ML19204A193
| ML19204A193 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/22/2019 |
| From: | Dilorenzo M Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-07955-MDD/TMJ | |
| Download: ML19204A193 (91) | |
Text
Technical Specification 5.6.Sd 102-07955-MDD/TMJ July 22, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Palo Verde Nuclear Generating Station 5871 S. Wlntersburg Road Tonopah, AZ 85354
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Unit 1 Core Operating Limits Report Revision 27 Unit 2 Core Operating Limits Report Revision 22 Unit 3 Core Operating Limits Report Revision 25
Dear Sirs:
Pursuant to Palo Verde Nuclear Generating Station (PVNGS) Technical Specifications, Section 5.6.5d, enclosed are the Units 1, 2, and 3 Core Operating Limits Report (COLR),
Revisions 27, 22, and 25, respectively, which were made effective July 1, 2019.
The changes Implemented by these revisions are to the Table In the Analytical Methods section of each unit's COLR. Previously, documents referenced In that Table did not list all the reference Information required by the NOTE contained In Technical Specification 5.6.5b (Reporting Requirements - Analytical Methods). No technical changes are necessary.
These changes affect several pages In the respective COLRs. Revision bars have been applied to those pages which contain changes.
No commitments are being made to the Nuclear Regulatory Commission (NRC) by this letter. If you have any questions about this submittal please contact Michael D.
Dilorenzo, Nuclear Regulatory Affairs, Department Leader, at (623) 393-3495.
Sincerely,
~~
- ~
0 1 G 11t-1.... fc:Jr-Michae1 D. Dilorenzo Nuclear Regulatory Affairs Department Leader MDD/TMJ/mg
Enclosures:
Unit 1 Core Operating Limits Report, Revision 27 Unit 2 Core Operating Limits Report, Revision 22 Unit 3 Core Operating Limits Report, Revision 25 cc:
S. A. Morris S. P. Llngam M.M. O'Bannion C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
Enclosure Unit 1 Core Operating Limits Report Revision 27
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- Bodnar, Walter S(Z06432)
Digitally signed by Bodnar, Walter S(Z06432)
DN: cn=Bodnar, Walter S(Z06432)
Reason: I am the author of this document Date: 2019.06.28 07:34:15 -07'00'
- Arias, Joseph R(V02724)
Digitally signed by Arias, Joseph R(V02724)
DN: cn=Arias, Joseph R(V02724)
Reason: I have reviewed this document.
Date: 2019.06.28 08:24:00
-07'00'
- Karlson, Charles F(V55086)
Digitally signed by Karlson, Charles F(V55086)
DN: cn=Karlson, Charles F(V55086)
Reason: I am approving this document Date: 2019.06.28 09:14:35
-07'00'
Revision 27 Page 2 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1
Table of Contents 2
List of Figures 3
List of Tables 4
Affected Technical Specifications 5
Analytical Methods 6
CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13
Revision 27 Page 3 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 19 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 20 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 21 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 22 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 23 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 24 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Revision 27 Page 4 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 28 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 29 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95
Revision 27 Page 5 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 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 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
Revision 27 Page 6 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S Ref#a Title Report No.
Rev Date Suppl 1
CE Method for Control Element Assem-bly Ejection Analysis (N001-1301-01204)
CENPD-0190-A N.A.
January 1976 N.A.
2 The ROCS and DIT Computer Codes for Nuclear Design (N001-1900-01412)
CENPD-266-P-A N.A.
April 1983 N.A.
3 Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470 NUREG-0852 N.A.
November 1981 March 1983 September 1983 December 1987 N.A.
1 2
3 4
Modified Statistical Combination of Uncertainties (N001-1303-01747)
CEN-356(V)-P-A 01-P-A May 1988 N.A.
4 System 80TM Inlet Flow Distribution (N001-1301-01228)
Enclosure 1-P to LD-82-054 N.A.
February 1993 1-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
August 1974 N.A.
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
February 1975 1
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132-P N.A.
July 1975 2-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS CENPD-132 N.A.
June 1985 3-P-A
Revision 27 Page 7 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-1900-01192)
CENPD-132 N.A.
March 2001 4-P-A Rev. 1 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-0205-00046)
CENPD-132 N.A.
August 2007 4-P-A Adde-ndum 1-P-A 5
Revision 4 to the Supplement to Appen-dix A of CENPD-132 Supplement 4-P-A (N001-0205-00229)
CENPD-132 N.A.
December 2008 SUPP 4-P-A APP A-REV 004 6
Calculative Methods for the C-E Small Break LOCA Evaluation ModeL CENPD-137-P N.A.
August 1974 N.A.
6 Calculative Methods for the C-E Small Break LOCA Evaluation Model CENPD-137 N.A.
January 1977 1-P 6
Calculative Methods for the ABB C-E Small Break LOCA Evaluation Model (N001-1900-01185)
CENPD-137 N.A.
