 1.0                                                  I   I       1         I         1     I     I         I         I       I 0.9 +-                                            -(SEE FOOaTNOT-E-IN -SE-CTION3&#xfd;I-7-.................
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 m
0.9 +-
0.8 -
0.7 0.6 w
H 0.5 0
0.4 U
0.3 0.2 0.1 A )
0 (n
:0 0
Z 0.
I I
1 I
1 I
I I
I I
-(SEE FOOaTNOT-E-IN -SE-CTION3&#xfd;I-7 -.................
FOR APPLICABILITY FOLLOWING:
FOR APPLICABILITY FOLLOWING:
                                                                    .A_ C.T . ._
A REACTOR CUTBACK)
A REACTOR             CUTBACK)                     .................--
.A _ C.T.._
A. . ).................... ----      ------
A.. )....................
0.8  -
GRP4,-POS-= (-I2.5-,x-FRA-C. PWR) -+- 25.5---
0.7                                                GRP4,-POS-= (-I2.5-,x-FRA-C. PWR) -+-25.5---
GRP 5 POS = (172.5 x FRAC. PWR) - 64.5 L--
GRP 5 POS = (172.5 x FRAC. PWR) - 64.5 0.6 w                              0 H                                          Z 0.5 0 (n 0
1 I
0.4 U                  :0 0.
I I
L--
I 1
0.3 0.2 0.1 A )        I I     I       I       11    I GROUP I I     GROUP5 i I     I       I           i I GROUP3 I I                     I I             I     I       I         I I         I FW* 120 90       60       30       0   FW* 120       90     60       30         0     FW* 120         90       60       30     0 GROUP4                                         GROUP2 Ft*10                 t0 6+0 3t             Ft         I1t0 1 0 6+0           30 CEA POSITION (INCHES WITHDRAWN)
I GROUP5 GROUP3 GROUP I I
i I
I I
i I I I
I I I
I I
I I I
FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP4 GROUP2 Ft*
10 t0 6+0 3t Ft I1t0 1 0 6+0 30 CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 15 of 26
Page 15 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                                                     Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9                                             % ~i.~. .~.. . .~. ..---. .---          .? .--- . .. --------I............ ....... :........ :......
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 0.7 2
0.8                                              (SEE FOOTNOTE-IN-SECTION 3-1-....
0.6 0.5 0
0.4 0.3 0.2 0.1 An t
0.
0zV 0
% ~ ~ ~ ~ ---
: i.............?.... I................... :........ :......
(SEE FOOTNOTE-IN-SECTION 3-1-....
FOR APPIICABILITY FOLLOWING
FOR APPIICABILITY FOLLOWING
                                                              .... E...AC.T..O.R...C....-BAK) -                                               .............-
.... E...AC.T..O.R...C....-BAK) -
0.7 2
GRP4POS-= (250.9 y FRAC; PWR-+-9.82-GRP 5 POS (250.9 k FRAC. PWR) - 80.18 IHN*HHB*
0 0.6                                            ---GRP4POS-= (250.9 y FRAC; PWR-+-9.82-GRP 5 POS                         (250.9 k FRAC. PWR) - 80.18
I I
        -.-        0.              ------
I I
* 0.5 0
I V
0.4
GROUP5 GROUP3 GROUP 1 I I I
          . 0.3 0zV 0.2        IHN*HHB*
I I
0.1                                                            ....
I I
Ant          I     I I         I       I V
I I
GROUP3                                                               GROUP 1 I GROUP5 I I I         I         I       I   I       I             I       I           I             I         I             I         I             I         I FW* 120 90     60 30 0 FW* 120 90                             60         30 0 FW* 120 90                                             60           30           0 GROUP 4                                               GROUP 2 Ft It10          t9 60 3+0 Ft* 100 6+0 3 CEA POSITION (INCHES WITHDRAWN)
I I
I I
I I
I I
I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0
GROUP 4 GROUP 2 Ft I t10 t9 60 3+0 Ft 100 6+0 3 CEA POSITION (INCHES WITHDRAWN)
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
*Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
Page 16 of 26
Page 16 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                                               Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 20 .0 10.0     . . . .. .... :.... . . . . . .. -------        .--  .--- . . --
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 2 0.0.....
20.0 30.0
10.0 20.0 30.0 40.0 S
*<      40.0 S   50.0
50.0 m
: 30.        ------      -------------- --------                                                                - ------                        .....
60.0 o
m      60.0 o                                                                                         TRANSIE*NT INSERTION LIMIT (75.0::INCHES 10 0.0      --.  ..-----
TRANSIE*NT INSERTION LIMIT (75.0::INCHES
                                      ....          . . .. i........................
: 30.
z 5
5 90.0............
90.0     ............                                                 ........                    OPERATION.......                               .
OPERATION........
ZO                       ;UNACCEPTABLE :
ZO  
* RESTRICTED, Z  u 3710.0
;UNACCEPTABLE RESTRICTED, 1 0 0.0
          ~0 ..      ......b*......
.... i........................
                  -..-----...-  PiT          .......i.
z Z
                                    ............     O --      ......i............
710.0 I
                                                      ---..............  -- -I .........:-.................
1 LONG TERM STEADY STATE INSERTIONTLIMITS! (112.5 INCHES 130.0............
1                 LONG TERM STEADY STATE INSERTIONTLIMITS! (112.5 INCHES 130.0. ------------      -              ......................... -                  -------------........
u 3 ~........
14o.0 -.-...-                                    .. . ..--
0
OPERATION ACCEPTABLE 150.0      ....       I ...             .       .     ....           ....               I
*.............i.......i............
                                                                                              .............            .  ..... I. ....                .......
b PiT O --
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 17 of 26
OPERATION ACCEPTABLE 1 4 o.0 -....-
150.0 I...
I  
..... I.....
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 17 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                         Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0   I-                                 ..REGION -OF...............
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 I-F-
UNACCEPTABLE OPERATION F-10.0 F-N              -.  ;..
F-N 10.0 REGION OF
5.0                                                                       T             I REGION OF &#xfd;LCCEPTABLE OPERATION
..REGION -OF...............
                                                                                    -  . I . .
UNACCEPTABLE OPERATION 5.0 T
0.0 ................
I
20 .0       30.0       40.0       50.0           60.0             70.0           80.0   90.0 100.0 CORE POWER LEVEL
