ML083090877: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Technical Specification 5.6.5.d.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 102-05916-TNW/KAR October 24, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
{{#Wiki_filter:Technical Specification 5.6.5.d
                              .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 102-05916-TNW/KAR October 24, 2008 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)Unit 1 Docket No. STN 50-528 Core Operating Limits Reports (COLR), Unit I -Revision 19 Pursuant to PVNGS Technical Specifications, Section 5.6.5.d, enclosed is Core Operating Limits Reports (COLR), Unit 1 -Revision 19, which was made effective October 24, 2008. This revision includes changes to the Moderator Temperature Coefficient (MTC) limits for Technical Specification (TS) 3.1.4, and the Axial Shape Index (ASI) limits for TS 3.2.5.By copy of this letter and the enclosure, this COLR revision is being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector.
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 Core Operating Limits Reports (COLR), Unit I - Revision 19 Pursuant to PVNGS Technical Specifications, Section 5.6.5.d, enclosed is Core Operating Limits Reports (COLR), Unit 1 - Revision 19, which was made effective October 24, 2008. This revision includes changes to the Moderator Temperature Coefficient (MTC) limits for Technical Specification (TS) 3.1.4, and the Axial Shape Index (ASI) limits for TS 3.2.5.
By copy of this letter and the enclosure, this COLR revision is being provided to the NRC Region IVAdministrator and the PVNGS Senior Resident Inspector.
This letter does not make any commitments to the NRC. If you have questions regarding this submittal, contact Russell A. Stroud, Licensing Section Leader at 623-393-5111.
This letter does not make any commitments to the NRC. If you have questions regarding this submittal, contact Russell A. Stroud, Licensing Section Leader at 623-393-5111.
Sincerely, TNW/RAS/KAR/gat
Sincerely, TNW/RAS/KAR/gat


==Enclosure:==
==Enclosure:==
PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 19 cc:      E. E. Collins Jr.          NRC Region IV Regional Administrator B. K. Singal              NRC NRR Project Manager R. I. Treadway            NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance                          4  O /
Callaway 11Comanche Peak 0 Diablo Canyon 0 Palo Verde U1San Onofre U]South Texas LiWolf Creek LH14A


PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 19 cc: E. E. Collins Jr. NRC Region IV Regional Administrator B. K. Singal NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance 4 O /Callaway 11 Comanche Peak 0 Diablo Canyon 0 Palo Verde U1 San Onofre U] South Texas Li Wolf Creek LH14A Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)Revision 19 PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 , Digitally signed by Bodnar, Responsible Engineer Bodnar, Walter S(Z06432)Date oN: cn=Bodnar, Walter S W alter S (41), erail=Walter.
Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)
W alt r S Bodnar@ aps.com Reason:.l am the author of this, document.  
Revision 19
'__ (Z06432) Date: 2008.10.22 11:39:09-07'00'Independent Reviewer Digitally signed by Hwang, Lun-Hwang, Chih (Z01868)Date DN, en=Hwang Lun-Chih un Reason: I have reviewed this (Z 1 668)"... Date: 2008.10.22 11:44:17-07'00'Responsible Section Leader Row land, James W(Z80533)Dateowla nd, W J":Rwanm .....033 DIN cn=Rowland, James W Date W (Z80533), email=James.
 
