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{{#Wiki_filter:Technical Specification 5.6. | {{#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 | ||
==Dear Sirs:== | ==Dear Sirs:== | ||
Palo | Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road Tonopah, AZ 85354 | ||
==Subject:== | ==Subject:== | ||
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, | 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 | 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 | ||
Sincerely, Thomas N. | |||
==Enclosures:== | ==Enclosures:== | ||
PVNGS Unit 1 Core Operating Limits Report (COLR), Revision | 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 Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS DZA A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway | ||
* Comanche Peak | * Comanche Peak | ||
* Diablo Canyon | * Diablo Canyon | ||
| Line 35: | 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 | * 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 I fl, Digitally signed by Bodnar, Independent Reviewer Boate iar, Waiter S(Z06432)Date DN cn=Bodnar, Walter 5(Zox32 Walter alte / a ve reviewed this Date 20 ~12.18 16:15:01 S(Z064;. -07'00'Responsible Section Leader As, to , jDigitallysigned by Ashton, Astn , efr.yCZ03403) | ||
Date DN cn=Bodnar, | Date DN cn=Ashton, Jeffrey IlC(Z03403) | ||
-07'00'Responsible Section Leader As, to , jDigitallysigned by Ashton,Astn , efr.yCZ03403) | Jeffrey anm approving this S .Date, 20132.1822:23:06 | ||
Date DN cn=Ashton, | -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 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffh 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 24 25 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 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 26 27 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. | ||
Jeffrey anm approving | 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) | ||
DNBR Margin Operating Limit Based on the | 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) | ||
AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers | 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 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) | ||
T. | System 8 0 TM Inlet Flow Distribution Enclosure N.A. February I-P 4 (13-NOI-1301-01228-0) | ||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design 266-P-A(13-N001 | 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) | ||
-1900-01412-0) | 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) | ||
Safety Evaluation Report related to the NUREG- N.A. March 1983 | 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. | ||
System | 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. | ||
I-P to LD- | Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(1 3-N001-0201-00026-1) | ||
Calculative Methods for the CE Small CENPD- N.A. April 2-P- | P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for 1990 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | ||
-1900-01185-3) | 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 | ||
Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the | : 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 | ||
Page 6 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS | : 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 | ||
Fuel Rod Maximum Allowable Pressure CEN-372-N.A. May N.A.(1 3-N001-0201-00026-1) | : 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) | ||
P-A | HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | ||
Arizona Public Service Company PWR NFM-005 1 August N.A.Reactor Physics Methodology Using | 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) | ||
Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume I 282-P-A 2005(CENTS-TD MANUAL-VOL | Page 7 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 T. S ReS Title Report No. Rev Date Re f#a Sm 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, (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) | ||
: 1) Vols. | 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)19 Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.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) | ||
: 2) Vols. | 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) | ||
: 3) Vols. | : 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). | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161 -P-A | When > 20% power Regulating Group 3 shall be maintained | ||
Page 7 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.Nuclear Generating | |||
Issuance of Amendment | |||
Verification of the Acceptability of a I- CEN-386-0 August N.A.Pin Bumup Limit of 60 MWD/kgU for P-A | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6. | |||
The required | |||
> fully withdrawnI' 3 | |||
When > 20% | |||
> fully withdrawn. | > fully withdrawn. | ||
1' | 1' 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. | ||
In | 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 | 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). | ||
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 | No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
No further CEA withdrawal above FW is | 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. | ||
3.1.8 -Part Strength CEA Insertion | 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 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 | ||
3.2.3 -Azimuthal Power Tilt (Tq)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% | > 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/6 5.............. | ||
-Operate within | ........ ....................... | ||
Page 10 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS | * ..REGION OF ACCEPTABLE 2 cj~I l l. l. l .... .....F I I .. ... ....F 9 0 .........4 3 OPER.................... | ||
3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and | |||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS | |||
........ | |||
....................... | |||
* ..REGION | |||
..ATION................ | ..ATION................ | ||
......... | ......... | ||
(500,5.0) | (500,5.0).......... | ||
.......... | |||
/ ; ECA;o A"E .......... .................. | / ; ECA;o A"E .......... .................. | ||
..... .................. | ..... .................. | ||
--..................... | --..................... | ||
* ~REGION | * ~REGION OF UNACCEPTABLE OPERATION (350,10)2 0...........................I ...................I .........0 100 200 300 400 COLD LEG TEMPERATURE | ||
(°F) | (°F)500 600 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 S 5 ......... | ||
O.RATION.-........ | O.RATION.-........ | ||
..................... | ..................... | ||
(350,4.0) 0* | (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 | (*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 0.0-0.5 0~'T 0 z 0 U 0 0 0-1.0-1.5-2.0-2.5*~~ ~ :.... .....,,. ...,. ....... ..... .. ........... ................ | ||
.....,,. ...,. ....... ..... .. ........... ................ | ; ........ -- ----, --... ( o ..,o (50%,(0.0)I 0.. ................... | ||
; ........ | |||
-- ----, --... ( o ..,o(50%,(0.0)I 0.. ................... | |||
------............. | ------............. | ||
............. | ............. | ||
i ................................ | i ................................ | ||
............... | ............... .o o.% -o.7 ........ ...... ....... ............. | ||
.o o.% -o.7 ........ ...... ....... ............. | |||
T C R E A O F .................................................. | T C R E A O F .................................................. | ||
ACCEPTABLE OPERATION (100%,4.4 (0%-4.4)-3.0-3.5-4.0-4. | ACCEPTABLE OPERATION (100%,4.4 (0%-4.4)-3.0-3.5-4.0-4.5 mimi mi -u -u -.-.-im~ I ~L J ~4L J ~L J ~JL~ I ~L I J~L I ~ 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 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION* | ||
20_ | 20_ 120 15 z 0 LLD:E -LL 10 0............ | ||
............ | ............ | ||
............. | ............. | ||
.. .....................I ......I l. ......I | .. .....................I ......I l. ......I 1 6<100% to>80% RTP 12 12: 80% to>70% RTP 9, 8 8- 70% to>45% RTP........ ..................... | ||
I .............. | I .............. | ||
................. | ................. | ||
15 10 5 5 0.... .....I ......................I I I .......i l l ..0 10 20 30 40 TIME AFTER DEVIATION, MINUTES 50 60* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION: | |||
* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF | -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* | ||
-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 | for 0.7 ..power levels > 20%.CEA Group 3 must be withdrawn | ||
(see definition below) in MODE | > 60" for z power > 0% and < 20%.0 AND 6 CEA Group 4 must be > fully withdrawn* | ||
for: z; power levels > 70.87%.2:.4 : CEA Group 4 must be withdrawn | |||
> 60" | > 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 | ||
for: z; power levels > 70.87%.2:.4 :CEA Group 4 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 .. ......-. .......: .... .. .... .: ................. | ||
> | |||
TIL4 = (172.5" x Fractional Power)+ 25.5"-4 "(for power > 20% and < 70.87%).z 0 | |||
> the, | |||
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 ........ | 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) | ||
....... .... ..... ...0. | |||
* 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. | * 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 | 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 0.9 0.8 0~0 z 0 U 0.7 0.6 F 0.5 1 0z a.. .T. .. ..... .-- --- .. ........ ......... ......... ~ .. ..----- ---..r 00 U.20o.......NOTE::See Footnote in Section 3.1.7 for applicability"following a Reactor Power Cutback.:To meet the Transient Insertion Limit (TIL) all conditions below must be met: CEA Groups 1 and 2 must be > fully withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn* | ||