&#xfd;LCCEPTABLE OPERATION I.
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)
(% OF RATED THERMAL POWER)
Page 18 of 26
Page 18 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                     Revision 19 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95,20) 20  . .........................
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE Revision 19 IN ANY OPERABLE CPC CHANNEL 25 20 (95,20) z 0
z 0
0 z
15        ...................
15 101-
0 z   101-5                                                            ...................
:(80,5)
:(80,5)
(70,0);
(70,0);
0 50                 60               70         80       90                   100 CORE POWER LEVEL
5 0
50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
(% OF RATED THERMAL POWER)
Page 19 of 26
Page 19 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                                       Revision 19 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5   ri-w-...............,-iY~i u................................                     U l~   l l   U m l l...       .... 1'IUYll rrri999II ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 ri-w-...............,-iY~i u................................
:                i:
U l~
2.3              ~
l l
                    -~     ------------------    I....,----------.....
U m l l...
(-6.1,2.28) la 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
1'IUY ll rrri999II 2.3 UD u
UD                                                    AT LEAST 1 CEAC OPERABLE IN 2.1                  .................
2.2 2.1 ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL i:
            -..---.-...-                            EACH OPERABLEECPC CIIANNEL:".
(-6.1,2.28)
u                                                                                                    *
-~ ~
(0.0.,2.00) 2.0 93... .. . .. .I. *&deg;&deg;
I....,----------.....
(-01,              ..I . ... . . . . I . .UNACCEPT'ABLE
la ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
                                                                              . . . . . . . . . . . . I . . . . . . . I . . .. . . . I . . .   . . .
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLEECPC CIIANNEL:".
                  .. -.         --------------------------------..       .O PE RAT ION ..... ..................................                      ..
(0.0.,2.00)
1.9 18
(-01, 93  
      -0.20         -0.15                 -0.10                 -0.05                 0.00       0.05             0.10             0.15             0.20 CORE AVERAGE ASI Page 20 of 26
*&deg;&deg; UNACCEPT'ABLE
.O P E R A T IO N.......................................
I...
....I.
... I..
.. I...
. I....
I 2.0 1.9 18
-0.20  
-0.15  
-0.10  
-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                                                                                                                         Revision 19 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   ....       ...      r.        .    .. ...........              ......... .........                        .. ....        ....                r ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 . .................................. --       ---  ----    ---  O----  E---  ---- B---    -C   --*-----------..--...                ---...        .... . ...
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Re 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  
IN ANY OPERABLE CPC CHANNEL 34                                                     (Ot,341)(01.1,3.4....
... r r
3 .4   .... .. ........ .............. .... ..              - -------.                          .-- ................. ] ............. --...            ............. .
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5................................... --
U                                         (-0.1.3.27) 3 .2     ...................................    .............---.................  ..... ...................................................          ................ .
O E B C
UNACCEPTABLE OPERATION 3 .0         .. ... . I                 ........                i
* IN ANY OPERABLE CPC CHANNEL 34 (Ot,341)(01.1,3.4....
                                                            .........                   i i           ....... I     ..    ......... I . .    .    .
3.4  
      -0.20             -0.15               -0.10             -0.05                 0.00                 0.05                 0.10                 0.15               0.20 CORE AVERAGE ASI Page 21 of 26
................. ]............. --...
U
(-0.1.3.27) 3.2 UNACCEPTABLE OPERATION 3.0  
...... I i
i
.........i I  
......... I.
-0.20  
-0.15  
-0.10  
-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI vision 19 Page 21 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                 Revision 19 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                 Number of Operating Charging Pumps MODE                     0               1         2           3 3                     12 hours       0.5 hours   ONA           ONA 4 not on SCS         12 hours       0.5 hours   ONA           ONA 5 not on SCS           8 hours       0.5 hours   ONA           ONA 4 & 5 on SCS           ONA           ONA       ONA           ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                 Revision 19 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 &#x17d; Keff > 0.97 OPERATIONAL                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours         1 hour     0.5 hours     ONA 4 not on SCS         12 hours       1.5 hours   0.5 hours     ONA 5 not on SCS           8 hours       1.5 hours   0.5 hours     ONA 4 & 5 on SCS           8 hours       0.5 hours     ONA         ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 &#x17d; Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                 Revision 19 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                 Number of Operating Charging Pumps MODE                     0               1         2           3 3                     12 hours       2.5 hours   1 hour       ONA 4 not on SCS         12 hours       2.5 hours   1 hour     0.5 hours 5 not on SCS           8 hours       2.5 hours   1 hour     0.5 hours 4 & 5 on SCS           8 hours         1 hour     ONA           ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                   Revision 19 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                   Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours         3 hours     1 hour     0.5 hours 4 not on SCS         12 hours       3.5 hours   1.5 hours   0.75 hours 5 not on SCS           8 hours       3.5 hours   1.5 hours   0.75 hours 4 & 5 on SCS           8 hours       1.5 hours   0.5 hours     ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 3 hours 1 hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26


