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{{#Wiki_filter:Technical Specification 5.6.5d Saps 102-06813 TNW/RKR January 2, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | {{#Wiki_filter:Technical Specification 5.6.5d Saps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road Tonopah, AZ 85354 102-06813 TNW/RKR January 2, 2014 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, 3 Docket Nos. STN 50-528, 50-529 and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 23 Unit 2 Core Operating Limits Report (COLR), Revision 19 Unit 3 Core Operating Limits Report (COLR), Revision 22 Pursuant to PVNGS Technical Specifications, Section 5.6.5d, enclosed are the Units 1, 2 and 3 Core Operating Limits Report (COLR), Revisions 23, 19 and 22, respectively, which were made effective December 20, 2013. The following change was implemented in these COLR revisions: | Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, 3 Docket Nos. STN 50-528, 50-529 and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 23 Unit 2 Core Operating Limits Report (COLR), Revision 19 Unit 3 Core Operating Limits Report (COLR), Revision 22 Pursuant to PVNGS Technical Specifications, Section 5.6.5d, enclosed are the Units 1, 2 and 3 Core Operating Limits Report (COLR), Revisions 23, 19 and 22, respectively, which were made effective December 20, 2013. The following change was implemented in these COLR revisions: | ||
Figure 3.1.5-1 revised to include an exemption to the immediate downpower requirement, allowed if certain prerequisites are met, for a single small CEA misalignment (greater than 6.6 inches but less than 9.9 inches) in the top 9.9 inches of the active fuel region.No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/KAR/hsc | Figure 3.1.5-1 revised to include an exemption to the immediate downpower requirement, allowed if certain prerequisites are met, for a single small CEA misalignment (greater than 6.6 inches but less than 9.9 inches) in the top 9.9 inches of the active fuel region. | ||
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241. | |||
Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/KAR/hsc | |||
==Enclosures:== | ==Enclosures:== | ||
PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 23 PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 19 PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 22 cc: M. L. Dapas NRC Region IV Regional Administrator J. K. Rankin NRC NRR Project Manager for PVNGS A. E. George M. A. Brown NRC NRC NRR Project Manager Senior Resident Inspector for PVNGS DZA A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway | |||
PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 23 PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 19 PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 22 cc: M. L. Dapas J. K. Rankin A. E. George M. A. Brown NRC | |||
* Comanche Peak | * Comanche Peak | ||
* Diablo Canyon | * Diablo Canyon | ||
| Line 33: | Line 33: | ||
* San Onofre | * San Onofre | ||
* South Texas | * South Texas | ||
* Wolf Creek Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)Revision 23 PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 Effective December 20, 2013 I I | * Wolf Creek | ||
Date DN cn=Ashton, Jeffrey IlC(Z03403) | |||
Jeffrey | Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR) | ||
-070 Page 1 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 9 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) I1 3.9.1 Boron Concentration I1 Page 2 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Figures Description Figure 3.1.1i-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 | Revision 23 | ||
T.S Ref#a Title Report No. Rev Date CE Method for Control Element Assem- CENPD- N.A. January N.A.1 bly Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1) | PALO VERDE NUCLEAR GENERATING STATION (PVNGS) | ||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design 266-P-A (13-N001 -1900-01412-0) | UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 I Effective December 20, 2013 I I | ||
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September | Independent Reviewer Boate iar, fl, Digitally signed by Bodnar, Waiter S(Z06432) | ||
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOI-1301-01228-0) | Date Walter /*'°32) DN cn=Bodnar, Walter 5(Zox32 alte / a ve reviewed this S(Z064;. Date 20 | ||
I-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOO1-1900-01192-3) | -07'00' | ||
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOO1 -1900-01185-3) | ~12.18 16:15:01 Responsible Section Leader to , | ||
Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for: 5.6.5.b.6. | As, Astn , jDigitallysigned efr.yCZ03403)by Ashton, Date DN cn=Ashton, Jeffrey IlC(Z03403) | ||
Page 6 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T.S Ref#a Title Report No. Rev Date Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6. | Jeffrey anmapproving this S .Date, 20132.1822:23:06 | ||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.( | -070 Page 1 of 27 | ||
P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for | |||
Arizona Public Service Company PWR NFM-005 1 August N.A.Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) I1 3.9.1 Boron Concentration I1 Page 2 of 27 | ||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Figures Description Page Figure 3.1.1i-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service) | |||
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service) | |||
HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service) | ||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161 -P-A 1986 Reactor Core (NO01 -1301-01202) | Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s) | ||
Page 7 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T. S ReS Title Report No. Rev | Operable) | ||
Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003)17 and November"Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 -Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.18 Improvement Program, (NO01-1 303- P-A 1986 02283) | Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel) | ||
Verification of the Acceptability of a I- CEN-386- 0 August N.A.Pin Bumup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | Page 3 of 27 | ||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 I 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 limitsI shown in Figure 3.1.7-2.2 Regulating Groups I and 2 CEAs shall be maintained | |||
> fully withdrawnI' 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffh 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 27 | ||
When > 20% power Regulating Group 3 shall be maintained | |||
> fully withdrawn. | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: | |||
T.S Ref#a Title Report No. Rev Date CE Method for Control Element Assem- CENPD- N.A. January N.A. | |||
1 bly Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1) | |||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A. | |||
2 Nuclear Design 266-P-A (13-N001 - 1900-01412-0) | |||
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 3 Steam Supply Reference Systems September 19832 CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A. | |||
4 Uncertainties 356(V)-P-A (13-NOO1-1303-01747-2) | |||
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOI-1301-01228-0) I-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOO1-1900-01192-3) | |||
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOO1 -1900-01185-3) | |||
Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A. | |||
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for: | |||
5.6.5.b.6. | |||
Page 6 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T.S Ref#a Title Report No. Rev Date Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A. | |||
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6. | |||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A. | |||
(13-N001-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A. | |||
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | |||
Arizona Public Service Company PWR NFM-005 1 August N.A. | |||
Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005) | |||
Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. 1 Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A. | |||
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOOI-1900-01329-0) | |||
HERMITE, A Multi-Dimensional CENPD- July N.A. | |||
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A. | |||
15 Determining the Thermal Margin of a 161 -P-A 1986 Reactor Core (NO01 - 1301-01202) | |||
Page 7 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T. S ReS Title Report No. Rev Sm Re f#a Date CETOP-D Code Structures and Model- CEN- 1-P September N.A. | |||
ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3, (N001-1301-01185) | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A. | |||
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: | |||
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." | |||
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A. | |||
18 Improvement Program, (NO01-1 303- P-A 1986 02283) | |||
Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A. | |||
19 Flow Analysis, (NOOI - 1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A. | |||
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035) | |||
Verification of the Acceptability of a I- CEN-386- 0 August N.A. | |||
Pin Bumup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 I 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 limitsI shown in Figure 3.1.7-2.2 Regulating Groups I and 2 CEAs shall be maintained > fully withdrawnI' 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power 1 | |||
Regulating Group 3 shall be maintained > fully withdrawn. ' 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 Page 9 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 Regulating Group 4 position.c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | b) Regulating Group 5 position is maintained at least 10 inches lower than Page 9 of 27 | ||
No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | |||
3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 Regulating Group 4 position. | ||
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. | 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). | ||
Page 10 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 | 3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and | ||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN/ | >145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
........ ....................... | 3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1. | ||
3.2.1 - Linear Heat Rate (LHR) | |||
.. | The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
......... | 3.2.3 - Azimuthal Power Tilt (Tq) | ||
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1. | |||
/ | 3.2.4 - Departure From Nucleate Boiling Ratio (DNBR) | ||
..... .................. | COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1. | ||
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel. | |||
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE. | |||
(°F) | Page 10 of 27 | ||
O.RATION.-........ | |||
..................... | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 3.2.5 - Axial Shape Index (ASI) | ||
(350,4.0)0 | The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits: | ||
(*F)Page 13 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 | 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) | ||
i ................................ | -0.10*< ASI | ||
............... . | * 0.10 for power >20% | ||
3.3.12 - Boron Dilution Alarm System (BDAS) | |||
ACCEPTABLE OPERATION | 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. | ||
20_ 120 | 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 11 of 27 | ||
.. ..................... | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN | ||
/ l l.l. l . . .. . . | |||
................. | F I. . I .. . .. . F | ||
. 9.. 0 . . . . . . . . . | |||
-RATED THERMAL POWER IS ABOVE 95 %-COLSS IN SERVICE AND CEACS IN SERVICE-AZIMUTHAL POWER TILT IS LESS THAN 3.0 %-ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140. 1" WITHDRAWN BY RSPT INDICATION Page 15 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)1.0! , i | 6 | ||
for 0.7 ..power levels > 20%.CEA Group 3 must be withdrawn | .............. ........ ....................... * .. | ||
> 60" for z power > 0% and < 20%.0 AND 6 CEA Group 4 must be > fully withdrawn* | 5 ................ ......... (500,5.0) | ||
REGION OF ACCEPTABLE 2 OPERATION 4 | |||
> the 0.5 ... | 3 .................... . . | ||
> the ,W U group 5 TIL (TIL5) as indicated on the graph or by the equation: 0 ............., ........ , | .......... | ||
......... --------... | / ........ ; ECA;o A"E cj~I 2 | ||
i ....... i ........ ....... .... ..... . | ..*............... | ||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | ...... .................. | ||
Page 16 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)1.0 | ~REGION OF UNACCEPTABLE | ||
-............. | |||
> 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | - | ||
for power levels > 54.97%.CEA Group 4 must be withdrawn | OPERATION (350,10) 0 ... .... ... .... .... .... ... ..I. . . . . . . . . . . . ..... ..I .... ..... | ||
> | 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F) | ||
> the group 5 TIL (TIL5) as indicated on the graph or by the equations: | Page 12 of 27 | ||
TIL5 = (250.9" x Fractional Power) -80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power level > 75.00%). | |||
I I I I I I | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500,6.5)i 6 -.- | ||