(see definition below) in MODE | for power levels > 20%.CEA Group 3 must be withdrawn | ||
> 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | |||
> 60" | for power levels > 54.97%.CEA Group 4 must be withdrawn | ||
>_ the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (250.9" x Fractional Power) + 9.82" (for power > 20% and < 54.97%).AND CEA Group 5 must be withdrawn | |||
>_ | > the group 5 TIL (TIL5) as indicated on the graph or by the equations: | ||
TIL4 = (250.9" x Fractional Power) + 9.82"(for power > 20% and < 54.97%). | TIL5 = (250.9" x Fractional Power) -80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power level > 75.00%).0.4 0.3 0.2 0.1 0.0.............................. | ||
> | I I I I I I----I....I I I I I I GROUP 5 I I GROUP 3 I I i i I GROUP 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 210 9+0 6t 3+0 1I0" 120 i 90 160 130 CEA POSITION (INCHES WITHDRAWN) | ||
TIL5 = (250.9" x Fractional Power) -80.18"(for power > 31.96% and < 75.00%).TIL5 = 108" (for power level > 75.00%).0. | |||
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. | * 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 | 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 p z 0 E z 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 1...........M E E m w m-..--------- | ||
.- .... ................ | .- .... ................ | ||
i.............. | i.............. | ||
| Line 155: | Line 124: | ||
-------............ | -------............ | ||
P-E-I- -- ---Io N ............. | P-E-I- -- ---Io N ............. | ||
OR | OR I UNACCEPTABLE | ||
............-- | ............-- | ||
............ | ............ | ||
| Line 173: | Line 142: | ||
-........... | -........... | ||
----------- | ----------- | ||
-------- | -------- ---- I ........... | ||
---- I ........... | |||
............. | ............. | ||
-------------- | -------------- | ||
| Line 193: | Line 161: | ||
........... | ........... | ||
TRANSIE.NT INSERTION LIMIT (75.0:INCRES) | TRANSIE.NT INSERTION LIMIT (75.0:INCRES) | ||
T " I I | T " I I n ii OPERATION | ||
.................. | .................. | ||
RESTRICTED | RESTRICTED | ||
| Line 199: | Line 167: | ||
............. | ............. | ||
............. | ............. | ||
.............m6m...........mnm mmi...M -m | .............m6m...........mnm mmi...M -m mmm LONG TERM STEADY STATE INSERTION::LIMITS: | ||
(112.5 INCHES)............ | (112.5 INCHES)............ | ||
AC.............C.P TA.. B-........ | AC.............C.P TA.. B-........ | ||
| Line 219: | Line 187: | ||
.... .... ........... | .... .... ........... | ||
,.... ---------------- | ,.... ---------------- | ||
0 0. | 0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 FRACTION OF RATED THERMAL POWER 0.2 0.1 0.0 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)........-. ! -* rr .......V .1-. ..I -r I T 20.0 15.0............. | ||
....... ...REGION-OF | ....... ...REGION-OF | ||
............. | ............. | ||
UNACCEPTABLE OPERATION | UNACCEPTABLE OPERATION M U-)10.0 5.0 REGION OF, kLCCEPTABL .E OPERATION 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 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 23 25 20 z7 0 u 2 Ii 0d 0.0 u 15 10 5 0 50 60 70 80 90 CORE POWER LEVEL (% OF RATED THERMAL POWER)100 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 2.4 2.3.........1 .........z C.-CL u-2.2 2.1 (-01,2.28) | ||
. | |||
-.-.----1.9 3)................. | -.-.----1.9 3)................. | ||
........ ................ | ........ ................ | ||
--------................ | --------................ | ||
................. | ................. | ||
...... .............. ....ACCEPTABLE OPERATION ANY POWER | ...... .............. ....ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0).06,2.38) ( 8................. | ||
( 8................. | -- -......... ...... ............... | ||
-- -......... | |||
...... ............... | |||
i................. | i................. | ||
ACCEPTABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN,EACH OPERABLE CPC-ClANNEL (0.05,2.00) | ACCEPTABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN ,EACH OPERABLE CPC-ClANNEL (0.05,2.00) | ||
................ | ................ | ||
............. | ............. | ||
.0 UNACCEPTABýLE | .0 UNACCEPTABýLE | ||
........ | ........ ............... | ||
............... | |||
OPERATION | OPERATION | ||
--- ............... | --- ............... | ||
| Line 245: | Line 209: | ||
....................... | ....................... | ||
(0.1,2.38):: | (0.1,2.38):: | ||
illllilll 2. | illllilll 2.0 1.9 1.8 1 lI ...Il ....l. l l l i. .I I i i-0.20 -0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4.........1 .........z u 3.3.... ...........ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE | ||
.. .... ........ ........"IN ANY OPERABLE CPC .......CHANNEL-.....0.0.3.4..... | .. .... ........ ........"IN ANY OPERABLE CPC .......CHANNEL-.....0.0.3.4..... | ||
........................... | ........................... | ||
......... | ......... | ||
-- ---------------------7.......... | -- ---------------------7.......... | ||
...,3.27)UNACCEPTABLE OPERATION | ...,3.27)UNACCEPTABLE OPERATION.....................I. ... ..... ..................1 .........(0.1,3.41):: | ||
.....................I. ... ..... ..................1 .........(0.1,3.41):: | |||
.. ....................... | .. ....................... | ||
(-0. | (-0.1 3.2 3.1 30........ 1 1 .........1 ............I ..................................................I ..I-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 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 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 Effective December 20, 2013 I I r Dig~itallys(i~gned by Bodnar, Independent Reviewer Bod n ar, War Z6432)Wate (Z0632 Date DN: cnBodnar, Walter Walter ,/ W alt e so: ave reviewed this Date0:0201 2.18 16:16:10 S(Z0643 070 LiJeffrey signd0b3 Aston Responsible Section Leader Ash .ton, Digitally signed byAshton, Date DN cn=Ashton, Jeffrey"C(Z03403) | ||
Jeffrey a m approving this C(7fl 4 Date 20 12.1822:24:41vv 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 Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keft'> 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 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 24 25 26 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 27 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. | |||
Jeffrey a m approving | 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: | ||
DNBR Margin Operating Limit Based on the | T.S ReS Title Report No. Rev Date Supp_Re f#a _ L -CE Method for Control Element Assem- CENPD- N.A. January N.A.I bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1) | ||
AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1 .1 Shutdown Margin (SDM) -Reactor Trip Breakers | 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) | ||
T. | 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) | ||
The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design 266-P-A(13-NOOI | 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) | ||
-1900-01412-0) | 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) | ||
Safety Evaluation Report related to the NUREG- N.A. March 1983 | 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. | ||
-1303-01747-2) | Page 6 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 T. S ReS Title Report No. Rev Date Supp Re fW 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. | ||
System | Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(13-NOO1-0201-00026-1) | ||
-1301-01228-0) 1 -P to LD- | P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for 1990 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | ||
-1900-01192-3) | 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 | ||
Calculative Methods for the CE Small CENPD- N.A. April 2-P- | : 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 | ||
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the | : 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 | ||
Page 6 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS | : 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) | ||
Fuel Rod Maximum Allowable Pressure CEN-372-N.A. May N.A.(13-NOO1-0201-00026-1) | HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | ||
P-A | 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) | ||
Arizona Public Service Company PWR NFM-005 1 August N.A.11 Reactor Physics Methodology Using | 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) | ||
Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume I 282-P-A 2005(CENTS-TD MANUAL-VOL | 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)19 Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.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) | ||
: 1) Vols. | 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) | ||
: 2) Vols. | : 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 limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained | ||
: 3) Vols. | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161-P-A | |||
Page 7 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.Nuclear Generating | |||
Issuance of Amendment | |||
Verification of the Acceptability of a 1- CEN-386-0 August N.A.Pin Burnup Limit of 60 MWD/kgU for P-A | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6. | |||
The required | |||
> fully withdrawn | > fully withdrawn | ||
' 3 | ' 3 while in Modes I and 2 (except while performing SR 3.1.5.3). | ||
When > 20% | When > 20% power Regulating Group 3 shall be maintained | ||
> fully withdrawn. | > fully withdrawn. | ||
1' | 1' 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. | ||