J a n esRowland@aps.com Reason: I am approving this document as acting Reload Analysis SL__ (Z80533) Date: 2008.10.22 13:14:20 -07'00'Page 1 of 26 PVNGS UNIT 1 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 1 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 1 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 1 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.
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
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 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:
UNIT 1 CORE OPERATING LIMITS REPORT Revision 19
Title Report No.Rev Date Supplement
                                                      , Digitally signed by Bodnar, Responsible Engineer Date Bodnar,           Walter S(Z06432)
: 1) CE Method for Control Element Assembly Ejection Analysis (13-N001-1301-01204-1)
W alter    S Walt r S oN: cn=Bodnar, Walter S (41), erail=Walter.
: 2) The ROCS and DIT Computer Codes for Nuclear Design (13-N001-1900-01412-0)
Bodnar@ aps.com Reason:.l am the author of this, document. '
: 3) Modified Statistical Combination of Uncertainties (13-N001-1 303-01747-2)
__ (Z06432)           Date: 2008.10.22 11:39:09
: 4) System 8 0 TM Inlet Flow Distribu-tion (13-N001-1301-01228-0)
                                                        -07'00' Independent Reviewer                                 Digitally signed by Hwang, Lun-Date Hwang,         Chih (Z01868)
: 5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (13-NOO1 -1900-01192-3)
DN,en=Hwang Lun-Chih un           Reason: I have reviewed this (Z 1668)"... Date: 2008.10.22 11:44:17
: 6) Calculative Methods for the CE Small Break LOCA Evaluation Model (13-NOO1-1900-01185-3)
                                                      -07'00' Responsible Section Leader Dateowla Row land, nd, W
: 7) Fuel Rod Maximum Allowable Pressure (13-N001-0201-00026-1)
W(Z80533)
: 8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)CENPD-0190-A CENPD-266-P-A N.A. January 1976 N.A.N.A.N.A.April 1983 May 1988 (April 1996)CEN-356(V)-P-A -P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A 01-P-A (ARI)N.A.N.A. February 1993 N.A.N.A.N.A.March 2001 April 1998 May 1990 1-P 4-P-A 2-P-A N.A.NFM-005 N.A.January 2006 N.A.Page 6 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 Title Report No.Rev Date Supplement
J":Rwanm.
: 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)12) Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (13-N001-1900-01329-0)
James 033....
CE-NPD 282-P-A Vols. 1 CE-NPD 282-P-A Vols. 2 CE-NPD 282-P-A Vols. 3 CENPD-404-P-A 2 March 2005 2 March 2005 2 March 2005 0 November 2001 N.A.N.A.N.A.N.A.Page 7 of 26 PVNGS UNIT 1 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 3.1.5-1.3.1.7 -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 limits 1 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.
Date                                            W    DIN cn=Rowland, James W JnaesRowland@aps.com (Z80533), email=James.
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:
Reason: I am approving this document as acting Reload (Z80533)
Analysis SL Date: 2008.10.22 13:14:20 -07'00' Page 1 of 26
 
PVNGS UNIT 1 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 1 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 1 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 1 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 1 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     Supplement
: 1) CE Method for Control Element         CENPD-            N.A.      January 1976      N.A.
Assembly Ejection Analysis           0190-A (13-N001-1301-01204-1)
: 2) The ROCS and DIT Computer             CENPD-           N.A.      April 1983        N.A.
Codes for Nuclear Design            266-P-A (13-N001-1900-01412-0)
: 3) Modified Statistical Combination         CEN-           01-P-A        May 1988        N.A.
of Uncertainties              356(V)-P-A        (ARI)      (April 1996)
(13-N001-1 303-01747-2)
: 4) System  8 0 TM  Inlet Flow Distribu-   Enclosure          N.A. February 1993        1-P tion                    1-P to LD-(13-N001-1301-01228-0)               82-054
: 5) Calculative Methods for the CE         CENPD-            N.A.      March 2001      4-P-A Large Break LOCA Evaluation               132 Model for the Analysis of CE and W Designed NSSS (13-NOO1 - 1900-01192-3)
: 6) Calculative Methods for the CE        CENPD-           N.A.      April 1998      2-P-A Small Break LOCA Evaluation              137-P Model (13-NOO1-1900-01185-3)
: 7) Fuel Rod Maximum Allowable            CEN-372-           N.A.        May 1990        N.A.
Pressure                      P-A (13-N001-0201-00026-1)
: 8) Arizona Public Service Company        NFM-005            N.A.         January        N.A.
PWR Reactor Physics Methodology                                            2006 Using CASMO-4/SIMULATE-3 (NFM-005)
Page 6 of 26
 
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT       Revision 19 Title                 Report No. Rev   Date     Supplement
: 9) Technical Description Manual for   CE-NPD      2  March 2005    N.A.
the CENTS CodeVolume 1           282-P-A (CENTS-TD MANUAL-VOL 1)             Vols. 1
: 10) Technical Description Manual for   CE-NPD      2  March 2005    N.A.
the CENTS Code Volume 2           282-P-A (CENTS-TD MANUAL-VOL 2)             Vols. 2
: 11) Technical Description Manual for   CE-NPD      2  March 2005    N.A.
the CENTS CodeVolume 3           282-P-A (CENTS-TD MANUAL-VOL 3)             Vols. 3
: 12) Implementation of ZIRLOTM         CENPD-      0  November      N.A.
Cladding Material in CE Nuclear   404-P-A          2001 Power Fuel Assembly Designs (13-N001-1900-01329-0)
Page 7 of 26
 