* Fully Withdrawn (FW) is defined as> 147.75" (Pulse Counter) and > 145.25" (RSPT).No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | REGION OF ACCEPTABLE 5 ......... O.RATION.-........ | ||
Page 17 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER | S ..................... | ||
(350,4.0) 0 CIO REGION OF UNACCEPTABLE OPERATION 0 . . . . . . . . .I . . . . . . . .. . . .. . . . . .. , , . . , . . . . . ., . . | |||
0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F) | |||
-------... .... .......... | Page 13 of 27 | ||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 | |||
-------............ | *~~ ~ I*...... | ||
:.... . . . . .,,. . . .,. . | |||
...... | |||
............ | ..... .. ........... ................ ; ........ ,-- ---- (--... | ||
............ | o . .,o 0.0 (50%,(0.0)I 0 | ||
............ | ................... | ||
.. ... ............. ...... .-------. | .. ------............. | ||
.......... | ............. | ||
i ................................ ............... *.. . . . .oo.% -o.7. | |||
-0.5 0~ | |||
.......... | 'T 0 -1.0 z | ||
.......... | -1.5 ....... | ||
.......... | ...... ....... ............. TC REA O F .................................................. | ||
0 U ACCEPTABLE | |||
............. | -2.0 OPERATION 0 | ||
.......... | 0 -2.5 0 -3.0 | ||
-3.5 | |||
-4.0 (100%,4.4 (0%-4.4) mimi I ~L Jmi J-~L u J-~JL~ u I -~L .I -J~L .- | |||
I~ | |||
---------- | im L~ | ||
-------- ---- | -4.5 ~ ~4L 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 14 of 27 | |||
....... | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION* | |||
............. | 20_ 120 | ||
. | .. . . . . . . . . . . . . . . . . . . . . . I . . . . . . I . . . . . . | ||
: l. I 1 6<100% to | |||
>80% RTP 15 ............ 15 z | |||
12 12: *80% to 0 | |||
>70% RTP 10 ............ | |||
10 9, | |||
LLD 8 8- 70% to | |||
:E - | |||
>45% RTP LL 5 ............. | |||
5 0 | |||
0 | |||
. ..................... | |||
. . . . . .. I .............. ................. | |||
. ... | |||
.. .. . I . .. . .. | |||
. . . . . . . . . . . . . . . . I I I . . . . . . . i l l . . | |||
0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES | |||
* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED. | |||
* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION: | |||
- RATED THERMAL POWER IS ABOVE 95 % | |||
- COLSS IN SERVICE AND CEACS IN SERVICE | |||
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 % | |||
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140. 1" WITHDRAWN BY RSPT INDICATION Page 15 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 | |||
! !, ! i !"NOTE: | |||
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback. | |||
0.9 .. : . .. . - . To meet the Transient Insertion Limit (TIL) all conditions below must be met: | |||
CEA Groups 1 and 2 must be > fully 0.8 -- withdrawn* (see definition below) in MODE 1 and MODE 2. | |||
AND CEA Group 3 must be > fully withdrawn* for 0.7 . . power levels > 20%. | |||
CEA Group 3 must be withdrawn > 60" for z power > 0% and < 20%. | |||
0 AND 6 CEA Group 4 must be > fully withdrawn* for | |||
: 2:.4 z; : power levels > 70.87%. | |||
CEA Group 4 must be withdrawn > the 0.5 ',.. ... .. group 4 TIL (TIL4) as indicated on the graph or z: by the equation: | |||
TIL4 = (172.5" x Fractional Power)+ 25.5" | |||
- 4 "(for power > 20% and < 70.87%). | |||
z 0 AND U CEA Group 5 must be withdrawn > the | |||
,W U group 5 TIL (TIL5) as indicated on the graph or by the equation: | |||
: 0. . ........... 03.TIL5 ,........ , | |||
= (172.5" x Fractional Power)- 64.5" | |||
ýD 0 . * ,* (for powers > 37.39% and < 100%). | |||
0 .2 i. . " . . . '. ll . . . . -.--.-.---. ... ...... ... .... -...... | |||
----.. ... . ...... ..... .... . | |||
: : ' | |||
0.1 ... .*.. ...-.... ... .:...... .....:.. ... . ........... . ........--------... i .......i........ ....... ..... . . . .. | |||
0.0 GROUP 5 GROUP 3 GROUP 1 150*120 90 60 30 0 150*120 90 60 30 0 150*120 90 60 30 0 GROUP 4 GROUP 2 il0*lt 9+0 6+0 31o *) i10" i20 190 F60 F30 | |||
* CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 16 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE: | |||
... T. | |||
... .... .-----...... :See Footnote in Section 3.1.7 for applicability "following a Reactor Power Cutback. | |||
0.9 :To meet the Transient Insertion Limit (TIL) all conditions below must be met: | |||
CEA Groups 1 and 2 must be > fully 0.8 withdrawn* (see definition below) in MODE 1 and MODE 2. | |||
... | |||
.... ..... ....... AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%. | |||
.. | |||
.... ~-------- .. CEA Group 3 must be withdrawn > 60" for 0~ power > 0% and < 20%. | |||
r AND 0.6 F CEA Group 4 must be > fully withdrawn* for power levels > 54.97%. | |||
CEA Group 4 must be withdrawn >_the 0.5 1 group 4 TIL (TIL4) as indicated on the graph or 00 by the equation: | |||
TIL4 = (250.9" x Fractional Power) + 9.82" 0 (for power > 20% and < 54.97%). | |||
z 0.4 0z AND 0 a CEA Group 5 must be withdrawn > the U U. group 5 TIL (TIL5) as indicated on the graph or by the equations: | |||
0.3 20o TIL5 = (250.9" x Fractional Power) - 80.18" | |||
....... (for power > 31.96% and < 75.00%). | |||
TIL5 = 108" (for power level > 75.00%). | |||
.............................. | |||
0.2 --- | |||
-I 0.1 .... | |||
I I I I I I II I I I I | |||
0.0 GROUP 5 GROUP 3 GROUP I I I I I i i I I I I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 11*0" 10 9+0 6t 3+0 | |||
* 1I0" 120 i90 160 130 CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as> 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 17 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 . . . . . . . . .. M E E m w m 10.0 .......... -------------............. ............. | |||
------------- - | |||
I ........... | |||
20.0 .......... ........... - ------------------ ---- I........... | |||
30.0 ---------- .............-------------- I........................... .......... | |||
- ..---------.-.... ................ i.............. | |||
---- --- | |||
40.0 ---------- .......................... .............. | |||
......................... | |||
. .. . . .. .............. | |||
I ............. i.............. | |||
- -- ---- | |||
50.0 .......... -------------------- ....... ........... | |||
p 60.0 .......... ........................................ -------------------------- | |||
z 70.0 -------------......... | |||
TRANSIE.NT INSERTION LIMIT (75.0:INCRES) | TRANSIE.NT INSERTION LIMIT (75.0:INCRES) | ||
T " I I n ii OPERATION | ........... | ||
.................. | 0 T " I I n E | ||
80.0 .......... | |||
------------ ----------... ..... | ............ OR P-E-I------ IIo N............. | ||
............. | 90.0 ii OPERATION .................. | ||
............. | z 100.0 | ||
.............m6m...........mnm mmi...M -m mmm LONG TERM STEADY STATE INSERTION::LIMITS: | ............--UNACCEPTABLE | ||
(112.5 INCHES)........... | ............ ............. ............. RESTRICTED | ||
------------ ---... | |||
....... | --- --............*... ... | ||
B ............. | --..i. | ||
- | ... | ||
110.0 | |||
...........-------. ...----------- ----............. . . . . . . . . . . . . . . . . . . . . . ....... | |||
......m6m...........mnm mmi...M -m mmm LONG TERM STEADY STATE INSERTION::LIMITS: (112.5 INCHES) 120.0 ............ . ........... TA.. | |||
AC.............C.P B - - ............. | |||
B-........ | |||
LE......................... | LE......................... | ||
.......... | ............. | ||
........... :.............. :..............: ............. ............. ............. -- .............................. | |||
:..............: | ------------------.... | ||
............. | 130.0 S OPERATION AccEPTABLE 140.0 | ||
............. | ....--....--....- | ||
............. | .................... ------- .... .... ...........,.... ---------------- | ||
150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27 | |||
... ........................ | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 . . . . . . . . -.. . !. - *. rr . | |||
.................... | . . V . 1-. . . I - r I T 15.0 ............. .......... REGION-OF ............. | ||
UNACCEPTABLE OPERATION M | |||
.... .... ........ | 10.0 U-) | ||
5.0 REGION OF, kLCCEPTABL .EOPERATION 0.u -0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 CORE POWER LEVEL | |||
0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 | (% OF RATED THERMAL POWER) | ||
....... ...REGION-OF | Page 19 of 27 | ||
............. | |||
UNACCEPTABLE OPERATION M U-) | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 20 z7 0 | ||
u 15 2 | |||
........ ......... | Ii 10 0d 0. | ||
0 u | |||
................. | 5 0 | ||
...... .............. ....ACCEPTABLE OPERATION | 50 60 70 80 90 100 CORE POWER LEVEL | ||
-- -......... ...... .............. | (% OF RATED THERMAL POWER) | ||
Page 20 of 27 | |||
................ | PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 . . . . . . . . . 1 . . . . . . . . . illllilll ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 ................. | ||
............. | (0).06,2.38) 8 (0.1,2.38):: | ||
.0 UNACCEPTABýLE | ( | ||
........ ............... | ................. -- -. ........ | ||
OPERATION | . . . . .. ............... i................. | ||
--- ............... | 2.3 | ||
.. | (-01,2.28) z 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90% | ||
AT LEAST 1 CEAC OPERABLE IN 2.1 -.-.---- 1.93)................. | |||
......... | C.- | ||
CL ,EACH OPERABLE CPC-ClANNEL u- | |||
. . . . . ... ................ | |||
.. .... ........ ........" | - --- --- - | ||
........................... | (0.05,2.00) .. | ||
......... | (0. 1 2.. | ||
-- ------------ | . . ............. | ||
... | 2.0 ................ ............. | ||
.. ....................... | . ............... ................. | ||
.0 UNACCEPTABýLE 1.9 ........ ............... | |||
Jeffrey a m approving this C(7fl 4 Date 20 12.1822:24: | OPERATION --- ............... | ||
. . . ... ....... .... .... | |||
. .. | |||
I......... ...... | |||
I ii 1.8 lI. ..Il... . l.l l l i. .1 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 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 . . . . . . . . . 1 . . . . . . . . . . . . . . . . . . 1 . . . . . . . . . | |||
Page 6 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T. | ACCEPTABLE OPERATION ANY POWER LEVEL 3.5 | ||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(13-NOO1-0201-00026-1) | .................... | ||
P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for | BOTH CEACs INOPERABLE | ||
Arizona Public Service Company PWR NFM-005 1 August N.A.11 Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL | .. | ||
"INANY OPERABLE CPC ....... | |||
CHANNEL (0.1,3.41):: | |||
3.4 -..... 0.0.3.4..... . . . . | |||
HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | . . . . . . . -- | ||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (N00l -1301-01202) | . - | ||
Page 7 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A.16 ing Methods for San Onofre Nuclear 160(S)-P 1981 Generating Station Units 2 and 3, (NO01-1301-01185)"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) | . -. - | ||
Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003)17 and November"Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 -Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.18 Improvement Program, (NOO1 -1303- P-A 1986 02283) | . ......... | ||
Verification of the Acceptability of a 1- CEN-386- 0 August N.A.Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | . - | ||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 The cycle-specific operating limits for the specifications listed are presented below.3. .I -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 I 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 | - . -. -......... | ||
> fully withdrawn | - - - - - - - - - 7.......... | ||
' 3 while in Modes I and 2 (except while performing SR 3.1.5.3). | - - - -- . . . | ||
When > 20% power Regulating Group 3 shall be maintained | z 3.3 ... . .. . . ................ | ||
> fully withdrawn. | u (-0.1 ,3.27) 3.2 UNACCEPTABLE OPERATION | ||
. . ... . . . . . . . . . . | |||
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: | 3.1 | ||
.. . . . . . . . | |||
.. . . . . . . . . . . I. . .. . . . .. . . . . . . . . . | |||
30 ....I .... ................... ......... ......... | |||
........ 1 | |||
. . . . . . . . . I1 .. .. . . . . . . . | |||
I 1 . . . . . . . . | |||
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 23 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 MODE0 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 24 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 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 25 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 I 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 26 of 27 | |||
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 27 of 27 | |||
Enclosure PVNGS Unit 2 Core Operating Limits Report (COLR) | |||
Revision 19 | |||
PALO VERDE NUCLEAR GENERATING STATION (PVNGS) | |||
UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 I Effective December 20, 2013 I r | |||
Independent Reviewer Bod n ar, Dig~itallys(i~gned by Bodnar, War Z6432) | |||
Date DN: | |||
WatecnBodnar, (Z0632 Walter Walt e Walter ,/ *(zo632) so: ave reviewed this S(Z0643 Date0:02012.18 16:16:10 070 Responsible Section Leader Ash ton, LiJeffrey | |||
. | |||
signd0b3 Aston Digitally signed byAshton, Date */" DN cn=Ashton, Jeffrey | |||
* "C(Z03403) | |||
Jeffrey a m approving this C(7fl 4 Date 20 12.1822:24:41 | |||
*\*vv | |||