In | 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 | 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). | ||
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 | No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
No further CEA withdrawal above FW is | 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. | ||
3.1.8 -Part Strength CEA Insertion | 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 | ||
3.2.3 -Azimuthal Power Tilt (Tq)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% | > 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 5 2 4 3................... | ||
-Operate within | |||
Page 10 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS | |||
3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and | |||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS | |||
........................ | ........................ | ||
: ............... | : ............... | ||
.... ...REGION | .... ...REGION OF ACCEPTABLE OPERATION...........-----------............------....... .............. | ||
...........-----------............------....... .............. | .0 ....(5---- -----000,5.0)REGION OF UNACCEPTABLE OPERATIO0N (350..0)2 0 0 100 200 300 400 COLD LEG TEMPERATURE | ||
.0 ....(5---- -----000,5.0)REGION | (°F)500 600 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 6 5 REGION OF ACCEPTABLE | ||
(°F) | |||
................- | ................- | ||
O P E R A T IO N -: ......... | O P E R A T IO N -: ......... | ||
. | .2 0 H 4 3 I-.2 0.. ..........-- -- -(500,6.5): | ||
(350,4.0) | (350,4.0)REGION OF UNACCEPTABLE | ||
REGION | |||
.......... | .......... | ||
........................ | ........................ | ||
....................... | ....................... | ||
OPERATION | OPERATION...... ....... ..I ............. ..... ...... ............... | ||
...... ....... ..I ............. ..... ...... ............... | 0 100 200 300 400 COLD LEG TEMPERATURE (TF)500 600 Page 13 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 Revision 19 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0-0.5-1.0 z W U 0 F-0:z-1.5-MTCAREAI .... 2..(100%,44,-. ------ -- ----.............. | ||
.... 2..(100%,44, | |||
-. ------ -- ----.............. | |||
.---...... | .---...... | ||
........ | ........ ... .. --S (50%, 0.o)-------------.... | ||
... .. --S (50%, 0.o)-------------.... | |||
... ............. | ... ............. | ||
............. | ............. | ||
| Line 336: | Line 277: | ||
M T C -- A R E A -O F ............................ | M T C -- A R E A -O F ............................ | ||
... ................. | ... ................. | ||
-ACCEPTABLE OPERATION | -ACCEPTABLE OPERATION........................................ | ||
........................................ | |||
----- .................. | ----- .................. | ||
i................................... | i................................... | ||
------------ | ------------ | ||
-- -----.................... | -- -----.................... ........ ......................... | ||
........ | |||
......................... | |||
--................ | --................ | ||
.. ........... | .. ........... | ||
| Line 360: | Line 298: | ||
.....-- -------------.... .... .... .. i ............ | .....-- -------------.... .... .... .. i ............ | ||
(100)%,-4.41 | (100)%,-4.41 | ||
.0%,-4.4) | .0%,-4.4)-2.0-2.5-3.0-3.5-4.0-4.5 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 z 0 r-uw CORE POWER REDUCTIO]20.......1 5 -.-. --------------........... | ||
-2.0-2.5-3.0-3.5-4.0-4. | |||
20....... | |||
1 5 -.-. --------------........... | |||
................. | ................. | ||
....... ............ | ....... ............ | ||
101 5 /10------.................. | |||
..... ................ | ..... ................ | ||
...../5 ---------- -------------------61 100% to>80% | ...../5 ---------- -------------------61 100% to>80% RTP 12 12. ý80% to>70% RTP 9>45% RTP.-........ | ||
...................... | ...................... | ||
........... | ........... | ||
......... | ............ .. ................. | ||
... .. ................. | |||
.......... | .......... | ||
................ | ................15 AFTER CEA DEVIATION* | ||
m0 110 5 0 10 20 TIME AFTER DE'0........., ,. ..I. ....., 30 40 5 VIATION, MINUTES 0 60* 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: | |||
* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF | -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)0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 CEA Groups 1 and 2 must be > fully withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn* | ||
-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 | for power levels > 20%.CEA Group 3 must be withdrawn | ||
(see definition below) in MODE | > 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | ||
for power levels > 70.87%.CEA Group 4 must be withdrawn | |||
> 60" | > the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).AND CEA Group 5 must be withdrawn | ||
> the group 5 TIL (TIL5) as indicated on the graph or by the equation: TIL5 = (172.5" x Fractional Power) -64.5" (for powers > 37.39% and < 100%).......---.. .. .-- -.. .. ... .. ... ........ ...-- -- -......I .. ..........T ' :. .............NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all:conditions below must be met:* .. I .p p .~. ~ p I I I I I I GROUP 5 SI I GROUP 3 I I ','I GROUP 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) | |||
> | |||
TIL4 = (172.5" x Fractional Power) + 25.5"(for power > 20% and < 70.87%). | |||
> | |||
TIL5 = (172.5" x Fractional Power) -64.5"(for powers > 37.39% and < 100%).......---.. .. .-- -.. .. ... .. ... ........ ...-- -- -......I .. ..........T ' :. .............NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all:conditions below must be met:* .. I .p p .~. ~ | |||
* 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. | * 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 | 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 0.9 0.8 0.7 Lu 0 ru U 0.6 0.5 0.4 0.3 0.2 0.1 0.0-r z 5 (COLSS OUT OF SERVICE)in" NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.---.--. ................. | ||
.................. | .................. | ||
'To m eet the Transient Insertion Lim it (TIL) | 'To m eet the Transient Insertion Lim it (TIL) all conditions below must be met: CEA Groups 1 and 2 must be > fully----.------.----.---............. | ||
....... withdrawn* | ....... withdrawn* (see definition below) in M O DE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn* | ||
(see definition below) in M O DE | for power levels > 20%.CEA Group 3 must be withdrawn | ||
> 60" for , power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | |||
> 60" for, power > 0% and < 20%. | for z power levels > 54.97%.CEA Group 4 must be withdrawn | ||
> the.group 4 TIL (TIL4) as indicated on the graph or gopby the equation:TIL4 = (250.9" x Fractional Power) + 9.82"*:- power > 20% and < 54.97%).------ ..AND CEA Group 5 must be withdrawn | |||
> the.group 4 TIL (TIL4) as indicated on the graph | > 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 1 75.00%).-~*-- ~P!~I I I I I I---SI a I I GROUP 5 I I I I I I GROUP 3 I I I I I I GROUP 1 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 20 190 F60 F30 CEA POSITION (INCHES WITHDRAWN) | ||
TIL5 = (250.9" x Fractional Power) -80.18"(for power? 31.96% and <75.00%). | |||
(L=108" (for power level 1 75.00%).-~*-- ~P!~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. | * 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 | 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 10.0 20.0 30.0 z 0 0 z 40.0 50.0 60.0 70.0 80.0 90.0.......................................- | ||
I............... | I............... | ||
.----------------.... | .----------------.... | ||
| Line 419: | Line 347: | ||
............-- | ............-- | ||
............................ | ............................ | ||
........... | ............TRANSIENT INERTION LIMIT (75.0::INCHES.) | ||
.TRANSIENT INERTION LIMIT (75.0::INCHES.) | |||
I I I.......O...... PERA;U.TION. | I I I.......O...... PERA;U.TION. | ||
RESTRICTED | RESTRICTED | ||
| Line 426: | Line 353: | ||
----------- | ----------- | ||
........... | ........... | ||
100. | 100.0 110.0......................... | ||
120. | 120.0 130.0 LONG TERM STEADY STATE INSERTIONULIMITS: | ||
(112.5 INCHES)............. | (112.5 INCHES)............. | ||
: P E AO..A...... | : P E AO..A...... | ||
| Line 439: | Line 366: | ||
------- .............. | ------- .............. | ||
....... -------:...... --------------..... | ....... -------:...... --------------..... | ||
..............140. | ..............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 15.0..m 9 .............m w K m---------------- | ||
0 REG IO N O F ---- -- .......UNACCEPTABLE OPERATION 10.0 5.0 REGION OF LCCEPTABLE | |||
...I ...I .OPERATION u. | ...I ...I .OPERATION 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 20 z 0 0 0z~0 0 15-------------------------- | ||
.......................... | .......................... | ||
.......................... | .......................... | ||
| Line 447: | Line 374: | ||
(95,20).......................... | (95,20).......................... | ||
.................... | .................... | ||
(95,20) | (95,20)10 5I (70.0) I 0 50 60 70 80 CORE POWER LEVEL (% OF RATED THERMAL POWER)90 100 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 2.4 I I 2.3 ýz z u CL u 2.2 2.1 (-0.1,2.28) | ||
(-0--------- | (-0--------- | ||
................. | ................. | ||
| Line 453: | Line 380: | ||
................. | ................. | ||
------........ | ------........ | ||
I ......... | I .........I I I I I I I I I I I I .ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC ClltANNEL----------------- | ||