PVNGS UNIT 1 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.
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 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.
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 Regulating Group 4 position.Page 8 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 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  
b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.
->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.
Page 8 of 26
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 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
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                         Revision 19 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).
_> 3000 ppm.Page 10 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 5 4 z 0 3 2 0 0 100 200 300 400 500 COLD LEG TEMPERATURE
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.
('F)600 Page 11 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7.........I ...................I .........................6 5 4 z 3 0 F-2 0 REGION OF ACCEPTABLE OPERATION..............
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 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 1 CORE OPERATING LIMITS REPORT     Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7
6 5
4 z
0 3 2
0 0     100     200       300     400   500 600 COLD LEG TEMPERATURE ('F)
Page 11 of 26
 
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                           Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7   . .... . ...I ... .. ... .... .. .... . I... ... .. ... .... .. .. ... ...
(500,6.5)::
(500,6.5)::
(350,4.0)...... ............................
6                                                        ..............
.................  
REGION OF ACCEPTABLE 5                  OPERATION                            ...............
..............
4 z                                                                                                  (350,4.0) 3 0                                                            ...............
...............
F-REGION OF UNACCEPTABLE 2            .................     ..............
REGION OF UNACCEPTABLE
OPERATION I I l l.l.. l.. l.             .     .. ... .   .                                                                 1        Illllllll 0
............................  
0                    100                      200                    300                          400                    500          600 COLD LEG TEMPERATURE (F)
............--  
Page 12 of 26
------OPERATION.. .. .. ....... ..... ......I I l l. l. .l. .l. ........1 Illllllll 0 100 200 300 400 COLD LEG TEMPERATURE (F)500 600 Page 12 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2'0 F-U 0 U L1.~F-0 F-0 0.5 0.0-0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5 (0% .-3. .......i -- -I ---.... .. * (100%,0...................--------......... ............ .....................---------. ................. .............................: .., , ,; ( 100%,-0.2............  
 
... .. ..... ...............  
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                                                                                                            Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2' 0.5 (0% .-3.                                                                                    .. ..                       ...
.............  
                  . .. . .i .----.-.-.-
............
                                                                  .........               ---------.          -I -........
............... ............... -.. -............--
                                                                                                              ......           - -.... *:.             ............................              ..*. ...: ...*            (100%,0 ,,,
---...........  
0.0
........-------------------
                                                                                                      *          ;                                                                                                    ( 100%,-0.2
........................................................................................-
    -0.5 0    -1.0 F-U    -1.5
!ACCEPT'ABLE
                                                                                          !ACCEPT'ABLE 0
:OPERATION:
U                                                                                          :OPERATION:
... ........................ ... ... -- -----..... .. ...... ... .... ... ... --------- -- -- ---- -- .. ... .........  
    -2.0
.... .... .... ...............
    -2.5 L1.~
........ ...-----------.. ........... ............................. ............'2. .......................................- --. ......... ...
F-                                     . . . . . . . . . ... . . . . . . . .
.1 ... ..... ... .. ...........
                            -----------..                                    . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . '2.
i .... ... ...... -- ------- --------- -- -- ----..... .... -- --.. ..... ...i .........  
0 F-
...... .I.. ..I.. ..-- ---------....I. ....--. -- ---- --- -- -- ...--- -- --- ---- -- --- -II 0 10 20 30 40 50 60 70 CORE POWER LEVEL (% OF RATED THERMAL POWER)80 90 100 Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit .......Page 13 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*
    -3.0 0          -o%.-3-4),*
Revision 19 30 25 04 20 15 (60 MIN, 20.0%)...........  
                .1                                                                ... . . .-- .-
.. ..... ....... ..........  
                                                                                                                  -- .-. -. ----i---                --    --    ----.....               ....--            -..-.....   ...i. . . . . ...
........................
    -3.5 II
........................
    -4.0
.................
                .   ..         -- - -. -. -. -I..- .- .         - - I..                             . . . .       I... .--. . -- ----          --- -- --                                      -----    . -. --    . - ----- - ---
... ....................
    -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 .......
........ Z .............
Page 13 of 26
..... ..... ....--- ................  
 