* i .07'00' Page 1 of 27 | |||
PVNGS UNIT 2 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 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) 11 3.9.1 Boron Concentration I1 Page 2 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service) | |||
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service) | |||
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service) | |||
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s) | |||
Operable) | |||
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel) | |||
Page 3 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keft'> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 27 | |||
PVNGS UNIT 2 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 27 | |||
PVNGS UNIT 2 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) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: | |||
T.S ReS Title Report No. Rev Date _L - | |||
Supp_ | |||
Re f#a CE Method for Control Element Assem- CENPD- N.A. January N.A. | |||
I bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1) | |||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A. | |||
2 Nuclear Design 266-P-A (13-NOOI - 1900-01412-0) | |||
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A. | |||
4 Uncertainties 356(V)-P-A (13-NOO1 - 1303-01747-2) | |||
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (13-NOOI - 1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOO1 - 1900-01192-3) | |||
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOOI-1900-01185-3) | |||
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A. | |||
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for: | |||
5.6.5.b.6. | |||
Page 6 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T. | |||
ReSS Title Report No. Rev Re fW Date Supp Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A. | |||
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6. | |||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A. | |||
(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A. | |||
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | |||
Arizona Public Service Company PWR NFM-005 1 August N.A. | |||
11 Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005) | |||
Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A. | |||
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOO1-1900-01329-0) | |||
HERMITE, A Multi-Dimensional CENPD- July N.A. | |||
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A. | |||
15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (N00l - 1301-01202) | |||
Page 7 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A. | |||
16 ing Methods for San Onofre Nuclear 160(S)-P 1981 Generating Station Units 2 and 3, (NO01-1301-01185) | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A. | |||
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: | |||
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." | |||
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A. | |||
18 Improvement Program, (NOO1 - 1303- P-A 1986 02283) | |||
Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A. | |||
19 Flow Analysis, (NOOI - 1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A. | |||
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035) | |||
Verification of the Acceptability of a 1- CEN-386- 0 August N.A. | |||
Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 The cycle-specific operating limits for the specifications listed are presented below. | |||
: 3. . I - 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 I 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 I and 2 (except while performing SR 3.1.5.3). When > 20% power 1 | |||
Regulating Group 3 shall be maintained > fully withdrawn. ' 3 1A 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 Page 9 of 27 PVNGS UNIT 2 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 (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | b) Regulating Group 5 position is maintained at least 10 inches lower than Page 9 of 27 | ||
No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | |||
3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 Regulating Group 4 position. | ||
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. | 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). | ||
Page 10 of 27 PVNGS UNIT 2 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 | 3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and | ||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 | >145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
........................ | 3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1. | ||
3.2.1 - Linear Heat Rate (LHR) | |||
.... ... | The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
3.2.3 - Azimuthal Power Tilt (Tq) | |||
(°F) | 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 10 of 27 | ||
...................... | |||
..................... | PVNGS UNIT 2 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: | |||
0 100 200 300 400 COLD LEG TEMPERATURE (TF) | COLSS OPERABLE | ||
.---...... | -0.18*< ASI *0.17 for power> 50% | ||
........ ... .. --S (50%, 0.o)-------------.... | -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 11 of 27 | ||
.............. | |||
................ | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 | ||
M T C -- A | 6 ....... .............. .0 . ... | ||
... ................. | 5 ................... ........................ | ||
-ACCEPTABLE OPERATION........................................ | : ................... | ||
----- .................. | ... -----(5----000,5.0) | ||
i................................... | REGION OF ACCEPTABLE 2 | ||
------------ | OPERATION 4 | ||
3 | |||
--................ | ... ....... ----------- ............------ | ||
.. ........... | REGION OF UNACCEPTABLE 2 | ||
............... | OPERATIO0N (350..0) 0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F) | ||
..........- | Page 12 of 27 | ||
...... ......... | |||
............. | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 | ||
--------------............. | (500,6.5): | ||
............. | 6 REGION OF ACCEPTABLE 5 ................-OP ER AT IO N -:......... . | ||
............... | 2 4 | ||
..................................... | (350,4.0) 0 3 I-. | ||
--............ | H REGION OF UNACCEPTABLE 2 .......... ........................ ....................... | ||
.. ................................ ..... .... .............-- | OPERATION | ||
... . . . . . . . . . -- --- | |||
......... | ............ | ||
.....-- ---------- | . . . . I . .. .. .... | ||
(100)%,-4.41 | .. . . . . . . . . . .. .. . ..... . . . .. | ||
.0%,-4.4) | ... | ||
....... | 0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (TF) | ||
....... ............ | Page 13 of 27 | ||
..... ....... | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0 -. ------ -- ----.............. . ---............... .. .. -- | ||
...../ | S (50%, 0.o) | ||
...................... | -0.5 - | ||
........... | -------------.... ................ ............. MTCAREAI -- -- --......... ................. . . . . . . . . . . . . . .......... .... | ||
............ .. ................. | _(10 T.Q., ,-... 2.. | ||
.......... | -1.0 z | ||
.......... | .... .............. .............. ................ M T C-- A RE A -OF ............................ ... ................. - | ||
-1.5 W | |||
-RATED THERMAL POWER IS ABOVE 95 %-COLSS IN SERVICE AND CEACS IN SERVICE-AZIMUTHAL POWER TILT IS LESS THAN 3.0 %-ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 15 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) | U ACCEPTABLE OPERATION | ||
-2.0 (100%,44, | |||
> | ........................................ ----- .................. i................................... | ||
for power levels > | -2.5 | ||
> | .------------ | ||
> the group | . . . . . . -- . .- .- .- .- -........ ........ ......................... --................ .. ........... ............... ..........- | ||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | F-0 | ||
Page 16 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER 1.0 | -3.0 | ||
. | :z 0 | ||
. . . ... | |||
....... withdrawn* (see definition below) in | ........... ............. - - - - - - - - - - - - --.......................... ............... | ||
for | . . . . . . . . . ............................ --............ | ||
> 60" for , power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | -3.5 | ||
for z power levels > 54.97%.CEA Group 4 must be withdrawn | .. . . .. . . . . . . . . . . . . . . . ..... . . -. - | ||
> the.group 4 TIL (TIL4) as indicated on the graph or | .... | ||
> the group 5 TIL (TIL5) as indicated on the graph or by the equations: | . --......... | ||
TIL5 = (250.9" x Fractional Power) -80.18" (for power? 31.96% and <75.00%).(L=108" (for power level | . .............-- | ||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | . . ...... ......... | ||
Page 17 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 | - - -.....-- | ||
- - - - - - - - --.... .... .... .. i ............ | |||
. | -4.0 (100)%,-4.41 | ||
.. .......... | .0%,-4.4) | ||
.......... | -4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL | ||
........ ............. | (% OF RATED THERMAL POWER) | ||
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit ....... | |||
Page 14 of 27 | |||
............. | |||
............ | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.5-1 CORE POWER REDUCTIO] AFTER CEA DEVIATION* | ||
.......... | m0 20....... | ||
61 100% to | |||
>80% RTP 15 -. -. ................. ....... ............ | |||
.......... | --------------........... 15 z | ||
..... | 0 r-12 12. *ý80% to | ||
.......... | >70% RTP 110 uw 101 9 10------.................. ..... ................/ ..... | ||
. | >45% RTP 5 / | ||
........... | 5-------- | ||
............................ | -- ------------------- . -.............................. ........... ......... | ||
............ | 5 | ||
..... ................. | |||
.......... | |||
---------- | .......... | ||
----------- | 0 | ||
........... | .. . . . . . , ,. | ||
. . . . I. . . . . ., | |||
0 10 20 30 40 50 60 TIME AFTER DE' VIATION, MINUTES | |||
(112.5 INCHES)............. | * WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED. | ||
: | * NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION: | ||
.... | - RATED THERMAL POWER IS ABOVE 95 % | ||
L ............. | - COLSS IN SERVICE AND CEACS IN SERVICE | ||
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 % | |||
.............. | - ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 15 of 27 | ||
.......... | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE: | ||
See Footnote in Section 3.1.7 for applicability Ifollowing | |||
.. . . . . a. .Reactor | |||
. . . . Power ' :.Cutback. | |||
T.*O . . . . . . . . . . . . . | |||
0.9 To meet the Transient Insertion Limit (TIL) all | |||
:conditions below must be met: | |||
CEA Groups 1 and 2 must be > fully 0.8 withdrawn* (see definition below) in MODE 1 and MODE 2. | |||
AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%. | |||
CEA Group 3 must be withdrawn > 60" for power > 0% and < 20%. | |||
0.6 AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%. | |||
CEA Group 4 must be withdrawn > the 0.5 group 4 TIL (TIL4) as indicated on the graph or by the equation: | |||
TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%). | |||
0 0.4 AND CEA Group 5 must be withdrawn > the group 5 TIL (TIL5) as indicated on the graph or by the equation: | |||
0.3 TIL5 = (172.5" x Fractional Power) - 64.5" (for powers > 37.39% and < 100%). | |||
0.2 * .. I . p p .~. ~ p ...... --- | |||
0.1 | |||
..... --- .......... ............. -----...... | |||
0.0 I I I I I I SIGROUP 5 GROUP 3 GROUP I I I I ','I I I I i i I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 I1ý0"*1I0 9+0 6+0 3+0 ý 1*0 120 ff90 V60 130 CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 16 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 in" NOTE: | |||
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback. | |||
0.9 ................. .................. 'To m eet the Transient Insertion Lim it (TIL) all | |||
---.--. | |||
conditions below must be met: | |||
CEA Groups 1 and 2 must be > fully 0.8 ----.------.----.---............. ....... withdrawn* (see definition below) in MO DE 1 and MODE 2. | |||
-r AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%. | |||
CEA Group 3 must be withdrawn > 60" for | |||
, power > 0% and < 20%. | |||
AND Lu 0.6 CEA Group 4 must be > fully withdrawn* for z power levels > 54.97%. | |||
CEA Group 4 must be withdrawn > the 0 .group 4 TIL (TIL4) as indicated on the graph or 0.5 the equation: | |||
gopby ru z Z* TIL4 = (250.9" x Fractional Power) + 9.82" 5 *:- *(for power > 20% and < 54.97%). | |||
------ . . AND 0.4 CEA Group 5 must be withdrawn > the U group 5 TIL (TIL5) as indicated on the graph or by the equations: | |||
0.3 TIL5 = (250.9" x Fractional Power) - 80.18" (for power? 31.96% and <75.00%). | |||
(L=108" (for power level 175.00%). | |||
0.2 ~P!~ -~*-- | |||
--- | |||
0.1 I I I I I I 0.0 SI a I I GROUP 5 GROUP 3 GROUP 1 I I I I I I I I I I I I I I I I I I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 ld0*l10 9+0 6t 3+0 ý It 1*0 20 190 F60 F30 | |||
* CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 17 of 27 | |||
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 | |||
. ......................................- I............... | |||
10.0 . .......... | |||
20.0 ........... | |||
30.0 .. .......... . .............. .. .......... | |||
----------------.... | |||
.!.............. ............--............................ ........... | |||
40.0 | |||