PVNGS UNIT 3 CORE OPERATING LIMITS REPORT                   Revision 19 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                 Number of Operating Charging Pumps MODE                     0               1           2           3 3                     12 hours       4 hours     1.5 hours     1 hour 4 not on SCS         12 hours       4.5 hours     2 hours     1 hour 5 not on SCS           8 hours       4.5 hours     2 hours     1 hour 4 & 5 on SCS           8 hours       2 hours   0.75 hours     ONA 6                     24 hours       1.5 hours     ONA         ONA Notes:   SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26}}
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 0
1 2
3 3
12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6
24 hours 1.5 hours ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26}}

Latest revision as of 09:05, 14 January 2025

Submittal of Revised Core Operating Limits Reports (Colrs)
ML093290107
Person / Time
Site: Palo Verde  
Issue date: 11/17/2009
From: Weber T
Arizona Public Service Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
102-06095-TNW/REB/CJS
Download: ML093290107 (82)


Text

Technical Specification 5.6.5d Thomas N Weber Mail Station 7636 Palo Verde Nuclear Department Leader, Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-06095-TNW/REB/CJS November 17, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Revised Core Operating Limits Reports (COLRs), Units 1, 2 and 3 Pursuant to PVNGS Technical Specification, Section 5.6.5, enclosed are the revised Core Operating Limits Reports (COLRs). Unit 1 - Revision 20, Unit 2 - Revision 16, and Unit 3 - Revision 19, were made effective October 29, 2009. These revisions include changes resulting from License Amendment No. 174, dated August 26, 2009.

By copy of this letter and the enclosures, these COLR revisions are being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector. This letter does not make any commitments to the NRC. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.

Sincerely, TNW/RAS/CJS/gat -PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 20 -PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 16 -PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 19 cc:

E. E. Collins Jr.

NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway " Comanche Peak " Diablo Canyon " Palo Verde " San Onofre " South Texas " Wolf Creek/(

(

PVNGS Unit I Core Operating Limits Report (COLR)

Revision 20

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 Effective October 29, 2009 Responsible Engineer C Digitally signed by Napier,

Napier, 1 Joseph J(Z71881)

Date DN: cn=Napier, Joseph J I(4I Z71881)

Joseph J ýl Reason: I am the author of tf

-this' 86bZment (Z7188A)V.'

Date 2009.10.27 16:17:19 n e Digitally signed by Bodnar, Independent Reviewer

Bodnar, d1 Walter S(Z06432)

Date DN: cn=Bodnar, Walter DateW alter S (zo dnart6er2S W Reason: I have reviewed

-this document (Z06432ý )

Date: 2009.10.27 16:22:54 0-7'00o

=

  • ". Digitally signed by Rowland, Responsible Section Leader Rowland James W(Zbyown,

" DN: n=Rowland, James W Date I /(Z80533)

James vv /IýReason:

am approving this document as temporary R*"Reioad-Anrlysis SL (Z8053 X Date: 20096" 10.27 17:04:16

-0700' Page 1 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 8

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8

3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8

3.1.7 Regulating CEA Insertion Limits 8

3.1.8 Part Strength CEA Insertion Limits 9

3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 List of Figures Description Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Unit 1 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 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents::

Title Report No.

Rev Date Sump CE Method for Control Element Assembly CENPD-N.A.

January N.A.

Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)

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

April N.A.

Nuclear Design 266-P-A 1983 (13-N001-1900-01412-0)

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

Uncertainties 356(V)-P-A 1988 (13-N001 -1303-01747-2)

System 8 0 TM Inlet Flow Distribution Enclosure N.A.

February 1-P (13-N001 -1301-01228-0) 1 -P to LD-1993 82-054 Calculative Methods for the CE Large Break CENPD-N.A.

March 4-P-A LOCA Evaluation Model for the Analysis of CE 132 2001 and W Designed NSSS (13-NOO1-1900-01192-3)

Calculative Methods for the CE Small Break CENPD-N.A.

April 2-P-A LOCA Evaluation Model 137-P 1998 (13-NOO -1900-01185-3)

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

May N.A.