.... .............
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                                            Revision 19 FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*
(0 MIN, 0.0%)..... .... .. ...................
30 25 (60 MIN, 20.0%)
I............I.............I..  
20 04 15 Z.............               .....
..........
10 -
10 -5 0 0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIMIT CURVE. FURTHER REDUCTION IS NOT REQUIRED.Page 14 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)1.0 0.9 0.8 0.7 0 0.6 0J.5 , 0.5 0 0.4 0.3 0.2 0.1.0n........ ----- --(SEE-FOO.TNO-TE IN SE-CTION 34.7.FOR APPLICABILITY FOLLOWING A REACTOR C'UTBACK)...
5 (0 MIN, 0.0%)
......  
0                        ..... .. .... ...................               I............I.............I..                           ..........
...... .. ----- GRP 4-PoS-=-(1-72-.5-xFRA.C.PW R)- 25---5 -......; GRP POS= (i72.5ix FAC. PWR)- 64.5....~ ~ ~ ~ -J N --------------..  
0                    10                          20                  30                              40                  50                        60 TIME AFTER DEVIATION, MINUTES
.. ... .. -- --........ -- --------- -- ------ ---- --- ; ..................'U Zo p4 .:... ..... o r .... ... i .... .... .... .... .... .... .... .... .... ............
* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIMIT CURVE. FURTHER REDUCTION IS NOT REQUIRED.
.... .... .... .... .... .... .. ..... .. ... ..............
Page 14 of 26
l...... .....----
 
... .... ....i .......V.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 GROUP4 GROUP2 Ft 0o 36o CEA POSITION (INCHES WITHDRAWN)
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                                                                      Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 0.9                              ........
*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 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)1.0 00 99... ... ... .... ... ... ... ... ....... ... ... ... .....-. ... ... ... .... ... ... ... ... .... ... ... ... .........
                                                  -----                    -- (SEE-FOO.TNO-TE IN SE-CTION 34.7.
...... ----------- --0.8 (S.......................  
FOR APPLICABILITY FOLLOWING A REACTOR C'UTBACK)...
...... ................ (SEE FOOTNOTE..IN.SEC.TION-3.1.7--
0.8 0.7 . ..... *:::...............     ...... ..-----GRP4-PoS-=-(1-72-.5-xFRA.C.PW R)- 25---5-......
FOR APPLICABILITY FOLLOWING0.7 [E- A: REACTOR CUTBACK.0 .7 .-- ---. .-- -- .. ...-.. ....... ........ .....---.R-.O.= .2 ...F , .-W.a..-0.6 GRP-4POS=(250.9-X FRAC. PWR ,-9;82 GRP S. POS =(250.9 i FRAC. PWR) -80118= -80 1 0.5 : .... 'z 0.4 ........ ........-.----...................................  
0                                                      ;            GRP POS= (i72.5ix FAC. PWR)- 64.5
....... ........ ....... ....... ........ .....
                            . ...~~ N              ~          ~-J--------------..
03 0.0 I I I I I t I I GROUP 5 GROUP 3 GROUP 1 I I II 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 2610 30 06]0 30 CEA POSITION (INCHES WITHDRAWN)
0.6
*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 19 0.0 10.0 20.0 30.0 40.0 50.0 V)u z V-0 ry.*UI-.F-,...........................  
                                  'U        Zo p4                :...                                                        .            .
.............
0J.5 0.5
4..............
                                                ....o...ri* _*..................................... . . . . . ........................... .
.............
0    0.4
................................................
                    * ,*!"* i*
---------.7 .............  
0.3
.............
                                                                                ......             .....----    ... ....       ....i .......
i ....................
                                                  .     ..... l *-.................l 0.2 0.1.
.............  
0n V.
.........--------------
GROUP5 I      I          I          I      I      I      I GROUPI 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 GROUP4                                  GROUP2 Ft        0o                                                            36o 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 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 00 99...           ...  ... ....   ...   ... ...   ... .......   ... ... ...   .....-. ... ... ...   .... ... ... ... ... ....
-------------
0.8                                              ......                         (S.......................
...........  
                                                                          ................(SEE        FOOTNOTE..IN.SEC.TION-3.1.7--
-------- ---- ..... .. .... ..........
FOR APPLICABILITY FOLLOWING
-------------
        "*  0.7            [E-                                                             A: REACTOR CUTBACK.
-------------
0.7 .               . --      . . . --
--------------------------------------
                                                            .--                                 ............---..2.
...........  
                                                                                              .R-.O.=                              . .F , .- W.a..-
.............  
0.6                                                                          GRP-4POS=(250.9-X FRAC. PWR                                                            ,-9;82 GRP S.POS                =(250.9        i FRAC. PWR)                            -   80118
..............
                                                                                                                    =                                                      - 80 1 0.5        :            ....            '
.............  
03 z 0.4            ........         ........-.----...................................             . . ..... ........ ........ ...... ........*                *..............
....... -.............  
0.0        I      I                    I                    I                                                        I        t            I            I GROUP 5                                                    GROUP 3                                                  GROUP 1 I I      II 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*/*O910 610 30                                                  F**10 06]0 30 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                                                                                                                              Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0                    ...........................   .............           4                              ......     ................     -------------           -
-_ .........  
20.0                      ...........................       ......                             - ------  ----....... ....                                         ..........
------ ------- -----------
30.0                      ..........................................               --------- -------------    -------------    --------------------------------------
-------------
40.0                                 .7 .............   .............           i .........    ...........   .............   .............. .............           -
.............  
V) 50.0                              ...........           .............               ......... .............     .............   .............   ........   .... ...........
.............  
60.0  V                              --------------  .............                                           .............. - _ .........   -------------    -----------
........ .... ...........  
u z
-tRANSI&#xfd;NT INSEkTION LIMIT (75.0::INCHES) 60.0 V-----------
U 70.0   -----------      ---------------------------  -------------              --------- -------------    .............   .............   ........   .... ...........
70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0............
tRANSI&#xfd;NT INSEkTION LIMIT (75.0::INCHES)
OPERATION
                                                                                                            -              -                -                        I ry.
............
V-z*
4.UNACCEPTABLE
                                                                                                              ... ..i............. .......... . . .                   -----------
.......-------------------. .-----------................---I 2.. ... ... ...i.............  
80.0 I-.
..........  
0
........... OPERATION
              ............ OPERATION ............ 4.                                             2        ........ OPERATION -----...........
-----RESTRICTED
90.0 UNACCEPTABLE                                                                        RESTRICTED F-,  100.0 110.0 120.0
.. ... ..............  
                  . LONG
..........
              ..---       . . TERM
..-. ..-----------
                      ..---.........             STEADY
...........
                                                          . -----..     STATE
LONG TERM STEADY STATE INSERTIONLIMITSi (112.5 INCHES).......------.............---........---------....-----............----.. ........ ..... ......-------------------.. ....... ......... ',............
                                                                          ---..--............ INSERTIONLIMITSi
-- -----..............
                                                                                                    ----..                           (112.5
.............
                                                                                                                                            -----INCHES) 130.0 OPERATION ACCEPTABLE 140.0 I-----------    .         I .                                     .       . . . ..     . -
.............
15    0.0 . . . . . . . .
-------------..
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
...............
 