. . . ... ............. | |||
--------------............... | |||
: -- --- --- | |||
50.0 | |||
. . . .. ............. ............. ............. | |||
60.0 z 70.0 .TRANSIENT INERTION LIMIT (75.0::INCHES.) | |||
0 I I I 0 80.0 | |||
... | |||
.. . . | |||
.......... OPE RA T.IO N ............... | |||
90.0 PERA;U.TION. | |||
O...... ---------- | |||
,,:NACCEPTABLE z RESTRICTED 100.0 ----------- | |||
110.0 ........... | |||
......................... | |||
LONG TERM STEADY STATE INSERTIONULIMITS: (112.5 INCHES) 120.0 130.0 . ............ : PE AO..A...... ............. | |||
............................ - L............. .............. ............. .......... | |||
O)PERATION ACCEPTABLE | O)PERATION ACCEPTABLE | ||
------- .............. | -------.............. ....... ------- --------------..... :...... | ||
....... ------- | 140.0 | ||
.............. | ... ... ... .. . . . | ||
150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27 | |||
...I ...I . | |||
.......................... | PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 .. m 9 . . .. . . .. .. . . . m wK m 15.0 - --------------- REG IO N OF---- -- ....... | ||
.......................... | UNACCEPTABLE OPERATION 0 | ||
10.0 5.0 REGION OF LCCEPTABLE OPERATION | |||
. .. I . . . I . | |||
u.u 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 19 of 27 | |||
................. | |||
............. | PVNGS UNIT 2 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) | ||
................. | (95,20) 20 - ------------------------- .......................... | ||
z 0 | |||
0 15 . ......................... .................... | |||
.................. | 0z~ | ||
................. | 10 . ......................... | ||
------........... | 0 0 | ||
................ | 5I - -------------------- | ||
----------- | (70.0) I 0 | ||
50 60 70 80 90 100 CORE POWER LEVEL | |||
(% OF RATED THERMAL POWER) | |||
------- | Page 20 of 27 | ||
....... ..... ........................ | |||
... -------------- | PVNGS UNIT 2 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 I I II I I I I I I I I I I. .lm ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC ClltANNEL 2.4 ----------------- | ||
.................. | |||
................. | |||
- | ------........... ................ | ||
................. | ----------- | ||
(0..06,2.38) (0.1,2.38):: | |||
................. | 2.3 ý | ||
------ | --------- | ||
....... | |||
.......... | ..... | ||
.................................. | ........................ | ||
........... | ... | ||
-------------- ................. | |||
(-0.1,2.28) z 2.2 ................. | |||
................. | ------------------ I................. | ||
---- | ................. ................. | ||
---------- | |||
--------------- | ACCEftABLE OPERATION POWER AT OR ABOVE 90% | ||
.......... | z AT LEAST 1 CEAC OPERABLE IN u 2.1 -EACH 'OPERARL"EUT' CIIA r*ML' I ---------------- .......... | ||
.......... | CL u | ||
............................ | (-0--------- | ||
............. ................. | |||
... .. ..... . | ................. (O.Oý,2.00) 2.0 .................................. | ||
... | ........ | ||
.......... | |||
..... ................................... | 00 UNACCEPTAB E | ||
........... | - - - - --........ | ||
.. .. ... | I ......... | ||
1.9 O PE R A T ION --- | |||
------------------ | |||
............... | ... ................. ................. | ||
---------- | |||
............... | 1.8 ' | ||
............... | ......... ..... 1 .... ......... ......... ......... ......... .. | ||
-0.220 -0.15 -0.10 -0.05 0.00 0.10 0.15 0.05 0.20 CORE AVERAGE ASI Page 21 of 27 | |||
............... | |||
. | PVNGS UNIT 2 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 flr*rlrrll Tll,1111il ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 . ................ :---------- | ||
... .. ..... .e ... ... .......... ...-- --.-- ............... --------------- | |||
Bradey 06jý1m the author of this | INANY OPE RABLE CPC CHANNEL 3.4 --------------- .......... (0.0, 3.44..1) ................. 0.1,3.41):: | ||
Date: 2013.12.18 15:51:37 -07'00'Digitally signed by Bodnar, | ............... --------------- | ||
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 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: | z 3.3 .......... ............... ............... | ||
T.S ReS Title Report No. Rev Date Re f#a | (-0. 1i,3.27) 3.2 ............................ --------------- ............... . | ||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design 266-P-A (I 3-NOO1 -1900-01412-0) | .............. ..... ................................... ........... .. .. . ..- | ||
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September | 3.1 ------------ | ||
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOO1-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOOI -1900-01192-3) | ........ | ||
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOOI-1900-01185-3) | .... I... . . . . . . . . I.. | ||
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for: 5.6.5.b.6. | ... | ||
Page 6 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T._SS ReS Title Report No. Rev Date Ref#a | . .. . . . ..... . . . . ... | ||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(13-NOO1-0201-00026-1) | 3.0 , , I . | ||
P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for | . . | ||
Arizona Public Service Company PWR NFM-005 1 August N.A.Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL | . | ||
. | |||
.,,, | |||
.. .. . . . | |||
HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | .,,. . . . . . . .. i . i. . i. ....l. . . . . . . i. . l. . l . .. . . . . . . . | ||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (NOO1 -1301-01202) | -0. 20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27 | ||
Page 7 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A. | |||
Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003)17 and November"Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 -Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.18 Improvement Program, (NOOI -1303- P-A 1986 02283)19 Loss of Flow, C-E Methods for Loss of | PVNGS UNIT 2 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 23 of 27 | ||
Verification of the Acceptability of a I- CEN-386- 0 August N.A.Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 I 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 | PVNGS UNIT 2 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 MODE0 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 24 of 27 | ||
> fully | |||
When > 20% power Regulating Group 3 shall be maintained | PVNGS UNIT 2 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 Ž_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 25 of 27 | ||
> fully withdrawn.l' | |||
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: | PVNGS UNIT 2 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 26 of 27 | ||
PVNGS UNIT 2 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 27 of 27 | |||
Enclosure PVNGS Unit 3 Core Operating Limits Report (COLR) | |||
Revision 22 | |||
PALO VERDE NUCLEAR GENERATING STATION (PVNGS) | |||
UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 I Effective December 20, 2013 I Responsible Engineer Sutton Su It CDigitally signed by Sutton, 14Bradley J(Z06308) | |||
Date ADN: cn=Sutton, Bradley BradleyZ0630]8) | |||
Bradey 06jý1m the author of this J(Z06308,)- docum Date: 2013.12.18 15:51:37 -07'00' Independent Reviewer Date Bodnar, Walter Digitally signed by Bodnar, ijWalter ser 5(Z06432) od43 r z0)3 Walt S(Z DDN cn=Bodnar, Walter alter W soB4 3 rhave reviewed this S(Z064b S(ZO 4~- 0Date2010 | |||
-07'00' 12.18 16:16:54 Responsible Section Leader As-Io,,- | |||
A IsIho Digitally signed by Ashton, Jeffrey C(Z03403) | |||
Date / *.¢* | |||
... | |||
DN cn=Ashton, Jeffrey C(z03403) | |||
J*ell rey son lam approving this C(Z. 34 . -')7.-07'00' Date: 20t?2.18 22:26:00 Page 1 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Page Cover Page 2 | |||
Table of Contents List of Figures List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 11 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 11 Page 2 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Figures Description Pae Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service) | |||
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service) | |||
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service) | |||
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s) | |||
Operable) | |||
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel) | |||
Page 3 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 231 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffl 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde 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 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: | |||
T.S ReS Title Report No. Rev Date S11P-Re f#a CE Method for Control Element Assem- CENPD- N.A. January N.A. | |||
1 bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1) | |||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A. | |||
2 Nuclear Design 266-P-A (I 3-NOO1 -1900-01412-0) | |||
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 3 Steam Supply Reference Systems September 1983 2 CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A. | |||
4 Uncertainties 356(V)-P-A (1 3-NOO1 - 1303-01747-2) | |||
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOO1-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOOI - 1900-01192-3) | |||
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOOI-1900-01185-3) | |||
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A. | |||
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for: | |||
5.6.5.b.6. | |||
Page 6 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T._SS ReS Title Report No. Rev Date UW Ref#a Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A. | |||
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6. | |||
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A. | |||
(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A. | |||
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | |||
Arizona Public Service Company PWR NFM-005 1 August N.A. | |||
Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005) | |||
Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A. | |||
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A. | |||
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOOI-1900-01329-0) | |||
HERMITE, A Multi-Dimensional CENPD- July N.A. | |||
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A. | |||
15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (NOO1 - 1301-01202) | |||
Page 7 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A. | |||
ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3, (NOI-1301-01185) | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A. | |||
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: | |||
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)." | |||
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A. | |||
18 Improvement Program, (NOOI - 1303- P-A 1986 02283) | |||
CENPD- 0 June N.A. | |||
19 Loss of Flow, C-E Methods for Loss of Flow Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A. | |||
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO-0201-00035) | |||
Verification of the Acceptability of a I- CEN-386- 0 August N.A. | |||
Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042) | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 I and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power. | |||
3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1 ' 3 while in Modes I and 2 (except while performing SR 3.1.5.3). When > 20% power 3 | |||
Regulating Group 3 shall be maintained > fully withdrawn.l' 1A 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 Page 9 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Regulating Group 4 position.c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | b) Regulating Group 5 position is maintained at least 10 inches lower than Page 9 of 27 | ||
No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | |||
3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Regulating Group 4 position. | ||
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. | 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). | ||
Page 10 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 < | 3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and | ||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN I | >145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1. | |||
... | 3.2.1 - Linear Heat Rate (LHR) | ||
---- | The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
....................------------------ | 3.2.3 - Azimuthal Power Tilt (Tq) | ||
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1. | |||
3.2.4 - Departure From Nucleate Boiling Ratio (DNBR) | |||
COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1. | |||
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel. | |||
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE. | |||
Page 10 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 11 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN I | |||
---------- | |||
. . . . . .R | |||
. E I* O"i.......................... | |||
... | |||
---------- --.....(500,5.0 .---- | |||
REGION OF ACCEPTABLE OPERATION | |||
.......... | |||
.......... | |||
REGION OF H ------------------ | |||
UNACCEPTABLE | UNACCEPTABLE | ||
..................... | .... ... ....... ---- ---- --- | ||
. . . . . . . . . . . . . . . . . . . . . . . . . . l l l l l l l l l . . . . . . l l l l l l l . . . . . . . I 1 0 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F) | |||