I I I I I I I I I I I I .ACCEPTABLE OPERATION ANY POWER | |||
----------------- | |||
.................. | .................. | ||
................. | ................. | ||
| Line 474: | Line 399: | ||
---------- | ---------- | ||
ACCEftABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN-EACH 'OPERARL"EUT' CIIA r*M L' I ---------------- | ACCEftABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN-EACH 'OPERARL"EUT' CIIA r*M L' I ---------------- | ||
.......... | ..........(O.Oý,2.00) | ||
(O.Oý,2.00) | |||
.................................. | .................................. | ||
.................. | .................. | ||
| Line 481: | Line 405: | ||
... O P E R A T IO N --- ................. | ... O P E R A T IO N --- ................. | ||
................. | ................. | ||
---------- | ----------.lm 2.0 1.9 1.8 '-0.2 1.................. .................................... ..20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 Tll,1111il 3.5 3.4 z 3.3................. | ||
. | |||
: ---------- | : ---------- | ||
--------------- | --------------- | ||
| Line 488: | Line 411: | ||
.......... | .......... | ||
............................ | ............................ | ||
ACCEPTABLE OPERATION ANY POWER | ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE | ||
... .. ..... .e ... ... .......... | ... .. ..... .e ... ... .......... | ||
...-- --.--IN ANY OPE R ABLE | ...-- --.--IN ANY OPE R ABLE CPC CHANNEL (0.0, 3.4 1) ................. | ||
4..1i,3.27).............. | 4..1i,3.27).............. | ||
..... ................................... | ..... ................................... | ||
| Line 504: | Line 427: | ||
............... | ............... | ||
.------------ | .------------ | ||
(-0.3. | (-0.3.2 3.1 3.0-0..,, , , I ...,,,...................... ... .......i i i l .........i l l ... .......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 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 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 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 _ 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 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 Effective December 20, 2013 I I Responsible Engineer Sutton C Digitally signed by Sutton, Su It 14 Bradley J(Z06308)Date ADN: cn=Sutton, Bradley BradleyZ0630]8) | ||
Date ADN: cn=Sutton, | Bradey 06jý1m the author of this docum J(Z06308,)- | ||
Bradey 06jý1m the author of | Date: 2013.12.18 15:51:37 -07'00'Digitally signed by Bodnar, Independent Reviewer Bodnar, Walt ser S(Z od43 r ijWalter 5(Z06432)DDN cn=Bodnar, Walter Date Walter z0)3 W alter soB 4 3 rhave reviewed this S(Z064b 0Date2010 12.18 16:16:54 S(ZO 4~- -07'00'Responsible Section Leader As-Io,,- Digitally signed by Ashton, A IsIho Jeffrey C(Z03403)Date DN cn=Ashton, Jeffrey/ ... C(z03403)rey son lam approving this)7. Date: 20t?2.18 22:26:00 C(Z 34 ..-' -07'00'Page 1 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 2 4 5 6 CORE Operating Limits 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 9 9 9 9 9 10 10 10 10 11 11 11 Page 2 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Pae 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Page 231 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffl 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 24 25 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 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 26 27 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. | ||
Date: 2013.12.18 15:51:37 | 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: | ||
-07'00'Digitally signed by Bodnar,Independent Reviewer Bodnar, Walt ser S(Z od43 | T.S ReS Title Report No. Rev Date Re f#a S11P-CE Method for Control Element Assem- CENPD- N.A. January N.A.1 bly Ejection Analysis 0190-A 1976 (13-NOO1-1301-01204-1) | ||
DDN cn=Bodnar, | 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) | ||
Digitally signed by Ashton,A IsIho Jeffrey C(Z03403) | 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 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) | ||
Date DN cn=Ashton, Jeffrey/ ... C(z03403)rey son lam approving this)7. Date: 20t?2.18 22:26: | 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) | ||
DNBR Margin Operating Limit Based on the | 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) | ||
AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1 .1 Shutdown Margin (SDM) -Reactor Trip Breakers | 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. | ||
T. | Page 6 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 T._SS ReS Title Report No. Rev Date Ref#a UW 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. | ||
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) | Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(13-NOO1-0201-00026-1) | ||
Safety Evaluation Report related to the NUREG- N.A. March 1983 | P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for 1990 Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9. | ||
System | 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 | ||
-1900-01192-3) | : 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 | ||
Calculative Methods for the CE Small CENPD- N.A. April 2-P- | : 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 | ||
Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the | : 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) | ||
Page 6 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS | HERMITE, A Multi-Dimensional CENPD- July N.A.14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL) | ||
Fuel Rod Maximum Allowable Pressure CEN-372-N.A. May N.A.(13-NOO1-0201-00026-1) | 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) | ||
P-A | 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.16 ing Methods for San Onofre Nuclear 160(S)-P 1981 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) | ||
Arizona Public Service Company PWR NFM-005 1 August N.A.Reactor Physics Methodology Using | 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 CENPD- 0 June N.A.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) | ||
Technical Description Manual for the CE-NPD 2 March N.A.12 CENTS CodeVolume 1 282-P-A 2005(CENTS-TD MANUAL-VOL | 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) | ||
: 1) Vols. | : 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 limits 1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained | ||
: 2) Vols. | > fully withdrawn 1' 3 while in Modes I and 2 (except while performing SR 3.1.5.3). | ||
: 3) Vols. | When > 20% power Regulating Group 3 shall be maintained | ||
> fully withdrawn.l' 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. | |||
TORC Code, A Computer Code for CENPD- N.A. April N.A.15 Determining the Thermal Margin of a 161-P-A | 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: | ||
Page 7 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS | |||
"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.Nuclear Generating | |||
Issuance of Amendment | |||
Verification of the Acceptability of a I- CEN-386-0 August N.A.Pin Burnup Limit of 60 MWD/kgU for P-A | |||
: a. Corresponds to the reference number specified in Technical Specification 5.6. | |||
The required | |||
> fully withdrawn 1' 3 | |||
When > 20% | |||
> fully withdrawn.l' | |||
In | |||
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 | 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). | ||
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 | No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements. | ||
3 Fully withdrawn (FW) is defined as >147.75" (Pulse Counter indication) and>145.25" (RSPT indication). | 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. | ||
No further CEA withdrawal above FW is | 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. | ||
3.1.8 -Part Strength CEA Insertion | 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 | ||
3.2.3 -Azimuthal Power Tilt (Tq)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% | > 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 H.............. | ||
-Operate within | |||
Page 10 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS | |||
3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and | |||
> 3000 ppm.Page 11 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS | |||
R E I O "i.......................... | R E I O "i.......................... | ||
...REGION | ...REGION OF ACCEPTABLE OPERATION---------- | ||
---------- | ---------- | ||
....................------------------.---- --.....(500,5.0 REGION OF UNACCEPTABLE | |||
....................------------------.---- --.....(500,5. | .. ............ -- ---------..........................l l l l l l l l l ......l l l l l l l .......I 1 0 100 200 300 400 COLD LEG TEMPERATURE | ||
.. ............ -- ---------..........................l l l l l l l l l ......l l l l l l l .......I | ('F)500 600 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 6 ....... ...<2.Z 4 0 3 F-(500,6.5)i REGION OF ACCEPTABLE O P. RA TIO N ------------- | ||
('F)500 | |||
------...................... | ------...................... | ||
! ................i ........... ...'... ....... ................ .(350,4.0) | ! ................i ........... ...'... ....... ................ .(350,4.0)............................................................................ | ||
............................................................................ | |||
....................... | ....................... | ||
...................... | ...................... | ||
REGION | REGION OF UNACCEPTABLE | ||
..................................................... | ..................................................... | ||
r ...................... | r ...................... | ||
.............................................. | .............................................. | ||