',. ................
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT                                Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0                                  REGIONOF  UN ACCE...   -----------
OPERATION ACCEPTABLE
UNACCEPTABLE OPERATION
-----------I .I .......... .--15 0.0 ........1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 FRACTION OF RATED THERMAL POWER 0.0 Page 17 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)20.0 15.0[.-2: 0 t'-----------
[.-
REGIONOF UN ACCE...UNACCEPTABLE OPERATION-----------
2:
...........
0 10.0                                                          ...........
10.0 5.0' r r I REGION OF, WCCEPTABLE OPERA TION 0.0 20.,..................
t' 5.0                                        '        r    r          I REGION OF, WCCEPTABLE OPERA TION 0.0                                  ..................                 ....
....0 30.0 40.0 50.0 60.0 70.0 80.0 CORE POWER LEVEL (% OF RATED THERMAL POWER)90.0 100.0 Page 18 of 26 PVNGS UNIT 1 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..... llll 20 z 0 E0 0 0 15 10.................................
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
.........(75,0)(95,20)5 0 0 25 50 75 CORE POWER LEVEL (% OF RATED THERMAL POWER)100 Page 19 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 2.5 2.4 2.3 2.2 2.1 u FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)........... ........... ... ..... .... ............. ...ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0.06,2.38)
 
(0.1,2.38):
PVNGS UNIT 1 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    .....              llll (95,20) 20 z
................
0 E0 15 10 0      . ................................ . ... ... .. ... ... . - ----...
................
0 5
.......... ....................
(75,0) 00                                                                                                                    75                100 25                                        50 CORE POWER LEVEL
... ................
(% OF RATED THERMAL POWER)
.................
Page 19 of 26
................................
 