.... | Page 12 of 27 | ||
. | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 | |||
............. | (500,6.5)i 6 . | ||
...... ...... | REGION OF ACCEPTABLE OP. RA TIO N ------------- | ||
!.........i.... .... ..... | |||
............... | ------...................... | ||
................ | . . ............ | ||
................ | '... | ||
................ | . . . . .. . .. | ||
..... | <2 | ||
.Z 4 (350,4.0) 0 3 | |||
. ........................................................................... ....................... ...................... | |||
F-REGION OF | |||
........ ............ ...... ........ ..... | . .................................................... | ||
.................. | UNACCEPTABLE r ...................... .............................................. | ||
. | 2 OPERATION I | ||
.. . ............ . .......... . . . L.L...... | |||
...... | |||
. . .. . ..L . .... | |||
.i 0 | |||
0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F) | |||
Page 13 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0. | |||
* ~ | |||
(o%,o.5) | |||
~....I .......... ...... . | |||
. :.... ' .- ME . . . . ':.. .' | |||
.............. | |||
.. . . | |||
i * ... ... ::....... (100% ,o1 . | |||
. . . ...... - - - - - --............. - - - - - --......... | |||
.............. ,.i ......... :............. | |||
:" l ~ l l . .. e 0.0 S(50%, 0.o) | |||
............--............... . . . . ............... | |||
-- -----............. ............................ ............. --------- (.Q% : .. | |||
-0.5 0~ | |||
. . . ... | |||
........... .. . . . . . ............... | |||
------ .... ............ | |||
........ | |||
. . . . . . .. ............................. ........... | |||
-1.0 0 | |||
...... :.............. | |||
------- ............. ..... ....... IMTC -ARlE A-OF ------------.............. ........................ | |||
-1.5 U ACCEPTABLE | |||
-------OPERATION | |||
. .. . . . . . . .. . . . . . .......................---............. ............. :............. *........................................... | |||
-2.0 0 | |||
-2.5 | |||
. . ... ............ ..................... .... --...... ........ ........................... . . ...... .................. . .. . . . . . . | |||
0 -3.0 02 | |||
-3.5 | |||
.... . .............. | |||
). ............ .......... .... .................... ....... .............. ............. ..............------------ | |||
-4.0 (100%,-4.41 | |||
.(0%,-4.4) . | |||
-lJ.LLIsz~I. I - I- U- I - mu - I - im | |||
-4.5 L~ L.L.LL..A. I .LLL..J. .1.. 1.L.J.L J LLL.L j .. LLLL I ~LL..A.. I LLL..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 14 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DE'VIATION* | |||
20 . . . .. . .I . . . .1 ___ 20 I'' | |||
16/100% to | |||
... ............ | |||
-------------....... ............. . ....... .......................... .............. / *"-- >80% RTP . | |||
.................... | |||
15 F- 15 0 | |||
12 12 <80% to - | |||
.........- ...... .-- ..........I .... | |||
>70% RTP 10 10 LL] *~9. | |||
8'. 8 f*70% to | |||
>45% RTP 5 5 0O1 I. . . . .. .. . . . ..... | |||
.. . . . . . . I . . . . . ... I .. I . .. . .. . . . | |||
ýi ; ; | |||
0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES | |||
* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED. | |||
* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION: | |||
- RATED THERMAL POWER IS ABOVE 95 % | |||
- COLSS IN SERVICE AND CEACS IN SERVICE | |||
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 % | |||
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 15 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 | |||
* See Footnote in Section 3.1.7 for applicability | |||
'following a Reactor Power Cutback. | |||
0.9 . , To meet the Transient Insertion Limit (TIL) all | |||
'conditions below must be met: | |||
CEA Groups 1 and 2 must be > fully 0.8 ...... withdrawn* (see definition below) in MODE 1 and MODE 2. | |||
AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels >20%. | |||
* CEA Group 3 must be withdrawn > 60" for power > 0% and < 20%. | |||
0.6 AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%. | |||
CEA Group 4 must be withdrawn > the 0.5 group 4 TIL (TIL4) as indicated on the graph or by the equation: | |||
TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%). | |||
z 0.4 AND CEA Group 5 must be withdrawn > the U group 5 TIL (TIL5) as indicated on the graph or by the equation: | |||
0.3 TIL5 = (172.5" x Fractional Power) - 64.5" (for powers > 37.39% and < 100%). | |||
0.2 i....... , - -- ....... | |||
i ........ | |||
0.1 0.0 1 1 1 I I I I I I GROUP 5 GROUP3 GROUP I I I I I I I I I I I I I I I I j I I 150*120 90 60 30 0 150*120 90 60 30 0 150*120 90 60 30 0 GROUP 4 GROUP 2 1*0"1t 9+0 6+0 3'0 ý 1J0" i20 190 t6 130 CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 16 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE: | |||
See Footnote in Section following a Reactor Power 3.1.7 for applicability Cutback. | |||
......... ..... i .... . T. | |||
..L o m eet the Trans ient Insertion L imit (T IL)a l 0.9 *,conditions,,L below must be met: | |||
Groups 1 and 2 must be >_fully OFCA | |||
.......................... q* wthdrawn* (see definition below) in MODE 1 0.8 | |||
.. . . ... . . . . . . . . . | |||
.. a..... | |||
',and MODE 2.>_20%.AND folpower levels I | |||
~CEA Group 3 must be_> fully withdrawn* for be withdrawn > 60" for 0.7 ..... CEA Group 3 must for | |||
_ fully withdrawn* | |||
F-, | |||
C S Group 4 must be 0.6 54.97%. | |||
>s 4 ed eo )i > the mustfntobe withdrawn O E1l CEA alevels | |||
........ .........S power wtd n Group on the graph or | |||
...... ------- conditi as indicated group 4 TIL (TIL4) 0.5 by the equation: Power) + 9.82 TIL4 = (250.9" x Fractional S (for power > 20% and < 54.97%). >_the | |||
* "-"... ...... CEA Group !. ANDbe withdrawn 5 must on the graph or z | |||
0 0.4 i group 5 TIL (TIL5) as indicated | |||
*-" by the equations: | |||
oI | |||
* TIL5 = (250.9" 31.96% and < 75.00%). | |||
x Fractional Power) - 80.18" 0.3 (for power> | |||
level 75.00%). | |||
= 108" >( power wTIL5 0.2 ! | |||
i 0.1 wi > the b | |||
I I I I t I 0.0 GROUP 5 t I 3 III GROUP GROUP I I I I I I I I I I I I I I 150" 120 90 60 30 0 150" 120 90 60 30 0 150"!120 90 60 30 0 GROUP 4 GROUP 2 1 9P0 6I O 3TI E0*1A0 ( C *0 I 20 190 60 130 CEA POSITION (INCHES WITHDRAWN) | |||
* Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT). | |||
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. | |||
Page 17 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 ---------- | |||
20.0 .......... | |||
i . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . | |||
30.0 ---------- | |||
40.0 ---------- | |||
-- - - .-. .-. .-. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . ..... . . .. . . . . . . | |||
50.0 .......... | |||
60.0 .......... | |||
u z 70.0 .......... | |||
0 I-80.0 ---------- | |||
u OPERA.. TION............. | |||
.......... | |||
-. | |||
0 ............. i............. *....... ...... ............. | |||
90.0 .......... .. O.. PERATION ------------- | |||
UNACCEPTABLE i RESTRICTED | |||
-2 100.0 ---------- | |||
:, | |||
110.0 .......... | |||
.... ... - | |||
... . -....... - | |||
LONG TERM STEADY STATE INSERTION:LIMITS:( 12.5 INCHES) 120.0 . ..........A ............. .. .. .............--.C CEP............- T A BL.. E................................................. | |||
......... .----... | |||
..... ....--...... ....... ... . . . . .*............. *............. | |||
------- -- ----------- .. ... .. -- | |||
------- ------ .............. . . . . | |||
130.0 b`PERATIONý ACCEPTABLE 140.0 . . ........ :: ....... .................................. | |||
. ..----- | |||
..----- ----- : ............. .............. ............. | |||
............. : .... . | |||
150.0 I | |||
*1 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 18 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 ---------------- ............... REGION OF ----------- | |||
UNACCEPTABLE OPERATION 0.. | |||
F-. 10.0 - S- S-5.0 a . - . - . - . - | |||
REGION OF kLcCEPTABLE OPERATION | |||
. .. . . - | |||
0.0 ................. Illlllll 1 1 1 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 19 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95,20) 20 - ----------------- | |||
-- ......... | |||
0 r-15 | |||
---i | |||
................................. | |||
-. .. | |||
...... .... | |||
..... . ... | |||
10 . ................................ | |||
0 u. | |||
5 ...... | |||
- ------------------------- | |||
(70,0) I 0 | |||
50 60 70 80 90 100 CORE POWER LEVEL | |||
(% OF RATED THERMAL POWER) | |||
Page 20 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 lllllllllllllllllUI ACCEPTABLE OPERATION ANY POWER LEVEL -. -- | |||
.--- . .. | |||
- -. . . . . . . .. | |||
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 , -. - - | |||
- -- . -.-- - - -, .. . | |||
(0.06,2.38) (0.1,2.38):: | |||
2.3 | |||
(-0.1,2.28) | |||
................. .................. ............ ..... *................., | |||
z 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90.i% | |||
AT LEAST I CEAC OPERABLE IN 2.1 E..ACH-OPERABLE CPC CIHANNEL: | |||
a.) | |||
- .* | |||
(0.05,2.00) (.1.2.00) | |||
. ..... . . . . . . ............. | |||
-- - - - - - | |||
2.0 | |||
-(-0.1,1.93) UNACCEPTABLE 1.9 ..................... OPE R A T ION ...................... | |||
. . . .I - - -....I - - -....I -.. .. .. | |||
Ig .. .... | |||
~ ~ | |||
.~ | |||
. | |||
... 1 . ..... | |||
. ... | |||
. | |||
1 | |||
. . . . . . . . . .. | |||
1 | |||
.IJ...J...J...I | |||
-0. | |||
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 . . . . . . . . . 1 . . . . . . . . . . .. . . I . . . . . I. . . . . I . . . . . | |||
lllll ACCEPTABLE :OPERATION ANY POWER LEVEL 3.5 ................... | |||
BOTH CEACs INOPERABLE | |||
--- --- ----- ... .... ........ | |||
IN A NY 0OPER BLE-CPC CHANNEL | |||
------------ .. ..... 3-4 1-. .............. . | |||
3.4 ............... | |||
. ... . . ... . . . . .. . . . . .. . . . . . . .. . . . . . i . ... . .. . . .. . . . . . | |||
3.3 ................ | |||
(-0.] 1:,3.27) 3.2 ................ | |||
UNACCEPTABLE OPERATION 3.1 ................ | |||
I.........--.............. .................. ............ i.... | |||
*1 A . . . . | |||
. .. . . . .. .. . . I . . . . . . . . . | |||
. . . . . . . . . .. .... . . . . . . . . . I. . . . . . .. . . . . . ..I .....1 , | |||
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 23 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 > Kefg > 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 24 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 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 25 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 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 26 of 27 | |||
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 27 of 27}} | |||
Revision as of 09:34, 4 November 2019
| ML14009A140 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/02/2014 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06813 TNW/RKR | |
| Download: ML14009A140 (85) | |
Text
Technical Specification 5.6.5d Saps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road Tonopah, AZ 85354 102-06813 TNW/RKR January 2, 2014 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, 3 Docket Nos. STN 50-528, 50-529 and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 23 Unit 2 Core Operating Limits Report (COLR), Revision 19 Unit 3 Core Operating Limits Report (COLR), Revision 22 Pursuant to PVNGS Technical Specifications, Section 5.6.5d, enclosed are the Units 1, 2 and 3 Core Operating Limits Report (COLR), Revisions 23, 19 and 22, respectively, which were made effective December 20, 2013. The following change was implemented in these COLR revisions:
Figure 3.1.5-1 revised to include an exemption to the immediate downpower requirement, allowed if certain prerequisites are met, for a single small CEA misalignment (greater than 6.6 inches but less than 9.9 inches) in the top 9.9 inches of the active fuel region.
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.
Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/KAR/hsc
Enclosures:
PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 23 PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 19 PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 22 cc: M. L. Dapas NRC Region IV Regional Administrator J. K. Rankin NRC NRR Project Manager for PVNGS A. E. George M. A. Brown NRC NRC NRR Project Manager Senior Resident Inspector for PVNGS DZA A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- San Onofre
- South Texas
- Wolf Creek
Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)
Revision 23
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 I Effective December 20, 2013 I I
Independent Reviewer Boate iar, fl, Digitally signed by Bodnar, Waiter S(Z06432)
Date Walter /*'°32) DN cn=Bodnar, Walter 5(Zox32 alte / a ve reviewed this S(Z064;. Date 20
-07'00'
~12.18 16:15:01 Responsible Section Leader to ,
As, Astn , jDigitallysigned efr.yCZ03403)by Ashton, Date DN cn=Ashton, Jeffrey IlC(Z03403)
Jeffrey anmapproving this S .Date, 20132.1822:23:06
-070 Page 1 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) I1 3.9.1 Boron Concentration I1 Page 2 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Figures Description Page Figure 3.1.1i-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffh 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S Ref#a Title Report No. Rev Date CE Method for Control Element Assem- CENPD- N.A. January N.A.