OPERATION | OPERATION............... | ||
............... | |||
........... | ........... | ||
......... ....L.L...... | ......... ....L.L...... | ||
..i ..L ..... | ..i ..L .....2 I 0 0 100 200 300 400 COLD LEG TEMPERATURE | ||
(*F) | (*F)500 600 Page 13 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 Revision 22 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0 0~0 U 0 0 02-0.5-1.0-1.5-2.0-2.5-3.0~ ~....I .:.... ' .- ME ....':.. .' .. ...... 0. ... .. ....... .(o%,o.5) .............. | ||
.............. | |||
i ... ...:: ....... (100% ,o1 .......... -------............. | i ... ...:: ....... (100% ,o1 .......... -------............. | ||
-------......... | -------......... | ||
| Line 583: | Line 485: | ||
:............. | :............. | ||
......... | ......... | ||
... ,.i e :" l ~ l | ... ,.i e :" l ~ l l S(50%, 0.o)............-- | ||
............... | ............... | ||
................... | ................... | ||
| Line 589: | Line 491: | ||
............................ | ............................ | ||
............. | ............. | ||
--------- | ---------( .Q % : ........ ........... | ||
( .Q % : ........ ........... | |||
.. .................... | .. .................... | ||
-- --- -.... ........ | -- --- -.... ........ ............ | ||
............ | |||
........ ............................. | ........ ............................. | ||
........... | ........... | ||
| Line 600: | Line 500: | ||
..... ....... IM T C -A RlE A -O F ------------.............. | ..... ....... IM T C -A RlE A -O F ------------.............. | ||
........................ | ........................ | ||
ACCEPTABLE OPERATION | ACCEPTABLE OPERATION... ........ ............................---............. | ||
... ........ ............................---............. | |||
-- -----............. | -- -----............. | ||
:............. | :............. | ||
...... ............ | ...... ............ | ||
..................... | ..................... | ||
.... --...... | .... --...... ........ ........................... | ||
........ | |||
........................... | |||
........ .................. | ........ .................. | ||
... ......... .... ............ ....... .. ..... ...... .. .. ........... ..... ...... .... ... ..............). ........ ..... ... ...........------------(100%,-4.41 | ... ......... .... ............ ....... .. ..... ...... .. .. ........... ..... ...... .... ... ..............). ........ ..... ... ...........------------(100%,-4.41 | ||
.(0%,-4.4) | .(0%,-4.4) | ||
.-3.5-4.0-I -I -U -I -mu -I - | .-3.5-4.0-I -I -U -I -mu -I -im lJ.LLIsz~I. | ||
L ~ L .L.LL..A. | L ~ L .L.LL..A. | ||
I .LLL..J. | I .LLL..J. .1 ..1.L.J.L J LLL.L j ..LLLL I ~LL..A.. I LLL..L.-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 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.5-1 Revision 22 CORE POWER REDUCTION AFTER CEA DE'20 .......I ....1 VIATION*___ 20 I''15 F-0 LL]10 5 16/100% to* >80% RTP-------------....... | ||
.1 ..1.L.J.L J LLL.L j ..LLLL I ~LL..A.. | |||
I LLL..L.-4. | |||
... ............ | ... ............ | ||
............. | ............. | ||
| Line 622: | Line 517: | ||
.............. | .............. | ||
/ "-- .................... | / "-- .................... | ||
.12 12 <80% to ->70% RTP...... .........................-- ---..................... .....I .....................*~9.8'. 8 f70% to>45% RTP......I ............ .. ......I ........I .. I ......... | .12 12 <80% to ->70% RTP...... .........................-- ---..................... .....I .....................*~9.8'. 8 f70% to>45% RTP......I ............ .. ......I ........I .. I .........15 10 5 0O1ý i ; ;0 10 20 30 40 TIME AFTER DEVIATION, MINUTES 50 60* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION: | ||
* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF | -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)z U 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0* See Footnote in Section 3.1.7 for applicability | ||
-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 | 'following a Reactor Power Cutback.., To meet the Transient Insertion Limit (TIL) all'conditions below must be met: CEA Groups 1 and 2 must be > fully...... withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn* | ||
'following a Reactor Power Cutback.., To meet the Transient Insertion Limit (TIL) all'conditions below must be met:CEA Groups 1 and 2 must be > fully...... withdrawn* | for power levels >20%.* CEA Group 3 must be withdrawn | ||
(see definition below) in MODE | > 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn* | ||
for power levels > 70.87%.CEA Group 4 must be withdrawn | |||
> 60" | > the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).AND CEA Group 5 must be withdrawn | ||
> the group 5 TIL (TIL5) as indicated on the graph or by the equation: TIL5 = (172.5" x Fractional Power) -64.5" (for powers > 37.39% and < 100%).---, i....... ....... i ........1 1 1 I I I I I I GROUP 5 I I I I I I GROUP3 I I I I I I GROUP 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 29+0 6+0 3'0 ý 1J0" i20 1 90 t6 130 CEA POSITION (INCHES WITHDRAWN) | |||
> | |||
TIL4 = (172.5" x Fractional Power) + 25.5"(for power > 20% and < 70.87%). | |||
> | |||
TIL5 = (172.5" x Fractional Power) -64.5"(for powers > 37.39% and < 100%).---, i....... | |||
....... i ........1 1 1 I I I 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. | * 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 | 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)F-, z 0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback...L .... ..... .....i .... .T. o m eet the Trans ient Insertion L im it (T IL) a l below must be met: ,,L OFCA Groups 1 and 2 must be >_ fully..........................wthdrawn* (see definition below) in MODE 1',and MODE 2.I AND~CEA Group 3 must be_> fully withdrawn* | ||
(see definition below) in MODE 1',and MODE 2.I AND~CEA Group 3 must be_> fully withdrawn* | for folpower levels >_ 20%...... CEA Group 3 must be withdrawn | ||
> 60" for.. ...... ......... ........ .a..... .S C Group 4 must be _ fully withdrawn* | |||
> 60" for.. ...... ......... | for S power levels > 54.97%.conditi CEA Group 4 must be withdrawn | ||
........ | > the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (250.9" x Fractional Power) + 9.82 S (for power > 20% and < 54.97%)."-" ...... !. ...AND CEA Group 5 must be withdrawn | ||
.a..... .S C Group 4 must be _ fully withdrawn* | >_ the i group 5 TIL (TIL5) as indicated on the graph orby the equations: | ||
...... ------- ........ ......... wtd a n s ed fnto eo )i O E1l oI TIL5 = (250.9" x Fractional Power) -80.18" (for power> 31.96% and < 75.00%).wTIL5 = 108" ( power level > 75.00%).I t I I I I b wi > the i!GROUP 5 I I I I I I GROUP 3 I t I II I GROUP I I I I I I I 150" 120 90 60 30 0 150" 120 90 60 30 0 150"!120 90 60 30 GROUP 4 GROUP 2 1 E0*1A0 9P0 6I 3TI O ( C 20 190 I 60 130 CEA POSITION (INCHES WITHDRAWN) 0* 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 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 22 u z 0 u 0 I-0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0---------- | ||
TIL4 = (250.9" x Fractional Power) + 9. | |||
>_ | |||
...... ------- ........ | |||
......... | |||
wtd a n s ed fnto eo )i O | |||
Page 17 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS | |||
.......... | .......... | ||
---------- | ---------- | ||
| Line 663: | Line 547: | ||
.. .......... | .. .......... | ||
-.UNACCEPTABLE i............. | -.UNACCEPTABLE i............. | ||
i............. | i............. ...... ............. | ||
...... ............. | :,-2 i .................... ................ .........................-------....................................... ..............O.. .. PERATION ------------- | ||
:,- | |||
------------- | |||
RESTRICTED | RESTRICTED | ||
-.... -... ... .-.......LONG TERM STEADY STATE INSERTION:LIMITS:( | -.... -... ... .-.......LONG TERM STEADY STATE INSERTION:LIMITS:( 12.5 INCHES)...........A C C E P T A B L E ............................ ..--. ............- .. ...................................... .............. ...... .----... ..... ....--...... | ||
12.5 INCHES)...........A C C E P T A B L E ............................ ..--. ............- .. ...................................... .............. ...... .----... | |||
..... ....--...... | |||
... .... ... .... | ... .... ... .... | ||
--------- ----------- | --------- ----------- | ||
.. ... .. -- ------- ------............. | .. ... .. -- ------- ------............. | ||
.....b`PERATIONý ACCEPTABLE | .....b`PERATIONý ACCEPTABLE | ||
.. ... ..----- ----- ........ | .. ... ..----- ----- ........ :: ....... .................................. | ||
:: ....... .................................. | |||
----- ............. | ----- ............. | ||
: ............. | : ............. | ||
.............. | .............. | ||
: ............. | : ............. | ||
.....* | .....*1 I 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 FRACTION OF RATED THERMAL POWER 0.2 0.1 0.0 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---------------- | ||
............... | ............... | ||
0..F-.REGION OF ----------- | 0..F-.REGION OF ----------- | ||
UNACCEPTABLE OPERATION 10.0-S -S -5. | UNACCEPTABLE OPERATION 10.0-S -S -5.0 REGION OF.....-a .-.-.-.-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 20 0 r-0 u.15------------------ | |||
-- ......... | -- .......................................... | ||
................................. | |||
................................. | ................................. | ||
-------------------------- | -------------------------- | ||