(-0..... 1,2 5 28) ... .ACCEPTABLE OPERATION POWER AT OR ABOVE 90%* i AT LEAST 1 CEAC OPERABLE IN...EACHOPER-ABLE-CPC CHANNEL-: (0.05,2.00)
PVNGS UNIT 1 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                      ......... .. ... ........ . .. ..... .. .. ....... ... ... ...
* 00 00'0'. ..(-..93) &deg; UNACCEPTABLE
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0.06,2.38)                            (0.1,2.38):
.................
1,25 28) ...
......................................
(-0.....                                                         .
O P E R A T IO N .................................
2.3 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
....... ........... ... ... ... I .... .. .I L.. ..... ...... I.. .... ... I ....2.0 1.9 1.8-0.20 -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 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 ........... ... .. .... .. ..... ...I. .............ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE
* i AT LEAST 1 CEAC OPERABLE IN 2.1    .             .           .                 EACHOPER-ABLE-CPC CHANNEL-:
...... ...... ...... ...... .... ................
u (0.05,2.00) 2.0
.........................
* 00'0'.                        00                                                                ..
..... ...3.5 -----IN AN-XY OPERABLE CPC CHANNEL (0031) ~(0.1.3.41):
(-..93) &deg;                                        UNACCEPTABLE 1.9    .................     ...................................... O PE R AT ION .................................                 ....... .......
3 .3 ..............
1.8        ....        . .. ... ...I . ... ..                    .I  L...    .                ... ...... I.. . ... ... I .                 . . .
................
    -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
---- ...... --- --- -- --- -- .... .. .. .. .. ..... ........ .. .... .... 1 ..... ... ..(-3. ].23.27)3 .2 -.- -- --............
 
....... ..............
PVNGS UNIT 1 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  . . . . .           . .....         ... .. ....       .. . . .         ..     . .     .I.       . . . .                 . . . .           . . . . .
.......... ....................................................
ACCEPTABLE OPERATION ANY POWER LEVEL
.................--
        . . . . . . . . . . . . ......BOTH CEACs INOPERABLE                                            .............. ......................... . . . ...
------UNACCEPTABLE OPERATION 3.1 -.... ........3.0 ... ....... ........ .........
3.5 -----                          IN AN-XY OPERABLE CPC CHANNEL (0031) ~(0.1.3.41):
.........
3.3 .............. ................ ----......                --- --- --
.........
                                                                        ----- ....  ..  ...........       ........ ..             1 ....
I .........
(-3. ].23.27) 3 .2  -.--- --............                      . . . . . .. . . . . . . . . . . . . . . . .....................................
I........-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 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 1 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 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 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 1 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 1 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}}
UNACCEPTABLE OPERATION 3.1  -          .
3.0          ...       .......           ........           .........         .........           .........               I .........               I........
  -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 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 1 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 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 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 1 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 &#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 1 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 20:01, 12 March 2020

Core Operating Limits Reports (COLR) - Revision 19
ML083090877
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 10/24/2008
From: Weber T
Arizona Public Service Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05916-TNW/KAR
Download: ML083090877 (28)
v • d • e


Text

Technical Specification 5.6.5.d

.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 102-05916-TNW/KAR October 24, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 Core Operating Limits Reports (COLR), Unit I - Revision 19 Pursuant to PVNGS Technical Specifications, Section 5.6.5.d, enclosed is Core Operating Limits Reports (COLR), Unit 1 - Revision 19, which was made effective October 24, 2008. This revision includes changes to the Moderator Temperature Coefficient (MTC) limits for Technical Specification (TS) 3.1.4, and the Axial Shape Index (ASI) limits for TS 3.2.5.

By copy of this letter and the enclosure, this COLR revision is being provided to the NRC Region IVAdministrator and the PVNGS Senior Resident Inspector.

This letter does not make any commitments to the NRC. If you have questions regarding this submittal, contact Russell A. Stroud, Licensing Section Leader at 623-393-5111.

Sincerely, TNW/RAS/KAR/gat

Enclosure:

PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 19 cc: E. E. Collins Jr. NRC Region IV Regional Administrator B. K. Singal NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance 4 O /

Callaway 11Comanche Peak 0 Diablo Canyon 0 Palo Verde U1San Onofre U]South Texas LiWolf Creek LH14A

Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)

Revision 19

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 1 CORE OPERATING LIMITS REPORT Revision 19

, Digitally signed by Bodnar, Responsible Engineer Date Bodnar, Walter S(Z06432)

W alter S Walt r S oN: cn=Bodnar, Walter S (41), erail=Walter.

Bodnar@ aps.com Reason:.l am the author of this, document. '

__ (Z06432) Date: 2008.10.22 11:39:09

-07'00' Independent Reviewer Digitally signed by Hwang, Lun-Date Hwang, Chih (Z01868)

DN,en=Hwang Lun-Chih un Reason: I have reviewed this (Z 1668)"... Date: 2008.10.22 11:44:17

-07'00' Responsible Section Leader Dateowla Row land, nd, W

W(Z80533)

J":Rwanm.