1 bly Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.
2 Nuclear Design 266-P-A (13-N001 - 1900-01412-0)
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 3 Steam Supply Reference Systems September 19832 CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.
4 Uncertainties 356(V)-P-A (13-NOO1-1303-01747-2)
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOI-1301-01228-0) I-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOO1-1900-01192-3)
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOO1 -1900-01185-3)
Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
Page 6 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T.S Ref#a Title Report No. Rev Date Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6.
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.
(13-N001-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
Arizona Public Service Company PWR NFM-005 1 August N.A.
Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)
Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. 1 Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOOI-1900-01329-0)
HERMITE, A Multi-Dimensional CENPD- July N.A.
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL)
TORC Code, A Computer Code for CENPD- N.A. April N.A.
15 Determining the Thermal Margin of a 161 -P-A 1986 Reactor Core (NO01 - 1301-01202)
Page 7 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T. S ReS Title Report No. Rev Sm Re f#a Date CETOP-D Code Structures and Model- CEN- 1-P September N.A.
ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3, (N001-1301-01185)
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.
18 Improvement Program, (NO01-1 303- P-A 1986 02283)
Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.
19 Flow Analysis, (NOOI - 1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)
Verification of the Acceptability of a I- CEN-386- 0 August N.A.
Pin Bumup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 I 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 limitsI shown in Figure 3.1.7-2.2 Regulating Groups I and 2 CEAs shall be maintained > fully withdrawnI' 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power 1
Regulating Group 3 shall be maintained > fully withdrawn. ' 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 9 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and
>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit of 13.1 kW/ft shall be maintained.
3.2.3 - Azimuthal Power Tilt (Tq)
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.
3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)
COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.
Page 10 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 < ASI < 0.17 for power > 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10*< ASI
- 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration > 3000 ppm.
Page 11 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN
/ l l.l. l . . .. . .
F I. . I .. . .. . F
. 9.. 0 . . . . . . . . .
6
.............. ........ ....................... * ..
5 ................ ......... (500,5.0)
REGION OF ACCEPTABLE 2 OPERATION 4
3 .................... . .
..........
/ ........ ; ECA;o A"E cj~I 2
..*...............
...... ..................
~REGION OF UNACCEPTABLE
-.............
-
OPERATION (350,10) 0 ... .... ... .... .... .... ... ..I. . . . . . . . . . . . ..... ..I .... .....
0 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F)
Page 12 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500,6.5)i 6 -.-
REGION OF ACCEPTABLE 5 ......... O.RATION.-........
S .....................
(350,4.0) 0 CIO REGION OF UNACCEPTABLE OPERATION 0 . . . . . . . . .I . . . . . . . .. . . .. . . . . .. , , . . , . . . . . ., . .
0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F)
Page 13 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5
- ~~ ~ I*......
- .... . . . . .,,. . . .,. .
......
..... .. ........... ................ ; ........ ,-- ---- (--...
o . .,o 0.0 (50%,(0.0)I 0
...................
.. ------.............
.............
i ................................ ............... *.. . . . .oo.% -o.7.
-0.5 0~
'T 0 -1.0 z
-1.5 .......
...... ....... ............. TC REA O F ..................................................
0 U ACCEPTABLE
-2.0 OPERATION 0
0 -2.5 0 -3.0
-3.5
-4.0 (100%,4.4 (0%-4.4) mimi I ~L Jmi J-~L u J-~JL~ u I -~L .I -J~L .-
I~
im L~
-4.5 ~ ~4L 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 14 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20_ 120
.. . . . . . . . . . . . . . . . . . . . . . I . . . . . . I . . . . . .
- l. I 1 6<100% to
>80% RTP 15 ............ 15 z
12 12: *80% to 0
>70% RTP 10 ............
10 9,
LLD 8 8- 70% to
- E -
5 0
0
. .....................
. . . . . .. I .............. .................
. ...
.. .. . I . .. . ..
. . . . . . . . . . . . . . . . I I I . . . . . . . i l l . .
0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- RATED THERMAL POWER IS ABOVE 95 %
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140. 1" WITHDRAWN BY RSPT INDICATION Page 15 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0
! !, ! i !"NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
0.9 .. : . .. . - . To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be > fully 0.8 -- withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be > fully withdrawn* for 0.7 . . power levels > 20%.
CEA Group 3 must be withdrawn > 60" for z power > 0% and < 20%.
0 AND 6 CEA Group 4 must be > fully withdrawn* for
- 2:.4 z; : power levels > 70.87%.
CEA Group 4 must be withdrawn > the 0.5 ',.. ... .. group 4 TIL (TIL4) as indicated on the graph or z: by the equation:
TIL4 = (172.5" x Fractional Power)+ 25.5"
- 4 "(for power > 20% and < 70.87%).
z 0 AND U CEA Group 5 must be withdrawn > the
,W U group 5 TIL (TIL5) as indicated on the graph or by the equation:
- 0. . ........... 03.TIL5 ,........ ,
= (172.5" x Fractional Power)- 64.5"
ýD 0 . * ,* (for powers > 37.39% and < 100%).
0 .2 i. . " . . . '. ll . . . . -.--.-.---. ... ...... ... .... -......
.. ... . ...... ..... .... .
- : '
0.1 ... .*.. ...-.... ... .:...... .....:.. ... . ........... . ........--------... i .......i........ ....... ..... . . . ..
0.0 GROUP 5 GROUP 3 GROUP 1 150*120 90 60 30 0 150*120 90 60 30 0 150*120 90 60 30 0 GROUP 4 GROUP 2 il0*lt 9+0 6+0 31o *) i10" i20 190 F60 F30
- CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 16 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:
... T.
... .... .-----...... :See Footnote in Section 3.1.7 for applicability "following a Reactor Power Cutback.
0.9 :To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be > fully 0.8 withdrawn* (see definition below) in MODE 1 and MODE 2.
...
.... ..... ....... AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%.
..
.... ~-------- .. CEA Group 3 must be withdrawn > 60" for 0~ power > 0% and < 20%.
r AND 0.6 F CEA Group 4 must be > fully withdrawn* for power levels > 54.97%.
CEA Group 4 must be withdrawn >_the 0.5 1 group 4 TIL (TIL4) as indicated on the graph or 00 by the equation:
TIL4 = (250.9" x Fractional Power) + 9.82" 0 (for power > 20% and < 54.97%).
z 0.4 0z AND 0 a CEA Group 5 must be withdrawn > the U U. group 5 TIL (TIL5) as indicated on the graph or by the equations:
0.3 20o TIL5 = (250.9" x Fractional Power) - 80.18"
....... (for power > 31.96% and < 75.00%).
TIL5 = 108" (for power level > 75.00%).
..............................
0.2 ---
-I 0.1 ....
I I I I I I II I I I I
0.0 GROUP 5 GROUP 3 GROUP I I I I I i i I I I I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 11*0" 10 9+0 6t 3+0
- 1I0" 120 i90 160 130 CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as> 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 17 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 . . . . . . . . .. M E E m w m 10.0 .......... -------------............. .............
-
I ...........
20.0 .......... ........... - ------------------ ---- I...........
30.0 ---------- .............-------------- I........................... ..........
- ..---------.-.... ................ i..............
---
40.0 ---------- .......................... ..............
.........................
. .. . . .. ..............
I ............. i..............
- -- ----
50.0 .......... -------------------- ....... ...........
p 60.0 .......... ........................................ --------------------------
z 70.0 -------------.........
TRANSIE.NT INSERTION LIMIT (75.0:INCRES)
...........
0 T " I I n E
80.0 ..........
............ OR P-E-I------ IIo N.............
90.0 ii OPERATION ..................
z 100.0
............--UNACCEPTABLE
............ ............. ............. RESTRICTED
---...
--- --............*... ...
--..i.
...
110.0
...........-------. ...----------- ----............. . . . . . . . . . . . . . . . . . . . . . .......
......m6m...........mnm mmi...M -m mmm LONG TERM STEADY STATE INSERTION::LIMITS: (112.5 INCHES) 120.0 ............ . ........... TA..
AC.............C.P B - - .............
B-........
LE.........................
.............
........... :.............. :..............: ............. ............. ............. -- ..............................
....
130.0 S OPERATION AccEPTABLE 140.0
....--....--....-
.................... ------- .... .... ...........,.... ----------------
150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 . . . . . . . . -.. . !. - *. rr .
. . V . 1-. . . I - r I T 15.0 ............. .......... REGION-OF .............
UNACCEPTABLE OPERATION M
10.0 U-)
5.0 REGION OF, kLCCEPTABL .EOPERATION 0.u -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 19 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 20 z7 0
u 15 2
Ii 10 0d 0.
0 u
5 0
50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
Page 20 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 . . . . . . . . . 1 . . . . . . . . . illllilll ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 .................
(0).06,2.38) 8 (0.1,2.38)::
(
................. -- -. ........
. . . . .. ............... i.................
2.3
(-01,2.28) z 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN 2.1 -.-.---- 1.93).................
C.-
CL ,EACH OPERABLE CPC-ClANNEL u-
. . . . . ... ................
- --- --- -
(0.05,2.00) ..
(0. 1 2..
. . .............
2.0 ................ .............
. ............... .................
.0 UNACCEPTABýLE 1.9 ........ ...............
OPERATION --- ...............
. . . ... ....... .... ....
. ..
I......... ......
I ii 1.8 lI. ..Il... . l.l l l i. .1 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 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 . . . . . . . . . 1 . . . . . . . . . . . . . . . . . . 1 . . . . . . . . .
ACCEPTABLE OPERATION ANY POWER LEVEL 3.5
....................
BOTH CEACs INOPERABLE
..
CHANNEL (0.1,3.41)::
3.4 -..... 0.0.3.4..... . . . .
. . . . . . . --
. -
. -. -
. .........
. -
- . -. -.........
- - - - - - - - - 7..........
- - - -- . . .
z 3.3 ... . .. . . ................
u (-0.1 ,3.27) 3.2 UNACCEPTABLE OPERATION
. . ... . . . . . . . . . .
3.1
.. . . . . . . .
.. . . . . . . . . . . I. . .. . . . .. . . . . . . . . .
30 ....I .... ................... ......... .........
........ 1
. . . . . . . . . I1 .. .. . . . . . . .
I 1 . . . . . . . .
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 23 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 MODE0 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 24 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 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 25 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> I hour 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 26 of 27
PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 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 27 of 27
Enclosure PVNGS Unit 2 Core Operating Limits Report (COLR)
Revision 19
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 I Effective December 20, 2013 I r
Independent Reviewer Bod n ar, Dig~itallys(i~gned by Bodnar, War Z6432)
Date DN:
WatecnBodnar, (Z0632 Walter Walt e Walter ,/ *(zo632) so: ave reviewed this S(Z0643 Date0:02012.18 16:16:10 070 Responsible Section Leader Ash ton, LiJeffrey
.
signd0b3 Aston Digitally signed byAshton, Date */" DN cn=Ashton, Jeffrey
- "C(Z03403)
Jeffrey a m approving this C(7fl 4 Date 20 12.1822:24:41
- \*vv
- i .07'00' Page 1 of 27
PVNGS UNIT 2 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 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) 11 3.9.1 Boron Concentration I1 Page 2 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keft'> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 27
PVNGS UNIT 2 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 27
PVNGS UNIT 2 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) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S ReS Title Report No. Rev Date _L -
Supp_
Re f#a CE Method for Control Element Assem- CENPD- N.A. January N.A.
I bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1)
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.
2 Nuclear Design 266-P-A (13-NOOI - 1900-01412-0)
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.
4 Uncertainties 356(V)-P-A (13-NOO1 - 1303-01747-2)
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (13-NOOI - 1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOO1 - 1900-01192-3)
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOOI-1900-01185-3)
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
Page 6 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T.
ReSS Title Report No. Rev Re fW Date Supp Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.
(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
Arizona Public Service Company PWR NFM-005 1 August N.A.
11 Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)
Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOO1-1900-01329-0)
HERMITE, A Multi-Dimensional CENPD- July N.A.
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL)
TORC Code, A Computer Code for CENPD- N.A. April N.A.
15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (N00l - 1301-01202)
Page 7 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A.
16 ing Methods for San Onofre Nuclear 160(S)-P 1981 Generating Station Units 2 and 3, (NO01-1301-01185)
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.
18 Improvement Program, (NOO1 - 1303- P-A 1986 02283)
Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.
19 Flow Analysis, (NOOI - 1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)
Verification of the Acceptability of a 1- CEN-386- 0 August N.A.
Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 The cycle-specific operating limits for the specifications listed are presented below.
- 3. . I - 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 I 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 I and 2 (except while performing SR 3.1.5.3). When > 20% power 1
Regulating Group 3 shall be maintained > fully withdrawn. ' 3 1A 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 9 of 27
PVNGS UNIT 2 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 (FW) is defined as >147.75" (Pulse Counter indication) and
>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit of 13.1 kW/ft shall be maintained.
3.2.3 - Azimuthal Power Tilt (Tq)
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.
3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)
COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.
Page 10 of 27
PVNGS UNIT 2 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:
-0.18*< ASI *0.17 for power> 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 < ASI < 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration > 3000 ppm.
Page 11 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7
6 ....... .............. .0 . ...
5 ................... ........................
- ...................
... -----(5----000,5.0)
REGION OF ACCEPTABLE 2
OPERATION 4
3
... ....... ----------- ............------
REGION OF UNACCEPTABLE 2
OPERATIO0N (350..0) 0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F)
Page 12 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7
(500,6.5):
6 REGION OF ACCEPTABLE 5 ................-OP ER AT IO N -:......... .
2 4
(350,4.0) 0 3 I-.
H REGION OF UNACCEPTABLE 2 .......... ........................ .......................
OPERATION
... . . . . . . . . . -- ---
............
. . . . I . .. .. ....
.. . . . . . . . . . .. .. . ..... . . . ..
...
0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (TF)
Page 13 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0 -. ------ -- ----.............. . ---............... .. .. --
S (50%, 0.o)
-0.5 -
.... ................ ............. MTCAREAI -- -- --......... ................. . . . . . . . . . . . . . .......... ....
_(10 T.Q., ,-... 2..
-1.0 z
.... .............. .............. ................ M T C-- A RE A -OF ............................ ... ................. -
-1.5 W
U ACCEPTABLE OPERATION
-2.0 (100%,44,
........................................ ----- .................. i...................................
-2.5
.------------
. . . . . . -- . .- .- .- .- -........ ........ ......................... --................ .. ........... ............... ..........-
F-0
-3.0
- z 0
. . . ...
........... ............. - - - - - - - - - - - - --.......................... ...............
. . . . . . . . . ............................ --............
-3.5
.. . . .. . . . . . . . . . . . . . . . ..... . . -. -
....
. --.........
. .............--
. . ...... .........
- - -.....--
- - - - - - - - --.... .... .... .. i ............
-4.0 (100)%,-4.41
.0%,-4.4)
-4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit .......
Page 14 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.5-1 CORE POWER REDUCTIO] AFTER CEA DEVIATION*
m0 20.......
61 100% to
>80% RTP 15 -. -. ................. ....... ............
........... 15 z
0 r-12 12. *ý80% to
>70% RTP 110 uw 101 9 10------.................. ..... ................/ .....
>45% RTP 5 /
5--------
-- ------------------- . -.............................. ........... .........
5
..... .................
..........
..........
0
.. . . . . . , ,.
. . . . I. . . . . .,
0 10 20 30 40 50 60 TIME AFTER DE' VIATION, MINUTES
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- RATED THERMAL POWER IS ABOVE 95 %
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 15 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE:
See Footnote in Section 3.1.7 for applicability Ifollowing
.. . . . . a. .Reactor
. . . . Power ' :.Cutback.
T.*O . . . . . . . . . . . . .
0.9 To meet the Transient Insertion Limit (TIL) all
- conditions below must be met:
CEA Groups 1 and 2 must be > fully 0.8 withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%.
CEA Group 3 must be withdrawn > 60" for power > 0% and < 20%.
0.6 AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.
CEA Group 4 must be withdrawn > the 0.5 group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).
0 0.4 AND CEA Group 5 must be withdrawn > the group 5 TIL (TIL5) as indicated on the graph or by the equation:
0.3 TIL5 = (172.5" x Fractional Power) - 64.5" (for powers > 37.39% and < 100%).
0.2 * .. I . p p .~. ~ p ...... ---
0.1
..... --- .......... ............. -----......
0.0 I I I I I I SIGROUP 5 GROUP 3 GROUP I I I I ','I I I I i i I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 I1ý0"*1I0 9+0 6+0 3+0 ý 1*0 120 ff90 V60 130 CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 16 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 in" NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
0.9 ................. .................. 'To m eet the Transient Insertion Lim it (TIL) all
---.--.
conditions below must be met:
CEA Groups 1 and 2 must be > fully 0.8 ----.------.----.---............. ....... withdrawn* (see definition below) in MO DE 1 and MODE 2.
-r AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%.
CEA Group 3 must be withdrawn > 60" for
, power > 0% and < 20%.
AND Lu 0.6 CEA Group 4 must be > fully withdrawn* for z power levels > 54.97%.
CEA Group 4 must be withdrawn > the 0 .group 4 TIL (TIL4) as indicated on the graph or 0.5 the equation:
gopby ru z Z* TIL4 = (250.9" x Fractional Power) + 9.82" 5 *:- *(for power > 20% and < 54.97%).
. . AND 0.4 CEA Group 5 must be withdrawn > the U group 5 TIL (TIL5) as indicated on the graph or by the equations:
0.3 TIL5 = (250.9" x Fractional Power) - 80.18" (for power? 31.96% and <75.00%).
(L=108" (for power level 175.00%).
0.2 ~P!~ -~*--
---
0.1 I I I I I I 0.0 SI a I I GROUP 5 GROUP 3 GROUP 1 I I I I I I I I I I I I I I I I I I 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0 GROUP 4 GROUP 2 ld0*l10 9+0 6t 3+0 ý It 1*0 20 190 F60 F30
- CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 17 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0
. ......................................- I...............
10.0 . ..........
20.0 ...........
30.0 .. .......... . .............. .. ..........
....
.!.............. ............--............................ ...........
40.0
. . . ... .............
...............
- -- --- ---
50.0
. . . .. ............. ............. .............
60.0 z 70.0 .TRANSIENT INERTION LIMIT (75.0::INCHES.)
0 I I I 0 80.0
...
.. . .
.......... OPE RA T.IO N ...............
90.0 PERA;U.TION.
O...... ----------
,,:NACCEPTABLE z RESTRICTED 100.0 -----------
110.0 ...........
.........................
LONG TERM STEADY STATE INSERTIONULIMITS: (112.5 INCHES) 120.0 130.0 . ............ : PE AO..A...... .............
............................ - L............. .............. ............. ..........
O)PERATION ACCEPTABLE
.............. ....... ------- --------------..... :......
140.0
... ... ... .. . . .
150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27
PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 .. m 9 . . .. . . .. .. . . . m wK m 15.0 - --------------- REG IO N OF---- -- .......
UNACCEPTABLE OPERATION 0
10.0 5.0 REGION OF LCCEPTABLE OPERATION
. .. I . . . I .
u.u 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 19 of 27
PVNGS UNIT 2 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)
(95,20) 20 - ------------------------- ..........................
z 0
0 15 . ......................... ....................
0z~
10 . .........................
0 0
5I - --------------------
(70.0) I 0
50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
Page 20 of 27
PVNGS UNIT 2 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 I I II I I I I I I I I I I. .lm ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC ClltANNEL 2.4 -----------------
..................
.................
........... ................
(0..06,2.38) (0.1,2.38)::
2.3 ý
.......
.....
........................
...
.................
(-0.1,2.28) z 2.2 .................
I.................
................. .................
ACCEftABLE OPERATION POWER AT OR ABOVE 90%
z AT LEAST 1 CEAC OPERABLE IN u 2.1 -EACH 'OPERARL"EUT' CIIA r*ML' I ---------------- ..........
CL u
(-0---------
............. .................
................. (O.Oý,2.00) 2.0 ..................................
........
..........
00 UNACCEPTAB E
- - - - --........
I .........
1.9 O PE R A T ION ---
... ................. .................
1.8 '
......... ..... 1 .... ......... ......... ......... ......... ..
-0.220 -0.15 -0.10 -0.05 0.00 0.10 0.15 0.05 0.20 CORE AVERAGE ASI Page 21 of 27
PVNGS UNIT 2 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 flr*rlrrll Tll,1111il ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 . ................ :----------
... .. ..... .e ... ... .......... ...-- --.-- ............... ---------------
INANY OPE RABLE CPC CHANNEL 3.4 --------------- .......... (0.0, 3.44..1) ................. 0.1,3.41)::
............... ---------------
z 3.3 .......... ............... ...............
(-0. 1i,3.27) 3.2 ............................ --------------- ............... .
.............. ..... ................................... ........... .. .. . ..-
3.1 ------------
........
.... I... . . . . . . . . I..
...
. .. . . . ..... . . . . ...
3.0 , , I .
. .
.
.
.,,,
.. .. . . .
.,,. . . . . . . .. i . i. . i. ....l. . . . . . . i. . l. . l . .. . . . . . . .
-0. 20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27
PVNGS UNIT 2 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 23 of 27
PVNGS UNIT 2 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 MODE0 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 24 of 27
PVNGS UNIT 2 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 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 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 25 of 27
PVNGS UNIT 2 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 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 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 26 of 27
PVNGS UNIT 2 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 27 of 27
Enclosure PVNGS Unit 3 Core Operating Limits Report (COLR)
Revision 22
PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 I Effective December 20, 2013 I Responsible Engineer Sutton Su It CDigitally signed by Sutton, 14Bradley J(Z06308)
Date ADN: cn=Sutton, Bradley BradleyZ0630]8)
Bradey 06jý1m the author of this J(Z06308,)- docum Date: 2013.12.18 15:51:37 -07'00' Independent Reviewer Date Bodnar, Walter Digitally signed by Bodnar, ijWalter ser 5(Z06432) od43 r z0)3 Walt S(Z DDN cn=Bodnar, Walter alter W soB4 3 rhave reviewed this S(Z064b S(ZO 4~- 0Date2010
-07'00' 12.18 16:16:54 Responsible Section Leader As-Io,,-
A IsIho Digitally signed by Ashton, Jeffrey C(Z03403)
Date / *.¢*
...
DN cn=Ashton, Jeffrey C(z03403)
J*ell rey son lam approving this C(Z. 34 . -')7.-07'00' Date: 20t?2.18 22:26:00 Page 1 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Page Cover Page 2
Table of Contents List of Figures List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 11 3.3.12 Boron Dilution Alarm System (BDAS) 3.9.1 Boron Concentration 11 Page 2 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Figures Description Pae Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Page 3 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 231 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffl 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde 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 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S ReS Title Report No. Rev Date S11P-Re f#a CE Method for Control Element Assem- CENPD- N.A. January N.A.