(1 3-NOO 1-0201-00026-1)

P-A 1990 Arizona Public Service Company PWR Reactor NFM-005 N.A.

January N.A.

Physics Methodology Using 2006 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CENTS CE-NPD 2

March N.A.

CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1)

Vols. 1 Technical Description Manual for the CENTS CE-NPD 2

March N.A.

Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2)

Vols. 2 Page 6 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 Title Report No.

Rev Date Suppi Technical Description Manual for the CENTS CE-NPD 2

March N.A.

CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3)

Vols. 3 Implementation of ZIRLOTM Cladding Material CENPD-0 November N.A.

in CE Nuclear Power Fuel Assembly Designs 404-P-A 2001 (13-NOO1 -1900-01329-0)

HERMITE, A Multi-Dimensional Space-Time CENPD-July Kinetics Code for PWR Transients 188-A 1976 (HERMITE-TOPICAL)

TORC Code, A Computer Code for Determin-CENPD-April ing the Thermal Margin of a Reactor Core 161-P-A 1986 (NOO1-1301-01202)

CETOP-D Code Structures and Modeling Meth-CEN-September ods for San Onofre Nuclear Generating Station 160(S)-P 1981 Units 2 and 3, (NOO1-1301-01185)

CPC Methodology Changes for the CPC CEN-3 10-0 April Improvement Program, (N001-1303-02283)

P-A 1986 Loss of Flow, C-E Methods for Loss of Flow CENPD-0 June Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Containing CENPD-0 August Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)

Verification of the Acceptability of a 1-Pin Bur-CEN-386-0 August nup Limit of 60 MWD/kgU for Combustion P-A 1992 Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)

Page 7 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 limitsi shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).

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.

b) Regulating Group 5 position is maintained at least 10 inches lower than Page 8 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 9 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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*< 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 _Ž 3000 ppm.

Page 10 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7

......... (50050) 5....................-

REGION OF ACCEPTABLE OPERATION z

z Z* 3 REGION !OF UNACCEPTABLE OPERATION 0

0 100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 11 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 I

FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7

6 5

. 4 z

03 2

0 I

REGION OF ACCEPTABLE

............... OPERATION--:-

+/-

(500,6.5)i (350,4.0)

REGION OF UNACCEPTABLE I.....................

OPERATION

. l l

l l

l l

l m

l l

l l

l

....l l l ll..

..l 0

100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5

-1.0.........-

o z

W 0.

U 0

F-0 0

-1.5

-2.0 m

I

..... I....

I.

I

... I.

."!........ i.....

(50%,0.0)

(100%,-0.2

-CAREA OF..................................................

ACCEPTABLE

OPERATION

............... I'............. ---............. I.............. I..........................................

i....

i..

I.

i..

-2.5

-3.0

-3.5

-4.0 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 13 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 1

FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

tevision 20 ASt 20 15 z

0 16 5100% to

>80% RTP 12 12

580% to

>70% RTP 8

8

-70% to

>45% RTP

-<45% RTP 15 10 5

I 10 5

-i i

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.

Page 14 of 26 I

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 0.9 -

0.8 -

0.7 0.6 05 0T.

0 L

0.3 0.2 0!

Uz.

-(SEE FOOTNOTE IN SECTION 31.;7.......-.-

FOR APPLICABILITY FOLLOWING

-GRP 4-POS-= (-12-.5-xFRAC.PWR)-+-25-5--

GRP 5 POS = (172.5:'x FRAC. PWR) - 64.5 I

........ I 0.1 -

I O0 GROUP5 GROUP3 GROUP I I

I I

I I

I I

I I

I I

I I

I I

I I

I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP 4 GROUP 2 F)ýC*

1 P0 OTI 34o FIN 1C0 6W0 31DRW CEA POSITION (INCHES WITHDRAWN)

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

Page 15 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 1 0.8 0.7 0.6 05 0.4 0

U 0.3 0.2 0.1

('n

...........i....!......

I --------

J....... i.....

.i............ *

.(SEE FOOTNOTE-iN SEC-TION-3;[;7.........7 FOR APPIACABILITY FOLLOWING A: REACTOR CUTBACK) 0


GRP-4POS-=(-250.9-X-FRAC.-PWR" +-9.82---

GRP 'PWOS = (250.9 i FRAC. PWR)- 80.18

...... i.....

z zz

.z,........

.I...........

£

'J, GROUP5 GROUP3 GROUP I I

I I

I I I I

I I

I I-I I

I I

I I I FW* 120 90 60 30 0OFW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP 4 GROUP 2 F

X%*

10 0

3 g Ft It L0O 6+0 t

CEA POSITION (INCHES WITHDRAWN)

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

Page 16 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 20 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 z

z r-

,.nF-0Z u) z

!TRANSIENT INSERTION LIMIT (75.0:INCHES) 80.0 90.0 IO............

OT..........I UNACCEPTABLE L......:.............

......... OPERATION..................

RESTRICTED I

I I

I 100.0 110.0 120.0 130.0 140.0 150.0 1.(

.6 LONG TERM STEADY STATE INSERTION:LIMITSI (112.5 INCHES)

.............. i..............................

I ------------

OPERATION ACCEPTABLE I..