April 1998 2-P-A 7
Letter: O.D. Parr (NRC) to F. M. Stern (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
N.A.
N.A.
June 13, 1975 N.A.
8 Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
N.A.
N.A.
September 27, 1977 N.A.
9 Fuel Rod Maximum Allowable Pressure (N001-0201-00026)
CEN-372-P-A N.A.
May 1990 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 27 Page 8 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 10 Letter: A. C. Thadani (NRC) to A. E.
Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
N.A.
N.A.
April 10, 1990 N.A.
11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
NFM-005 1
August 2007 N.A.
12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)
CE-NPD 282-P-A Vols. 1 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
CE-NPD 282-P-A Vols. 2 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)
CE-NPD 282-P-A Vols. 3 2
March 2005 N.A.
13 Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (N001-1900-01329)
CENPD-404-P-A 0
November 2001 N.A.
13 Optimized ZIRLOTM (N001-0203-00611)
CENPD-404-P-A Addendum 1-A 0
July 2006 N.A.
13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOTM (N001-0205-00006)
CENPD-404-P-A Addendum 2-A 0
October 2013 N.A.
14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)
CENPD-188-A N.A.
July 1976 N.A.
15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (N001-1301-01202)
CENPD-161-P-A N.A.
April 1986 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 27 Page 9 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 16 CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (N001-1301-01185)
CEN-160(S)-P 1-P September 1981 N.A.
17 Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) and Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005).
N.A.
N.A.
September 29, 2003 November 16, 2005 N.A.
18 CPC Methodology Changes for the CPC Improvement Program (N001-1303-02283)
CEN-310-P-A 0
April 1986 N.A.
19 Loss of Flow, C-E Methods for Loss of Flow Analysis (N001-1301-01203)
CENPD-183-A 0
June 1984 N.A.
20 Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (N001-0201-00035)
CENPD-382-P-A 0
August 1993 N.A.
21 Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)
CEN-386-P-A 0
August 1992 N.A.
22 CE 16x16 Next Generation Fuel Core Reference Report (N001-0203-00614)
August 2007 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 27 Page 10 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 22 Application of CE Setpoint Methodol-ogy for CE 16x16 Next Generation Fuel (NGF)
(N001-0205-00063)
December 2010 1
Rev. 1 22 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (N001-0205-00048)
June 2016 2-P-A 23 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (N001-0205-00002)
October 1999 N.A.
23 Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (N001-0205-00003)
WCAP-14565-P-A, Addendum 1-A 0
August 2004 N.A.
23 Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Cor-relation and Modified ABB-NV Correla-tion WLOP for PWR Low Pressure Applications (N001-0205-00004)
WCAP-14565-P-A, Addendum 2-P-A 0
April 2008 N.A.
24 ABB Critical Heat Flux Correlations for PWR Fuel (N001-0205-00042)
CENPD-387-P-A 0
May 2000 N.A.
25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup-ported Mixing Vanes (N001-0203-00615)
August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (N001-0205-00226)
August 2004 N.A.
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 T.S Ref#a Title Report No.
Rev Date Suppl
Revision 27 Page 11 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.
3.1.1 - Shutdown Margin (SDM) - Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.
3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.
3.1.4 - Moderator Temperature Coefficient (MTC)
The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.
3.1.5 - Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.
3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1, 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.1, 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
Revision 27 Page 12 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and
>145.25 (RSPT indication). No further CEA withdrawal above FW is required for CEAs to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit 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.
Revision 27 Page 13 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 AS 0.17 for power > 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 ASI 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 3000 ppm.
Revision 27 Page 14 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 1.0)
(500, 5.0)
Revision 27 Page 15 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 4.0)
(500, 6.5)
Revision 27 Page 16 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT
-4.5
-4.0
-3.5
-3.0
-2.5
-2.0
-1.5
-1.0
-0.5 0.0 0.5 0
10 20 30 40 50 60 70 80 90 100 MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 MTC AREA OF ACCEPTABLE OPERATION (0%,0.5)
(100%,0)
(50%, 0.0)
(100%,-0.2)
(0%,-4.4)
(100%,-4.4)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit
Revision 27 Page 17 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0
5 10 15 20 0
10 20 30 40 50 60 MINIMUM REQUIRED POWER REDUCTION
(% OF RATED THERMAL POWER)
TIME AFTER DEVIATION, MINUTES FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20 100% to
>80% RTP 16 12 8
4 0
15 80% to
>70% RTP 12 9
6 3
10 70% to
>45% RTP 8
6 4
2 5
45% RTP 4
3 2
1
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- > 95 % RATED THERMAL POWER
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION
Revision 27 Page 18 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 70.87%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power 20% and < 70.87%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equation:
TIL5 = (172.5" x Fractional Power) - 64.5" (for power 37.39% and 100%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 27 Page 19 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 54.97%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (250.9" x Fractional Power) + 9.82" (for power 20% and < 54.97%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) - 80.18" (for power 31.96% and 75.00%).