......(95,20)----------........... .........i ... ................... ...(70,0) | ......(95,20)----------........... .........i ... ................... ...(70,0) I 10 5 0 50 60 70 80 CORE POWER LEVEL (% OF RATED THERMAL POWER)90 100 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 2.4 2.3 z a.)2.2 2.1-, ...-----------, ...(-0.1,2.28) | ||
--(-0.1,1.93) | --(-0.1,1.93) | ||
ACCEPTABLE OPERATION ANY POWER | ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0.06,2.38) | ||
................. | ................. | ||
.................. | .................. | ||
............ | ............ | ||
..... | ..... ACCEPTABLE OPERATION POWER AT OR ABOVE 90.i%AT LEAST I CEAC OPERABLE IN E..ACH-OPERABLE CPC CIHANNEL: (0.05,2.00) | ||
ACCEPTABLE OPERATION POWER AT OR ABOVE 90.i%AT LEAST I CEAC OPERABLE | |||
(0.05,2.00) | |||
UNACCEPTABLE | UNACCEPTABLE | ||
..................... | ..................... | ||
| Line 706: | Line 582: | ||
(.1.2.00) | (.1.2.00) | ||
............. | ............. | ||
...... ......-------2. | ...... ......-------2.0 1.9 Ig.. .... ... 1 ...... ... 1 1.~ ~ ~ .............. .IJ...J...J...I | ||
-0.-0.20-0.15 -0.10 -0.05 0.00 0. | -0.-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4.........1 .........3.3................... | ||
............... | ............... | ||
................ | ................ | ||
| Line 713: | Line 589: | ||
................ | ................ | ||
.....I .....I .....I .....ACCEPTABLE | .....I .....I .....I .....ACCEPTABLE | ||
: OPERATION ANY POWER | : OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE | ||
--- --- ----- ... .... ........IN A NY 0OPER BLE- | --- --- ----- ... .... ........IN A NY 0OPER BLE-CPC CHANNEL------------ | ||
3-4 1-. .. ................... | 3-4 1-. .. ................... | ||
........ ............ ...... ........ .....i .... ... .... .....1:,3.27)UNACCEPTABLE OPERATION I.........--.............. | ........ ............ ...... ........ .....i .... ... .... .....1:,3.27)UNACCEPTABLE OPERATION I.........--.............. | ||
.................. | .................. | ||
............ | ............ | ||
i....lllll(-0.]3. | i....lllll (-0.]3.2 3.1*1 A.........I .........I ...................................I ................1 ,-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 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 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 17:35, 13 July 2018
| ML14009A140 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/02/2014 |
| From: | Weber T N 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 102-06813 TNW/RKR January 2, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road Tonopah, AZ 85354
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 J. K. Rankin A. E. George M. A. Brown NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC NRR Project Manager NRC 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 Effective December 20, 2013 I I I fl, Digitally signed by Bodnar, Independent Reviewer Boate iar, Waiter S(Z06432)Date DN cn=Bodnar, Walter 5(Zox32 Walter alte / a ve reviewed this Date 20 ~12.18 16:15:01 S(Z064;. -07'00'Responsible Section Leader As, to , jDigitallysigned by Ashton, Astn , efr.yCZ03403)
Date DN cn=Ashton, Jeffrey IlC(Z03403)
Jeffrey anm approving 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 Figure 3.1.1i-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 23 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffh 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 24 25 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 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 26 27 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 Steam Supply Reference Systems September 3 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.(1 3-N001-0201-00026-1)
P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.10 Scherer (CE), ("Acceptance for 1990 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 Date Re f#a Sm 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, (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)19 Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.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 Regulating Group 3 shall be maintained
> fully withdrawn.
1' 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted.
In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
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: 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 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN/6 5..............
........ .......................
- ..REGION OF ACCEPTABLE 2 cj~I l l. l. l .... .....F I I .. ... ....F 9 0 .........4 3 OPER....................
..ATION................
.........
(500,5.0)..........
/ ; ECA;o A"E .......... ..................
..... ..................
--.....................
- ~REGION OF UNACCEPTABLE OPERATION (350,10)2 0...........................I ...................I .........0 100 200 300 400 COLD LEG TEMPERATURE
(°F)500 600 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 S 5 .........
O.RATION.-........
.....................
(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 0.0-0.5 0~'T 0 z 0 U 0 0 0-1.0-1.5-2.0-2.5*~~ ~ :.... .....,,. ...,. ....... ..... .. ........... ................
- ........ -- ----, --... ( o ..,o (50%,(0.0)I 0.. ...................
.............
.............
i ................................
............... .o o.% -o.7 ........ ...... ....... .............
T C R E A O F ..................................................
ACCEPTABLE OPERATION (100%,4.4 (0%-4.4)-3.0-3.5-4.0-4.5 mimi mi -u -u -.-.-im~ I ~L J ~4L J ~L J ~JL~ I ~L I J~L I ~ 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 1 CORE OPERATING LIMITS REPORT Revision 23 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20_ 120 15 z 0 LLD:E -LL 10 0............
............
.............
.. .....................I ......I l. ......I 1 6<100% to>80% RTP 12 12: 80% to>70% RTP 9, 8 8- 70% to>45% RTP........ .....................
I ..............
.................
15 10 5 5 0.... .....I ......................I I I .......i l l ..0 10 20 30 40 TIME AFTER DEVIATION, MINUTES 50 60* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.* 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: z; power levels > 70.87%.2:.4 : 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 0.9 0.8 0~0 z 0 U 0.7 0.6 F 0.5 1 0z a.. .T. .. ..... .-- --- .. ........ ......... ......... ~ .. ..----- ---..r 00 U.20o.......NOTE::See Footnote in Section 3.1.7 for applicability"following a Reactor Power Cutback.:To meet the Transient Insertion Limit (TIL) all conditions below must be met: CEA Groups 1 and 2 must be > fully withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn*
for power levels > 20%.CEA Group 3 must be withdrawn
> 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn*
for power levels > 54.97%.CEA Group 4 must be withdrawn
>_ the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (250.9" x Fractional Power) + 9.82" (for power > 20% and < 54.97%).AND CEA Group 5 must be withdrawn
> the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) -80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power level > 75.00%).0.4 0.3 0.2 0.1 0.0..............................
I I I I I I----I....I I I I I I GROUP 5 I I GROUP 3 I I i i I GROUP 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 210 9+0 6t 3+0 1I0" 120 i 90 160 130 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 p z 0 E z 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 1...........M E E m w m-..---------
.- .... ................
i..............
... .... ..............
I .............
i..............
............
P-E-I- -- ---Io N .............
OR I UNACCEPTABLE
............--
............
.............
.. ... ............. ...... .-------. ...----------- ----.......................
..........
..........
..........
..........
.............
.............
I ...........
-...........
---- I ...........
.............
I .............
..............
..........
.............
.............
..............
.........................
....... ...........
.............
...........................
.........
...........
TRANSIE.NT INSERTION LIMIT (75.0:INCRES)
T " I I n ii OPERATION
..................
RESTRICTED
----------... .....i. .... ... ....... ................
.............
.............
.............m6m...........mnm mmi...M -m mmm LONG TERM STEADY STATE INSERTION::LIMITS:
(112.5 INCHES)............
AC.............C.P TA.. B-........
............
B .............
--.............
LE.........................
...........
- ..............
- ..............:
.............
.............
.............
-- ------------------....
... ...........................
S OPERATION AccEPTABLE
....................
....--....--....-
.... .... ...........
,.... ----------------
0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 FRACTION OF RATED THERMAL POWER 0.2 0.1 0.0 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)........-. ! -* rr .......V .1-. ..I -r I T 20.0 15.0.............
....... ...REGION-OF
.............
UNACCEPTABLE OPERATION M U-)10.0 5.0 REGION OF, kLCCEPTABL .E OPERATION 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 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 23 25 20 z7 0 u 2 Ii 0d 0.0 u 15 10 5 0 50 60 70 80 90 CORE POWER LEVEL (% OF RATED THERMAL POWER)100 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 2.4 2.3.........1 .........z C.-CL u-2.2 2.1 (-01,2.28)
-.-.----1.9 3).................
........ ................
................
.................
...... .............. ....ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0).06,2.38) ( 8.................
-- -......... ...... ...............
i.................
ACCEPTABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN ,EACH OPERABLE CPC-ClANNEL (0.05,2.00)
................
.............
.0 UNACCEPTABýLE
........ ...............
OPERATION
--- ...............