I.

I I-..

J 1..

I...

I.

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 17 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 F-0

z-10.0 REGION OF

-R E G I O N O F --------------

UNACCEPTABLE OPERATION 5.0 WLCEPTABLE OPERATION 0.u -

20.0 30.0 40.0 50.0 60.0 70.0 CORE POWER LEVEL 80.0 90.0 100.0

(% OF RATED THERMAL POWER)

Page 18 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 20 25 20......

0 E0 15 I-

/...

101-5 0

(80,5)

(70,0):

11 I

I I

Illlllll 50 60 70 80 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 90 100 Page 19 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 2.3 I

z 0

2.2 2.1

(-0.1,2.28)

(... 1193)............

,,°,,,,l

,o.

..l,,

l...

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

(0.1,2.3 ACCEPT~ABLE OPERATION POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN

....EACH OPER-ABILE-CPC CHtANNELA'-......

(0.05,2.00)

................. I.............................. * '........

"*0. 12.01 UNACCEPTABLE

...................... O P E R A T IO N....................................

......... I......... I........

I......... !.

8):

...i..............

2.0 1.9 1.8 I

i fl i i i fl i 1 I i

  • i i..... I i i I..... I l i I

-0.20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 IIgDHllll Illl 3.5 I 3.4 z

u C..)

3.3 ACCEPTABLE :OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE B:E IN ANY OPERABLE CPC CHANNEL

(-0.i.3.27)

UNACCEPTABLE OPERATION

( 1, 3.4 1) l'

'r i

3.2 P--

3.1 3.0 1.

1..

.. I.

I..

I..

......... m.........

. 1. 1.....

-0.20

-0.15

-0.10

-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 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 Page 22 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Ž Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 23 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Ž Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 24 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 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 Page 25 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 20 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 Number of Operating Charging Pumps MODE 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 Page 26 of 26 PVNGS Unit 2 Core Operating Limits Report (COLR)

Revision 16

Digitally signed by O'Connor, Tina O'Connor,

, M(Z06952)

SODN-cn=O'Connor, Tina M Ti na M ~

J (Z06952) n6ason:oi2 attest to the accuracy

[7Cic(*

rQ

,/-

nd integrity of this document (Z0695

'2 Date: 2009.10.28 05:57:33 -07'00' PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 Effective 10/29/2009 Responsible Engineer lDigitally signed by Foster, Foste r,

  • Glenn A(Z35831)

Date DN: cn=Foster, Glenn A Glenn. A

,(Z35831)

G le A'%

f"Rýeason: I am the author of this

/--,m,,*

  • e* J

,* ),,ý_document, Date: 2009.10.27 16:10:17 (Z.

3 5 83

-07'00' Independent Reviewer Digitally signed by Delorenzi,; Delorenzi, Mark J(Z01931)

Date DION:

cn=Delorenzi, Mark J M

rk /

f'7.*(ZO1931)

Mark J Reason: I have reviewed

, thl*; ddument 7

Date: 2009.10.27 16:34:06

.*,am 3l# m

-07'00' Digitally signed by Rowland, Responsible Section Leader Row a,

ýk j\\i James W(Z80533)

Ro la Dv**

,)

N: cn=Rowland, James W Date I

A

  • ,(Z80533)

Dta O.I I VV/ ;Reason: I am approving this James V,

1 documentas temporary

/-.*Rload *A*nlysis SL (Z8053,.

Date: 2009610.27 16:50:38

/*/

-0700' Page 1 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 8

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8

3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8

3.1.7 Regulating CEA Insertion Limits 8

3.1.8 Part Strength CEA Insertion Limits 9

3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Unit 2 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 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

Title Report No.

Rev N.A.

Date January 1976

1) CE Method for Control Element Assem-bly Ejection Analysis (NOO-1301-01204-1)
2) The ROCS and DIT Computer Codes for Nuclear Design (NOO1-1900-01412-0)
3) Modified Statistical Combination of Uncertainties (NOO1-1303-01747-2)
4) System 80 TM Inlet Flow Distribution (NOO1-1301-01228-0)
5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (NOOl-1900-01192-3)
6) Calculative Methods for the CE Small Break LOCA Evaluation Model (NOO1-1900-01185-3)
7) Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026-1)
8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
9) Technical Description Manual for the CENTS CodeVolume 1 (CENTS-TD MANUAL-VOL 1)
10) Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
11) Technical Description Manual for the CENTS CodeVolume 3 (CENTS-TD MANUAL-VOL 3)

CENPD-0190-A CENPD-266-P-A SuWpl ement N.A.

N.A.

N.A.

April 1983 CEN-356(V)-P-A Enclosure 1-P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A 01-P-A (ARI)

N.A.

May 1988 (April 1996)

February 1993 N.A.

1-P N.A.

March 2001 4-P-A N.A.

April 1998 2-P-A N.A.

May 1990 N.A.

NFM-005 N.A.

January 2006 N.A.

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

March 2005 2

March 2005 2

March 2005 N.A.

N.A.

N.A.