James 033....

Date W DIN cn=Rowland, James W JnaesRowland@aps.com (Z80533), email=James.

Reason: I am approving this document as acting Reload (Z80533)

Analysis SL Date: 2008.10.22 13:14:20 -07'00' Page 1 of 26

PVNGS UNIT 1 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 1 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 1 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 1 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 1 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 Supplement

1) CE Method for Control Element CENPD- N.A. January 1976 N.A.

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

2) The ROCS and DIT Computer CENPD- N.A. April 1983 N.A.

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

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

of Uncertainties 356(V)-P-A (ARI) (April 1996)

(13-N001-1 303-01747-2)

4) System 8 0 TM Inlet Flow Distribu- Enclosure N.A. February 1993 1-P tion 1-P to LD-(13-N001-1301-01228-0)82-054
5) Calculative Methods for the CE CENPD- N.A. March 2001 4-P-A Large Break LOCA Evaluation 132 Model for the Analysis of CE and W Designed NSSS (13-NOO1 - 1900-01192-3)
6) Calculative Methods for the CE CENPD- N.A. April 1998 2-P-A Small Break LOCA Evaluation 137-P Model (13-NOO1-1900-01185-3)
7) Fuel Rod Maximum Allowable CEN-372- N.A. May 1990 N.A.

Pressure P-A (13-N001-0201-00026-1)

8) Arizona Public Service Company NFM-005 N.A. January N.A.

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

Page 6 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 Title Report No. Rev Date Supplement

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

the CENTS CodeVolume 1 282-P-A (CENTS-TD MANUAL-VOL 1) Vols. 1

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

the CENTS Code Volume 2 282-P-A (CENTS-TD MANUAL-VOL 2) Vols. 2

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

the CENTS CodeVolume 3 282-P-A (CENTS-TD MANUAL-VOL 3) Vols. 3

12) Implementation of ZIRLOTM CENPD- 0 November N.A.

Cladding Material in CE Nuclear 404-P-A 2001 Power Fuel Assembly Designs (13-N001-1900-01329-0)

Page 7 of 26

PVNGS UNIT 1 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.

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

6 5

4 z

0 3 2

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

Page 11 of 26

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

(500,6.5)::

6 ..............

REGION OF ACCEPTABLE 5 OPERATION ...............

4 z (350,4.0) 3 0 ...............

F-REGION OF UNACCEPTABLE 2 ................. ..............

OPERATION I I l l.l.. l.. l. . .. ... . . 1 Illllllll 0

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

Page 12 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2' 0.5 (0% .-3. .. .. ...

. .. . .i .----.-.-.-

......... ---------. -I -........

...... - -.... *:. ............................ ..*. ...: ...* (100%,0 ,,,

0.0

  • ; ( 100%,-0.2

-0.5 0 -1.0 F-U -1.5

!ACCEPT'ABLE 0

U :OPERATION:

-2.0

-2.5 L1.~

F- . . . . . . . . . ... . . . . . . . .

.. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . '2.

0 F-

-3.0 0 -o%.-3-4),*

.1 ... . . .-- .-

-- .-. -. ----i--- -- -- ----..... ....-- -..-..... ...i. . . . . ...

-3.5 II

-4.0

. .. -- - -. -. -. -I..- .- . - - I.. . . . . I... .--. . -- ---- --- -- -- ----- . -. -- . - ----- - ---

-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 Revision 19 FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*

30 25 (60 MIN, 20.0%)

20 04 15 Z............. .....

10 -

5 (0 MIN, 0.0%)

0 ..... .. .... ................... I............I.............I.. ..........

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

  • WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIMIT CURVE. FURTHER REDUCTION IS NOT REQUIRED.

Page 14 of 26

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 0.9 ........

-- (SEE-FOO.TNO-TE IN SE-CTION 34.7.

FOR APPLICABILITY FOLLOWING A REACTOR C'UTBACK)...

0.8 0.7 . ..... *:::............... ...... ..-----GRP4-PoS-=-(1-72-.5-xFRA.C.PW R)- 25---5-......

0  ; GRP POS= (i72.5ix FAC. PWR)- 64.5

. ...~~ N ~ ~-J--------------..

0.6

'U Zo p4  :... . .

0J.5 0.5

....o...ri* _*..................................... . . . . . ........................... .