..(0. 1 2.. ...............
I.........
.......................
(0.1,2.38)::
illllilll 2.0 1.9 1.8 1 lI ...Il ....l. l l l i. .I I i i-0.20 -0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4.........1 .........z u 3.3.... ...........ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE
.. .... ........ ........"IN ANY OPERABLE CPC .......CHANNEL-.....0.0.3.4.....
...........................
.........
-- ---------------------7..........
...,3.27)UNACCEPTABLE OPERATION.....................I. ... ..... ..................1 .........(0.1,3.41)::
.. .......................
(-0.1 3.2 3.1 30........ 1 1 .........1 ............I ..................................................I ..I-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 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 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 hours 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 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 Effective December 20, 2013 I I r Dig~itallys(i~gned by Bodnar, Independent Reviewer Bod n ar, War Z6432)Wate (Z0632 Date DN: cnBodnar, Walter Walter ,/ W alt e so: ave reviewed this Date0:0201 2.18 16:16:10 S(Z0643 070 LiJeffrey signd0b3 Aston Responsible Section Leader Ash .ton, Digitally signed byAshton, Date DN cn=Ashton, Jeffrey"C(Z03403)
Jeffrey a m approving this C(7fl 4 Date 20 12.1822:24:41vv 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 Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 19 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keft'> 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 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 24 25 26 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 27 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 Supp_Re f#a _ L -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. S ReS Title Report No. Rev Date Supp Re fW 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.10 Scherer (CE), ("Acceptance for 1990 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)19 Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.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 limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained
> fully withdrawn
' 3 while in Modes I and 2 (except while performing SR 3.1.5.3).
When > 20% power Regulating Group 3 shall be maintained
> fully withdrawn.
1' 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted.
In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
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: 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 2 CORE OPERATING LIMITS REPORT Revision 19 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 5 2 4 3...................
........................
- ...............
.... ...REGION OF ACCEPTABLE OPERATION...........-----------............------....... ..............
.0 ....(5---- -----000,5.0)REGION OF UNACCEPTABLE OPERATIO0N (350..0)2 0 0 100 200 300 400 COLD LEG TEMPERATURE
(°F)500 600 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 6 5 REGION OF ACCEPTABLE
................-
O P E R A T IO N -: .........
.2 0 H 4 3 I-.2 0.. ..........-- -- -(500,6.5):
(350,4.0)REGION OF UNACCEPTABLE
..........
........................
.......................
OPERATION...... ....... ..I ............. ..... ...... ...............
0 100 200 300 400 COLD LEG TEMPERATURE (TF)500 600 Page 13 of 27 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 Revision 19 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0-0.5-1.0 z W U 0 F-0:z-1.5-MTCAREAI .... 2..(100%,44,-. ------ -- ----..............
.---......
........ ... .. --S (50%, 0.o)-------------....
... .............
.............
-- ----.........
................
........................
_( 1 0 T .Q., ,- ....... ..............
..............
................
M T C -- A R E A -O F ............................
... .................
-ACCEPTABLE OPERATION........................................
..................
i...................................
-- -----.................... ........ .........................
--................
.. ...........
...............
..........-
...... ...........
.............
.............
.............
...............
.....................................
--............
.. ................................ ..... .... .............--
.........
.........
.....-- -------------.... .... .... .. i ............
(100)%,-4.41
.0%,-4.4)-2.0-2.5-3.0-3.5-4.0-4.5 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 z 0 r-uw CORE POWER REDUCTIO]20.......1 5 -.-. --------------...........
.................
....... ............
101 5 /10------..................
..... ................
...../5 ---------- -------------------61 100% to>80% RTP 12 12. ý80% to>70% RTP 9>45% RTP.-........
......................
...........
............ .. .................
..........
................15 AFTER CEA DEVIATION*
m0 110 5 0 10 20 TIME AFTER DE'0........., ,. ..I. ....., 30 40 5 VIATION, MINUTES 0 60* 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)0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 CEA Groups 1 and 2 must be > fully withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn*
for power levels > 20%.CEA Group 3 must be withdrawn
> 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn*
for power levels > 70.87%.CEA Group 4 must be withdrawn
> the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).AND CEA Group 5 must be withdrawn
> the group 5 TIL (TIL5) as indicated on the graph or by the equation: TIL5 = (172.5" x Fractional Power) -64.5" (for powers > 37.39% and < 100%).......---.. .. .-- -.. .. ... .. ... ........ ...-- -- -......I .. ..........T ' :. .............NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all:conditions below must be met:* .. I .p p .~. ~ p I I I I I I GROUP 5 SI I GROUP 3 I I ','I GROUP 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 1.0 0.9 0.8 0.7 Lu 0 ru U 0.6 0.5 0.4 0.3 0.2 0.1 0.0-r z 5 (COLSS OUT OF SERVICE)in" NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.---.--. .................
..................
'To m eet the Transient Insertion Lim it (TIL) all conditions below must be met: CEA Groups 1 and 2 must be > fully----.------.----.---.............
....... withdrawn* (see definition below) in M O DE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn*
for power levels > 20%.CEA Group 3 must be withdrawn
> 60" for , power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn*
for z power levels > 54.97%.CEA Group 4 must be withdrawn
> the.group 4 TIL (TIL4) as indicated on the graph or gopby the equation:TIL4 = (250.9" x Fractional Power) + 9.82"*:- power > 20% and < 54.97%).------ ..AND CEA Group 5 must be withdrawn
> the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) -80.18" (for power? 31.96% and <75.00%).(L=108" (for power level 1 75.00%).-~*-- ~P!~I I I I I I---SI a I I GROUP 5 I I I I I I GROUP 3 I I I I I I GROUP 1 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 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 10.0 20.0 30.0 z 0 0 z 40.0 50.0 60.0 70.0 80.0 90.0.......................................-
I...............
.----------------....
.. ..........
...............
........ .............
- --------------...............
--- -....................
.............
.............
..........
O PE R A T.IO N ...............
,,:NACCEPTABLE
..........
...........
..........
.!..............
............--
............................
............TRANSIENT INERTION LIMIT (75.0::INCHES.)
I I I.......O...... PERA;U.TION.
RESTRICTED
...........
100.0 110.0.........................
120.0 130.0 LONG TERM STEADY STATE INSERTIONULIMITS:
(112.5 INCHES).............
- P E 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 15.0..m 9 .............m w K m----------------
0 REG IO N O F ---- -- .......UNACCEPTABLE OPERATION 10.0 5.0 REGION OF LCCEPTABLE
...I ...I .OPERATION 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 20 z 0 0 0z~0 0 15--------------------------
..........................
..........................
(95,20)..........................
....................
(95,20)10 5I (70.0) I 0 50 60 70 80 CORE POWER LEVEL (% OF RATED THERMAL POWER)90 100 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 2.4 I I 2.3 ýz z u CL u 2.2 2.1 (-0.1,2.28)
(-0---------
.................
.............
.................
........
I .........I I I I I I I I I I I I .ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST I CEAC OPERABLE IN EACH OPERABLE CPC ClltANNEL-----------------
..................
.................
...........
................
(0..06,2.38)
(0.1,2.38)::
....... ..... ........................
... --------------
.................
.................
.................
I .................
.................
ACCEftABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN-EACH 'OPERARL"EUT' CIIA r*M L' I ----------------
..........(O.Oý,2.00)
..................................
..................
00 UNACCEPTAB E------------------
... O P E R A T IO N --- .................
.................
.lm 2.0 1.9 1.8 '-0.2 1.................. .................................... ..20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 Tll,1111il 3.5 3.4 z 3.3.................
- ----------
..........
..........
............................
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE
... .. ..... .e ... ... ..........
...-- --.--IN ANY OPE R ABLE CPC CHANNEL (0.0, 3.4 1) .................
4..1i,3.27)..............
..... ...................................
...........
.. .. ...-.... ........I... .......I.. ..................... ................
0.1,3.41)::
...............
...............
...............
...............