Page 6 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 Title

12) Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (NO01-1900-01329-0)
13) HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients
14) TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core.
15) CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOO 1-1301-01185)
16) CPC Methodology Changes for the CPC Improvement Program (NOO1-1303-02283)
17) Loss of Flow, C-E Methods for Loss of Flow Analysis (NOO1-1301-01203)
18) Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (NOO 1-0201-00035)
19) Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (NO0 1-0201-00042)

Report No.

CENPD-404-P-A CENPD-188-A CENPD-161-P-A Rev Date Sumel ement 0

November 2001 July 1976 April 1986 N.A.

I CEN-160(S)-P September 1981 April 1986 CEN-3 10-P-A CENPD-183-A CENPD-382-P-A CEN-386-P-A 0

0 0

0 June 1984 I

August 1993 August 1992 Page 7 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).

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.

b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

Page 8 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 9 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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*< 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 10 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7..

REGION OF ACCEPTABLE/

OPERATION z

z REGIONOF UNACCEPTABLE

........ i:

OPERATION (350,1::.0) o 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F)

Page 11 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7I (51 6

5 4

z 03 2

0 REGION OF ACCEPTABLE-

............... O P E l A TIA o N...,..--..--

g4 Z

Z 0

3

[-,

(350,4.0)

'REGION OF UNACCEPTABLE T I OPERATION

.l.ll.l.liL1L i.1 J.

...L..

0 100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2 0.5 0.0

-0.5

-1.

z o

-1.5 0

U

-2.0 1

-2.5

-3.0 0

-3.5

-4.0

-4.5

"%0.

'ý '...

  • .* ' " '..'..... i...

(100%,-o.

M TC..............

A R E A O F-

-ACCEPTABLE OPEPATION I,--

-0%,-3.4)

.... i....

I I I m l 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 13 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.5-1 CORE POX 92 15 z0 r-ug~

0-VER REDUCTION AFTER 16 -100% to

>80% RTP 1

12.

80% to

>70% RTP 9----

7-----

1o CEA DEVIATION*

20 15 10 5

8

-70% to

>45% RTP 6

5

!ý45% RTP 0

I I

1.1......I.......................................

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

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

I Page 14 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)

, r, I.U 0.9 0.8 0.7 R

0.6 0.5 0

z 0.4 0

0.3 0.2 0.1 00l (SEE FOO.TNOT-E IN SEACTI N -31.7---------

FOR XPPLICAýBILi'1Y FOLLOWIMNG::

A REACTOR CUTBACK)

-RP-4-POS=-(72-5--xFRA*C.-PWR)

+-25..

GRP 5 POS = (*72.5::x FRAC. PWR -64.5

z.....

J1 e*

  • m
e J

GROUP 5 GROUP 3 GROUP I I

I I

I I I I

I I

I I

I I

I I I

I I

FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP 4 GROUP 2 Ft 1A0 9P0 6OS 3ITO FN W*ITHD 6A 0

3+0 CEA POSITION (INCHES WITHDRAWN)

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

Page 15 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 0.7 2

0.6 0.5 0

z 0.4 0p U.J

£ 0.3 0.2 0.1 nf

.(SEE-FOOTNO-T-EIN SECTInON 3i7.1-.7 FOR APPLICABILITY FOLLOWI'NG A: REACTOR CUTBACK)

PGRP4POS-=(250.9-jcFRA-C.PWRt+-9.82-aGRP 5,P08 (250.9 i FRAC. PWR) -80.18 i

ii i

...... i................

.......................................... i.......i.......*........ *.....

.I-I P:

. m - --:...... -- --

i GROUP5 GROUP 3 GROUP 1 I

I I

I I

I I I I

I I

I I

I I I

I I

FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP 4 GROUP 2 Ft*

A POSII 6N0 N3Co H FWIt HD 6+A CEA POSITION (INCHES WITHDRAWN)

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

Page 16 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 40.0 50.0 rti 60.0 Z

70.0 0

o 80.0 u

90.0 z

100.0 110.0 120.0 130.0 140.0 1*O 0

  • TRANSIEN T INSERTION, LIMIIT (75.0 INCHES}

E..............

RA.TIO.N.

O ---------

P-E-RATIO N........................

UNACCEPTABLE RESTRICTED LONG TERM STEADY STATE INSERTIONLIMITSEI (112.5 INCHESM P

............ - -I L...........

b A I O N

.....i.......i...

.......... O P R T O ---

UN RTINACCEPTABLE kSRCE

.......................... ::..........i.......................

..I

l....

l..

i..

I

.. I ---

  • VmV 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 17 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 e-0 F-10.0

................... R E G IO N O F.............---

UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPEl I I 1

I 1 5.0 RATION

(~ fl I 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 18 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 16 25 20 -

0 z

0 z

15 10 -

( 70,0)

(95,20)

(8 0 )..........................................

5 0

I 1

I 50 60 70 80 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 90 100 Page 19 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 2.3 i-I-Iwl z

u 2.2 2.1 S.....

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (006,2 38)(01,3)

(-0.1 2.28)

I ACCEPTABLE OPERATION I

ll POWER AT OR ABOVE 9W%

AT LEAST 1 CEAC OPERABLE IN

-EACH OPERABLE CPC-CIIANNEL" S((.0,0,2.00)

(119 3)

° UNACCEPTARLE

............ O PE R A T IO N ---..................