1 bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1)
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.
2 Nuclear Design 266-P-A (I 3-NOO1 -1900-01412-0)
Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 3 Steam Supply Reference Systems September 1983 2 CESSAR System 80, Docket No. STN 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.
4 Uncertainties 356(V)-P-A (1 3-NOO1 - 1303-01747-2)
System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOO1-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. I Analysis of CE and W Designed NSSS (13-NOOI - 1900-01192-3)
Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOOI-1900-01185-3)
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.
(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
Page 6 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T._SS ReS Title Report No. Rev Date UW Ref#a Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.
(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6.
Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.
(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.
1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
Arizona Public Service Company PWR NFM-005 1 August N.A.
Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)
Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.
12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.
Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (I 3-NOOI-1900-01329-0)
HERMITE, A Multi-Dimensional CENPD- July N.A.
14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL)
TORC Code, A Computer Code for CENPD- N.A. April N.A.
15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (NOO1 - 1301-01202)
Page 7 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T.S Ref#a Title Report No. Rev Date CETOP-D Code Structures and Model- CEN- 1-P September N.A.
ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3, (NOI-1301-01185)
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.
Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."
CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.
18 Improvement Program, (NOOI - 1303- P-A 1986 02283)
CENPD- 0 June N.A.
19 Loss of Flow, C-E Methods for Loss of Flow Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.
20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO-0201-00035)
Verification of the Acceptability of a I- CEN-386- 0 August N.A.
Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 8 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 I and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.
3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1 ' 3 while in Modes I and 2 (except while performing SR 3.1.5.3). When > 20% power 3
Regulating Group 3 shall be maintained > fully withdrawn.l' 1A 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 9 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and
>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit of 13.1 kW/ft shall be maintained.
3.2.3 - Azimuthal Power Tilt (Tq)
The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.
3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)
COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.
COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.
COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.
Page 10 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 < ASI*_ 0.17 for power> 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 < ASI *< 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration > 3000 ppm.
Page 11 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN I
. . . . . .R
. E I* O"i..........................
...
--.....(500,5.0 .----
REGION OF ACCEPTABLE OPERATION
..........
..........
REGION OF H ------------------
UNACCEPTABLE
.... ... ....... ---- ---- ---
. . . . . . . . . . . . . . . . . . . . . . . . . . l l l l l l l l l . . . . . . l l l l l l l . . . . . . . I 1 0 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F)
Page 12 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7
(500,6.5)i 6 .
REGION OF ACCEPTABLE OP. RA TIO N -------------
!.........i.... .... .....
......................
. . ............
'...
. . . . .. . ..
<2
.Z 4 (350,4.0) 0 3
. ........................................................................... ....................... ......................
F-REGION OF
. ....................................................
UNACCEPTABLE r ...................... ..............................................
2 OPERATION I
.. . ............ . .......... . . . L.L......
......
. . .. . ..L . ....
.i 0
0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F)
Page 13 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.
- ~
(o%,o.5)
~....I .......... ...... .
. :.... ' .- ME . . . . ':.. .'
..............
.. . .
i * ... ... ::....... (100% ,o1 .
. . . ...... - - - - - --............. - - - - - --.........
.............. ,.i ......... :.............
- " l ~ l l . .. e 0.0 S(50%, 0.o)
............--............... . . . . ...............
-- -----............. ............................ ............. --------- (.Q% : ..
-0.5 0~
. . . ...
........... .. . . . . . ...............
.... ............
........
. . . . . . .. ............................. ...........
-1.0 0
...... :..............
............. ..... ....... IMTC -ARlE A-OF ------------.............. ........................
-1.5 U ACCEPTABLE
OPERATION
. .. . . . . . . .. . . . . . .......................---............. ............. :............. *...........................................
-2.0 0
-2.5
. . ... ............ ..................... .... --...... ........ ........................... . . ...... .................. . .. . . . . . .
0 -3.0 02
-3.5
.... . ..............
). ............ .......... .... .................... ....... .............. ............. ..............------------
-4.0 (100%,-4.41
.(0%,-4.4) .
-lJ.LLIsz~I. I - I- U- I - mu - I - im
-4.5 L~ L.L.LL..A. I .LLL..J. .1.. 1.L.J.L J LLL.L j .. LLLL I ~LL..A.. I LLL..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 14 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DE'VIATION*
20 . . . .. . .I . . . .1 ___ 20 I
16/100% to
... ............
....... ............. . ....... .......................... .............. / *"-- >80% RTP .
....................
15 F- 15 0
12 12 <80% to -
.........- ...... .-- ..........I ....
>70% RTP 10 10 LL] *~9.
8'. 8 f*70% to
>45% RTP 5 5 0O1 I. . . . .. .. . . . .....
.. . . . . . . I . . . . . ... I .. I . .. . .. . . .
ýi ; ;
0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- RATED THERMAL POWER IS ABOVE 95 %
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 15 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0
- See Footnote in Section 3.1.7 for applicability
'following a Reactor Power Cutback.
0.9 . , To meet the Transient Insertion Limit (TIL) all
'conditions below must be met:
CEA Groups 1 and 2 must be > fully 0.8 ...... withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels >20%.
- CEA Group 3 must be withdrawn > 60" for power > 0% and < 20%.
0.6 AND CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.
CEA Group 4 must be withdrawn > the 0.5 group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).
z 0.4 AND CEA Group 5 must be withdrawn > the U group 5 TIL (TIL5) as indicated on the graph or by the equation:
0.3 TIL5 = (172.5" x Fractional Power) - 64.5" (for powers > 37.39% and < 100%).
0.2 i....... , - -- .......
i ........
0.1 0.0 1 1 1 I I I I I I GROUP 5 GROUP3 GROUP I I I I I I I I I I I I I I I I j I I 150*120 90 60 30 0 150*120 90 60 30 0 150*120 90 60 30 0 GROUP 4 GROUP 2 1*0"1t 9+0 6+0 3'0 ý 1J0" i20 190 t6 130 CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 16 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:
See Footnote in Section following a Reactor Power 3.1.7 for applicability Cutback.
......... ..... i .... . T.
..L o m eet the Trans ient Insertion L imit (T IL)a l 0.9 *,conditions,,L below must be met:
Groups 1 and 2 must be >_fully OFCA
.......................... q* wthdrawn* (see definition below) in MODE 1 0.8
.. . . ... . . . . . . . . .
.. a.....
',and MODE 2.>_20%.AND folpower levels I
~CEA Group 3 must be_> fully withdrawn* for be withdrawn > 60" for 0.7 ..... CEA Group 3 must for
_ fully withdrawn*
F-,
C S Group 4 must be 0.6 54.97%.
>s 4 ed eo )i > the mustfntobe withdrawn O E1l CEA alevels
........ .........S power wtd n Group on the graph or
...... ------- conditi as indicated group 4 TIL (TIL4) 0.5 by the equation: Power) + 9.82 TIL4 = (250.9" x Fractional S (for power > 20% and < 54.97%). >_the
- "-"... ...... CEA Group !. ANDbe withdrawn 5 must on the graph or z
0 0.4 i group 5 TIL (TIL5) as indicated
- -" by the equations:
oI
- TIL5 = (250.9" 31.96% and < 75.00%).
x Fractional Power) - 80.18" 0.3 (for power>
level 75.00%).
= 108" >( power wTIL5 0.2 !
i 0.1 wi > the b
I I I I t I 0.0 GROUP 5 t I 3 III GROUP GROUP I I I I I I I I I I I I I I 150" 120 90 60 30 0 150" 120 90 60 30 0 150"!120 90 60 30 0 GROUP 4 GROUP 2 1 9P0 6I O 3TI E0*1A0 ( C *0 I 20 190 60 130 CEA POSITION (INCHES WITHDRAWN)
- Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).
No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements.
Page 17 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 ----------
20.0 ..........
i . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .
30.0 ----------
40.0 ----------
-- - - .-. .-. .-. . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . ..... . . .. . . . . . .
50.0 ..........
60.0 ..........
u z 70.0 ..........
0 I-80.0 ----------
u OPERA.. TION.............
..........
-.
0 ............. i............. *....... ...... .............
90.0 .......... .. O.. PERATION -------------
UNACCEPTABLE i RESTRICTED
-2 100.0 ----------
- ,
110.0 ..........
.... ... -
... . -....... -
LONG TERM STEADY STATE INSERTION:LIMITS:( 12.5 INCHES) 120.0 . ..........A ............. .. .. .............--.C CEP............- T A BL.. E.................................................
......... .----...
..... ....--...... ....... ... . . . . .*............. *.............
-- ----------- .. ... .. --
------ .............. . . . .
130.0 b`PERATIONý ACCEPTABLE 140.0 . . ........ :: ....... ..................................
. ..-----
..----- ----- : ............. .............. .............
............. : .... .
150.0 I
- 1 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 18 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 ---------------- ............... REGION OF -----------
UNACCEPTABLE OPERATION 0..
F-. 10.0 - S- S-5.0 a . - . - . - . -
REGION OF kLcCEPTABLE OPERATION
. .. . . -
0.0 ................. Illlllll 1 1 1 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 19 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95,20) 20 - -----------------
-- .........
0 r-15
---i
.................................
-. ..
...... ....
..... . ...
10 . ................................
0 u.
5 ......
- -------------------------
(70,0) I 0
50 60 70 80 90 100 CORE POWER LEVEL
(% OF RATED THERMAL POWER)
Page 20 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 lllllllllllllllllUI ACCEPTABLE OPERATION ANY POWER LEVEL -. --
.--- . ..
- -. . . . . . . ..
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 , -. - -
- -- . -.-- - - -, .. .
(0.06,2.38) (0.1,2.38)::
2.3
(-0.1,2.28)
................. .................. ............ ..... *.................,
z 2.2 ACCEPTABLE OPERATION POWER AT OR ABOVE 90.i%
AT LEAST I CEAC OPERABLE IN 2.1 E..ACH-OPERABLE CPC CIHANNEL:
a.)
- .*
(0.05,2.00) (.1.2.00)
. ..... . . . . . . .............
-- - - - - -
2.0
-(-0.1,1.93) UNACCEPTABLE 1.9 ..................... OPE R A T ION ......................
. . . .I - - -....I - - -....I -.. .. ..
Ig .. ....
~ ~
.~
.
... 1 . .....
. ...
.
1
. . . . . . . . . ..
1
.IJ...J...J...I
-0.
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 . . . . . . . . . 1 . . . . . . . . . . .. . . I . . . . . I. . . . . I . . . . .
lllll ACCEPTABLE :OPERATION ANY POWER LEVEL 3.5 ...................
BOTH CEACs INOPERABLE
--- --- ----- ... .... ........
IN A NY 0OPER BLE-CPC CHANNEL
.. ..... 3-4 1-. .............. .
3.4 ...............
. ... . . ... . . . . .. . . . . .. . . . . . . .. . . . . . i . ... . .. . . .. . . . . .
3.3 ................
(-0.] 1:,3.27) 3.2 ................
UNACCEPTABLE OPERATION 3.1 ................
I.........--.............. .................. ............ i....
- 1 A . . . .
. .. . . . .. .. . . I . . . . . . . . .
. . . . . . . . . .. .... . . . . . . . . . I. . . . . . .. . . . . . ..I .....1 ,
-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 23 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 > Kefg > 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 24 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 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 25 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 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 26 of 27
PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 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 27 of 27