.------------
(-0.3.2 3.1 3.0-0..,, , , I ...,,,...................... ... .......i i i l .........i l l ... .......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 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 _ Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 Effective December 20, 2013 I I Responsible Engineer Sutton C Digitally signed by Sutton, Su It 14 Bradley J(Z06308)Date ADN: cn=Sutton, Bradley BradleyZ0630]8)
Bradey 06jý1m the author of this docum J(Z06308,)-
Date: 2013.12.18 15:51:37 -07'00'Digitally signed by Bodnar, Independent Reviewer Bodnar, Walt ser S(Z od43 r ijWalter 5(Z06432)DDN cn=Bodnar, Walter Date Walter z0)3 W alter soB 4 3 rhave reviewed this S(Z064b 0Date2010 12.18 16:16:54 S(ZO 4~- -07'00'Responsible Section Leader As-Io,,- Digitally signed by Ashton, A IsIho Jeffrey C(Z03403)Date DN cn=Ashton, Jeffrey/ ... C(z03403)rey son lam approving this)7. Date: 20t?2.18 22:26:00 C(Z 34 ..-' -07'00'Page 1 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 2 4 5 6 CORE Operating Limits 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 9 9 9 9 9 10 10 10 10 11 11 11 Page 2 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Pae 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes I and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)13 14 15 16 17 18 19 20 21 22 Page 3 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Page 231 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keffl 0.98 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 24 25 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 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 26 27 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 Re f#a S11P-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 Steam Supply Reference Systems September 3 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 Ref#a UW 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.10 Scherer (CE), ("Acceptance for 1990 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.16 ing Methods for San Onofre Nuclear 160(S)-P 1981 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)19 Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.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 limits 1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained
> fully withdrawn 1' 3 while in Modes I and 2 (except while performing SR 3.1.5.3).
When > 20% power Regulating Group 3 shall be maintained
> fully withdrawn.l' 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 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: 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 H..............
R E I O "i..........................
...REGION OF ACCEPTABLE OPERATION----------
....................------------------.---- --.....(500,5.0 REGION OF UNACCEPTABLE
.. ............ -- ---------..........................l l l l l l l l l ......l l l l l l l .......I 1 0 100 200 300 400 COLD LEG TEMPERATURE
('F)500 600 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 6 ....... ...<2.Z 4 0 3 F-(500,6.5)i REGION OF ACCEPTABLE O P. RA TIO N -------------
......................
! ................i ........... ...'... ....... ................ .(350,4.0)............................................................................
.......................
......................
REGION OF UNACCEPTABLE
.....................................................
r ......................
..............................................
OPERATION...............
...........
......... ....L.L......
..i ..L .....2 I 0 0 100 200 300 400 COLD LEG TEMPERATURE
(*F)500 600 Page 13 of 27 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 Revision 22 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0 0~0 U 0 0 02-0.5-1.0-1.5-2.0-2.5-3.0~ ~....I .:.... ' .- ME ....':.. .' .. ...... 0. ... .. ....... .(o%,o.5) ..............
i ... ...:: ....... (100% ,o1 .......... -------.............
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... ,.i e :" l ~ l l S(50%, 0.o)............--
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( .Q % : ........ ...........
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..... ....... IM T C -A RlE A -O F ------------..............
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ACCEPTABLE OPERATION... ........ ............................---.............
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... ......... .... ............ ....... .. ..... ...... .. .. ........... ..... ...... .... ... ..............). ........ ..... ... ...........------------(100%,-4.41
.(0%,-4.4)
.-3.5-4.0-I -I -U -I -mu -I -im lJ.LLIsz~I.
L ~ L .L.LL..A.
I .LLL..J. .1 ..1.L.J.L J LLL.L j ..LLLL I ~LL..A.. I LLL..L.-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 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.5-1 Revision 22 CORE POWER REDUCTION AFTER CEA DE'20 .......I ....1 VIATION*___ 20 I15 F-0 LL]10 5 16/100% to* >80% RTP-------------.......
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.12 12 <80% to ->70% RTP...... .........................-- ---..................... .....I .....................*~9.8'. 8 f70% to>45% RTP......I ............ .. ......I ........I .. I .........15 10 5 0O1ý i ; ;0 10 20 30 40 TIME AFTER DEVIATION, MINUTES 50 60* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.* 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)z U 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0* See Footnote in Section 3.1.7 for applicability
'following a Reactor Power Cutback.., To meet the Transient Insertion Limit (TIL) all'conditions below must be met: CEA Groups 1 and 2 must be > fully...... withdrawn* (see definition below) in MODE 1 and MODE 2.AND CEA Group 3 must be > fully withdrawn*
for power levels >20%.* CEA Group 3 must be withdrawn
> 60" for power > 0% and < 20%.AND CEA Group 4 must be > fully withdrawn*
for power levels > 70.87%.CEA Group 4 must be withdrawn
> the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).AND CEA Group 5 must be withdrawn
> the group 5 TIL (TIL5) as indicated on the graph or by the equation: TIL5 = (172.5" x Fractional Power) -64.5" (for powers > 37.39% and < 100%).---, i....... ....... i ........1 1 1 I I I I I I GROUP 5 I I I I I I GROUP3 I I I I I I GROUP 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 29+0 6+0 3'0 ý 1J0" i20 1 90 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)F-, z 0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 NOTE: See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback...L .... ..... .....i .... .T. o m eet the Trans ient Insertion L im it (T IL) a l below must be met: ,,L OFCA Groups 1 and 2 must be >_ fully..........................wthdrawn* (see definition below) in MODE 1',and MODE 2.I AND~CEA Group 3 must be_> fully withdrawn*
for folpower levels >_ 20%...... CEA Group 3 must be withdrawn
> 60" for.. ...... ......... ........ .a..... .S C Group 4 must be _ fully withdrawn*
for S power levels > 54.97%.conditi CEA Group 4 must be withdrawn
> the group 4 TIL (TIL4) as indicated on the graph or by the equation: TIL4 = (250.9" x Fractional Power) + 9.82 S (for power > 20% and < 54.97%)."-" ...... !. ...AND CEA Group 5 must be withdrawn
>_ the i group 5 TIL (TIL5) as indicated on the graph orby the equations:
...... ------- ........ ......... wtd a n s ed fnto eo )i O E1l oI TIL5 = (250.9" x Fractional Power) -80.18" (for power> 31.96% and < 75.00%).wTIL5 = 108" ( power level > 75.00%).I t I I I I b wi > the i!GROUP 5 I I I I I I GROUP 3 I t I II I GROUP I I I I I I I 150" 120 90 60 30 0 150" 120 90 60 30 0 150"!120 90 60 30 GROUP 4 GROUP 2 1 E0*1A0 9P0 6I 3TI O ( C 20 190 I 60 130 CEA POSITION (INCHES WITHDRAWN) 0* 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 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 22 u z 0 u 0 I-0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0----------
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O PE R A T ION.............
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-.UNACCEPTABLE i.............
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- ,-2 i .................... ................ .........................-------....................................... ..............O.. .. PERATION -------------
RESTRICTED
-.... -... ... .-.......LONG TERM STEADY STATE INSERTION:LIMITS:( 12.5 INCHES)...........A C C E P T A B L E ............................ ..--. ............- .. ...................................... .............. ...... .----... ..... ....--......
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.....b`PERATIONý ACCEPTABLE
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.....*1 I 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 FRACTION OF RATED THERMAL POWER 0.2 0.1 0.0 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----------------
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0..F-.REGION OF -----------
UNACCEPTABLE OPERATION 10.0-S -S -5.0 REGION OF.....-a .-.-.-.-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 20 0 r-0 u.15------------------
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......(95,20)----------........... .........i ... ................... ...(70,0) I 10 5 0 50 60 70 80 CORE POWER LEVEL (% OF RATED THERMAL POWER)90 100 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 2.4 2.3 z a.)2.2 2.1-, ...-----------, ...(-0.1,2.28)
--(-0.1,1.93)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0.06,2.38)
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..... ACCEPTABLE OPERATION POWER AT OR ABOVE 90.i%AT LEAST I CEAC OPERABLE IN E..ACH-OPERABLE CPC CIHANNEL: (0.05,2.00)
UNACCEPTABLE
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O P E R A T IO N ......................
.....I ---... .I ---... .I -.. .. ..lllllllllllllllllUI
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...... ......-------2.0 1.9 Ig.. .... ... 1 ...... ... 1 1.~ ~ ~ .............. .IJ...J...J...I
-0.-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4.........1 .........3.3...................
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- OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE
--- --- ----- ... .... ........IN A NY 0OPER BLE-CPC CHANNEL------------
3-4 1-. .. ...................
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i....lllll (-0.]3.2 3.1*1 A.........I .........I ...................................I ................1 ,-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 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 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 27