IV l ll l

I l

l ~ l (0-1,2.38)::

ýG. -I 1-00y..............

2.0 1.9 1.8 L

-0.2.0

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 3.5 3.4 0.)

3.3 ACCEPTABLE ::OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL r (00(3 4-1) --

0.--------41)

(-0.03.27)

UNACCEPTABýLE OPERATION

.I 0.1,3.41)::

3.2 3.1 3.0

.......1.1...................

-0.20

-0.15

-0.10

-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Number of Operating Charging Pumps MODE 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 Page 22 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Ž Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 23 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Ž Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 24 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Ž Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 25 of 26

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 16 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 Number of Operating Charging Pumps MODE 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 Page 26 of 26 PVNGS Unit 3 Core Operating Limits Report (COLR)

Revision 19

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 Effective Date: October 29, 2009 Responsible Engineer Daes bN

apier,

!Digitally signed by Napier, JosephJ DNs o Napier, Joseph J(Z71881)

J/

Reason: I am the author of this doc~ument ý (Z7 18 8

)"*

Dte: 200ý1,0.27 16:14:33-07'00' Independent Reviewer B odnar, f Digitealy signed by Bodnar, Walter Date

,,s'z06432)

Da lter S

(:...

Bodnar, Walter S(Z06432)

W a lter Reason: I have reviewed this

-document"-"

(Z 6432)*

Date: 2009:10.27 16:20:09-0700' Responsible Section Leader A w lan d

,0Dgoal,.

signed by Rowland, James

  • *v.

]

  • W(ZS0533)

Date W

\\DN: cn=Rowland, James W Jam es

.s(Z0533) iJ~rr]

VV/f/Re.....

I am approving this

  1. /,dgcurntV as temporary Reload n*ys I sD 1

(Z 80533 Date: 2009. 1'0.27 17:00:05 -0700O Page 1 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 8

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8

3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8

3.1.7 Regulating CEA Insertion Limits 8

3.1.8 Part Strength CEA Insertion Limits 9

3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 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 23 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 24 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 25 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 26 Dilution Detection as a Function of Operating Charging Pumps

'and Plant Operational Modes for Keff< 0.95 Page 4 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Unit 1 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 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

Title Report No.

Rev Date Supl CE Method for Control Element Assembly CENPD-N.A.

January N.A.

Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1)

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

April N.A.

Nuclear Design 266-P-A 1983 (13-N001-1900-01412-0)

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

Uncertainties 356(V)-P-A 1988 (13-NOO1 -1303-01747-2)

System 8 0 TM Inlet Flow Distribution Enclosure N.A.

February 1-P (13-NOO1-1301-01228-0) 1-P to LD-1993 82-054 Calculative Methods for the CE Large Break CENPD-N.A.

March 4-P-A LOCA Evaluation Model for the Analysis of CE.

132 2001 and W Designed NSSS (13-NOO1 -1900-01192-3)

  • Calculative Methods for the CE Small Break CENPD-N.A.

April 2-P-A LOCA Evaluation Model 137-P 1998 (13-NO1 -1900-01185-3)

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

May N.A.

(13-NOO1-0201-00026-1)

P-A 1990 Arizona Public Service Company PWR Reactor NFM-005 N.A.

January N.A.

Physics Methodology Using 2006 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CENTS CE-NPD 2

March N.A.

CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1)

Vols. 1 Technical Description Manual for the CENTS CE-NPD 2

March N.A.

Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2)

Vols. 2 Page 6 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 Title Report No.

Rev Date Suppi Technical Description Manual for the CENTS CE-NPD 2

March N.A.

CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3)

Vols. 3 Implementation of ZIRLOTM Cladding Material CENPD-0 November N.A.

in CE Nuclear Power Fuel Assembly Designs 404-P-A 2001 (13-NOO -1900-01329-0)

HERMITE, A Multi-Dimensional Space-Time CENPD-July Kinetics Code for PWR Transients 188-A 1976 (HERMITE-TOPICAL)

TORC Code, A Computer Code for Determin-CENPD-April ing the Thermal Margin of a Reactor Core 161-P-A 1986 (NOO-1301-01202)

CETOP-D Code Structures and Modeling Meth-CEN-September ods for San Onofre Nuclear Generating Station 160(S)-P 1981 Units 2 and 3, (N001-1301-01185)

CPC Methodology Changes for the CPC CEN-3 10-0 April Improvement Program, (NOO1-1303-02283)

P-A 1986 Loss; of Flow, C-E Methods for Loss of Flow CENPD-0 June Analysis,. (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Containing CENPD-0 August Erbium Burnable Absorbers 382-P-A 1993 (N001-0201-00035)

Verification of the Acceptability of a 1-Pin Bur-CEN-386-0 August nup Limit of 60 MWD/kgU for Combustion P-A 1992 Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)

Page 7 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 limitsI 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 withdrawn3 while in Modes 1 and 2 (except whileperforming SR 3.1.5.3).