0 0.4

  • ,*!"* i*

0.3

...... .....---- ... .... ....i .......

. ..... l *-.................l 0.2 0.1.

0n V.

GROUP5 I I I I I I I GROUPI 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 GROUP4 GROUP2 Ft 0o 36o 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 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 00 99... ... ... .... ... ... ... ... ....... ... ... ... .....-. ... ... ... .... ... ... ... ... ....

0.8 ...... (S.......................

................(SEE FOOTNOTE..IN.SEC.TION-3.1.7--

FOR APPLICABILITY FOLLOWING

"* 0.7 [E- A: REACTOR CUTBACK.

0.7 . . -- . . . --

.-- ............---..2.

.R-.O.= . .F , .- W.a..-

0.6 GRP-4POS=(250.9-X FRAC. PWR ,-9;82 GRP S.POS =(250.9 i FRAC. PWR) - 80118

= - 80 1 0.5  : .... '

03 z 0.4 ........ ........-.----................................... . . ..... ........ ........ ...... ........* *..............

0.0 I I I I I t I I GROUP 5 GROUP 3 GROUP 1 I I II 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*/*O910 610 30 F**10 06]0 30 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 Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 ........................... ............. 4 ...... ................ ------------- -

20.0 ........................... ...... - ------ ----....... .... ..........

30.0 .......................................... --------- ------------- ------------- --------------------------------------

40.0 .7 ............. ............. i ......... ........... ............. .............. ............. -

V) 50.0 ........... ............. ......... ............. ............. ............. ........ .... ...........

60.0 V -------------- ............. .............. - _ ......... ------------- -----------

u z

U 70.0 ----------- --------------------------- ------------- --------- ------------- ............. ............. ........ .... ...........

tRANSIýNT INSEkTION LIMIT (75.0::INCHES)

- - - I ry.

V-z*

... ..i............. .......... . . . -----------

80.0 I-.

0

............ OPERATION ............ 4. 2 ........ OPERATION -----...........

90.0 UNACCEPTABLE RESTRICTED F-, 100.0 110.0 120.0

. LONG

..--- . . TERM

..---......... STEADY

. -----.. STATE

---..--............ INSERTIONLIMITSi

.. (112.5

INCHES) 130.0 OPERATION ACCEPTABLE 140.0 I----------- . I . . . . . .. . -

15 0.0 . . . . . . . .

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 REGIONOF UN ACCE... -----------

UNACCEPTABLE OPERATION

[.-

2:

0 10.0 ...........

t' 5.0 ' r r I REGION OF, WCCEPTABLE OPERA TION 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 1 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 ..... llll (95,20) 20 z

0 E0 15 10 0 . ................................ . ... ... .. ... ... . - ----...

0 5

(75,0) 00 75 100 25 50 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 19 of 26

PVNGS UNIT 1 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 ......... .. ... ........ . .. ..... .. .. ....... ... ... ...

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0.06,2.38) (0.1,2.38):

1,25 28) ...

(-0..... .

2.3 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90%

  • i AT LEAST 1 CEAC OPERABLE IN 2.1 . . . EACHOPER-ABLE-CPC CHANNEL-:

u (0.05,2.00) 2.0

  • 00'0'. 00 ..

(-..93) ° UNACCEPTABLE 1.9 ................. ...................................... O PE R AT ION ................................. ....... .......

1.8 .... . .. ... ...I . ... .. .I L... . ... ...... I.. . ... ... I . . . .

-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

PVNGS UNIT 1 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 . . . . . . ..... ... .. .... .. . . . .. . . .I. . . . . . . . . . . . . .

ACCEPTABLE OPERATION ANY POWER LEVEL

. . . . . . . . . . . . ......BOTH CEACs INOPERABLE .............. ......................... . . . ...

3.5 ----- IN AN-XY OPERABLE CPC CHANNEL (0031) ~(0.1.3.41):

3.3 .............. ................ ----...... --- --- --

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

(-3. ].23.27) 3 .2 -.--- --............ . . . . . .. . . . . . . . . . . . . . . . .....................................

UNACCEPTABLE OPERATION 3.1 - .

3.0 ... ....... ........ ......... ......... ......... I ......... I........

-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 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 1 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 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 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 /> 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 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 /> 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 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 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ONA ONA Notes: . SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26

PVNGS UNIT 1 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 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 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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.hours 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 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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

Retrieved from "https://kanterella.com/w/index.php?title=ML083090877&oldid=2566015"