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, and4) 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.

b)' Regulating Gro up 5 position is maintained at least 10 inches lower than Page 8 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 - >147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 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 (T-)

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 9 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 < 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 10 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7

6 5

03 2

0

( 5 0 REGION OF(00)

ACCEPTABLE-OPERATION

~REGION :OF

  • UNACCEPTABLE
  • OPERATION (350,1:.0)

...........*.......................I...........................

0 100 200 300 400 COLD LEG TEMPERATURE (fF) 500 600 Page 11 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7

6 5

REGION OF ACCEPTABLE

-OPERATION..I_.

2 z

0 4

3 2

0 (350,4.0)

REGION OF UNACCEPTABI OPERATION I...

(500,6.5):

LE 0

100 200 300 400 COLD LEG TEMPERATURE ('F) 500 600 Page 12 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0

[.-

U L-.

W 0

[.-

0 0.5 0.0

-0.5

-1.0

-1.5

-2.0

-2.5

-3.0 0....

- ( i*

(..

.00O%,Q

i........

i....................

i (100%.-0.2

................... ýM T -C -A R E A --O F...................................................

ACCEPTABLE

............................ i....

i (0100%,4.2 I....

i...

L

-3.5

-4.0

.a 5

-45 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 13 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 I

FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*

I r..

rn

-r-r-T-rrr T.........

1111rrrIr 1

1 T r Ir[n[rs 20 A

15 0m 15 t0 t0 5

5 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.

Page 14 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 m

0.9 +-

0.8 -

0.7 0.6 w

H 0.5 0

0.4 U

0.3 0.2 0.1 A )

0 (n

0 0

Z 0.

I I

1 I

1 I

I I

I I

-(SEE FOOaTNOT-E-IN -SE-CTION3ýI-7 -.................

FOR APPLICABILITY FOLLOWING:

A REACTOR CUTBACK)

.A _ C.T.._

A.. )....................

GRP4,-POS-= (-I2.5-,x-FRA-C. PWR) -+- 25.5---

GRP 5 POS = (172.5 x FRAC. PWR) - 64.5 L--

1 I

I I

I 1

I GROUP5 GROUP3 GROUP I I

i I

I I

i I I I

I I I

I I

I I I

FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP4 GROUP2 Ft*

10 t0 6+0 3t Ft I1t0 1 0 6+0 30 CEA POSITION (INCHES WITHDRAWN)

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

Page 15 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 0.7 2

0.6 0.5 0

0.4 0.3 0.2 0.1 An t

0.

0zV 0

% ~ ~ ~ ~ ---

i.............?.... I................... :........ :......

(SEE FOOTNOTE-IN-SECTION 3-1-....

FOR APPIICABILITY FOLLOWING

.... E...AC.T..O.R...C....-BAK) -

GRP4POS-= (250.9 y FRAC; PWR-+-9.82-GRP 5 POS (250.9 k FRAC. PWR) - 80.18 IHN*HHB*

I I

I I

I V

GROUP5 GROUP3 GROUP 1 I I I

I I

I I

I I

I I

I I

I I

I I

I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0

GROUP 4 GROUP 2 Ft I t10 t9 60 3+0 Ft 100 6+0 3 CEA POSITION (INCHES WITHDRAWN)

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

Page 16 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 2 0.0.....

10.0 20.0 30.0 40.0 S

50.0 m

60.0 o

TRANSIE*NT INSERTION LIMIT (75.0::INCHES

30.

5 90.0............

OPERATION........

ZO

UNACCEPTABLE RESTRICTED, 1 0 0.0

.... i........................

z Z

710.0 I

1 LONG TERM STEADY STATE INSERTIONTLIMITS! (112.5 INCHES 130.0............

u 3 ~........

0

  • .............i.......i............

b PiT O --

OPERATION ACCEPTABLE 1 4 o.0 -....-

150.0 I...

I

..... I.....

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 17 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 I-F-

F-N 10.0 REGION OF

..REGION -OF...............

UNACCEPTABLE OPERATION 5.0 T

I

ýLCCEPTABLE OPERATION I.

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 18 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE Revision 19 IN ANY OPERABLE CPC CHANNEL 25 20 (95,20) z 0

0 z

15 101-

(80,5)

(70,0);

5 0

50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 19 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 2.4 ri-w-...............,-iY~i u................................

U l~

l l

U m l l...

1'IUY ll rrri999II 2.3 UD u

2.2 2.1 ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL i:

(-6.1,2.28)

-~ ~

I....,----------.....

la ACCEPTABLE OPERATION POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN EACH OPERABLEECPC CIIANNEL:".

(0.0.,2.00)

(-01, 93

  • °° UNACCEPT'ABLE

.O P E R A T IO N.......................................

I...

....I.

... I..

.. I...

. I....

I 2.0 1.9 18

-0.20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Re 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

... r r

ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5................................... --

O E B C

3.4

................. ]............. --...

U

(-0.1.3.27) 3.2 UNACCEPTABLE OPERATION 3.0

...... I i

i

.........i I

......... I.

-0.20

-0.15

-0.10

-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI vision 19 Page 21 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 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 Page 22 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Ž Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 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 Page 23 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 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 Page 24 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 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 Page 25 of 26

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 19 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 Number of Operating Charging Pumps MODE 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 Page 26 of 26