TIL5 = 108" (for power lever 75.00%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 27 Page 20 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN)
FRACTION OF RATED THERMAL POWER FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION RESTRICTED LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES)
TRANSIENT INSERTION LIMIT (75.0 INCHES)
(50% RATED THERMAL POWER)
Revision 27 Page 21 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0.0 5.0 10.0 15.0 20.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 AZIMUTHAL POWER TILT (%)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)
REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION
Revision 27 Page 22 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 0
5 10 15 20 25 50 60 70 80 90 100 COLSS DNBR POWER OPERATION LIMIT REDUCTION
(% OF RATED THERMAL POWER)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)
(80, 5)
(70, 0)
Revision 27 Page 23 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)
(-0.1, 1.99)
(-0.1, 2.28)
(0.06, 2.38)
(0.08, 2.07)
(0.1, 2.38)
(0.1, 2.07)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 27 Page 24 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 3.0 3.1 3.2 3.3 3.4 3.5 3.6
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)
(-0.1, 3.27)
(0.0, 3.41)
(0.1, 3.41)
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 27 Page 25 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 27 Page 26 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 Keff > 0.97 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 27 Page 27 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 Keff > 0.96 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 27 Page 28 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Keff > 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 27 Page 29 of 29 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Enclosure Unit 2 Core Operating Limits Report Revision 22
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- Bodnar, Walter S(Z06432)
Digitally signed by Bodnar, Walter S(Z06432)
DN: cn=Bodnar, Walter S(Z06432)
Reason: I am the author of this document Date: 2019.06.28 07:35:49 -07'00'
- Arias, Joseph R(V02724)
Digitally signed by Arias, Joseph R(V02724)
DN: cn=Arias, Joseph R(V02724)
Reason: I have reviewed this document Date: 2019.06.28 08:26:05
-07'00'
- Karlson, Charles F(V55086)
Digitally signed by Karlson, Charles F(V55086)
DN: cn=Karlson, Charles F(V55086)
Reason: I am approving this document Date: 2019.06.28 09:16:12
-07'00'
Revision 22 Page 2 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1
Table of Contents 2
List of Figures 3
List of Tables 4
Affected Technical Specifications 5
Analytical Methods 6
CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13
Revision 22 Page 3 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 19 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 20 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 21 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 22 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 23 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 24 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Revision 22 Page 4 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 28 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 29 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95
Revision 22 Page 5 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 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 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
Revision 22 Page 6 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S Ref#a Title Report No.
Rev Date Suppl 1
CE Method for Control Element Assem-bly Ejection Analysis (N001-1301-01204)
CENPD-0190-A N.A.
January 1976 N.A.
2 The ROCS and DIT Computer Codes for Nuclear Design (N001-1900-01412)
CENPD-266-P-A N.A.
April 1983 N.A.
3 Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470 NUREG-0852 N.A.
November 1981 March 1983 September 1983 December 1987 N.A.
1 2
3 4
Modified Statistical Combination of Uncertainties (N001-1303-01747)
CEN-356(V)-P-A 01-P-A May 1988 N.A.
4 System 80TM Inlet Flow Distribution (N001-1301-01228)
Enclosure 1-P to LD-82-054 N.A.
February 1993 1-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
August 1974 N.A.
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
February 1975 1
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132-P N.A.
July 1975 2-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS CENPD-132 N.A.
June 1985 3-P-A
Revision 22 Page 7 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-1900-01192)
CENPD-132 N.A.
March 2001 4-P-A Rev. 1 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-0205-00046)
CENPD-132 N.A.
August 2007 4-P-A Adde-ndum 1-P-A 5
Revision 4 to the Supplement to Appen-dix A of CENPD-132 Supplement 4-P-A (N001-0205-00229)
CENPD-132 N.A.
December 2008 SUPP 4-P-A APP A-REV 004 6
Calculative Methods for the C-E Small Break LOCA Evaluation ModeL CENPD-137-P N.A.
August 1974 N.A.
6 Calculative Methods for the C-E Small Break LOCA Evaluation Model CENPD-137 N.A.
January 1977 1-P 6
Calculative Methods for the ABB C-E Small Break LOCA Evaluation Model (N001-1900-01185)
CENPD-137 N.A.
April 1998 2-P-A 7
Letter: O.D. Parr (NRC) to F. M. Stern (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
N.A.
N.A.
June 13, 1975 N.A.
8 Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
N.A.
N.A.
September 27, 1977 N.A.
9 Fuel Rod Maximum Allowable Pressure (N001-0201-00026)
CEN-372-P-A N.A.
May 1990 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 22 Page 8 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 10 Letter: A. C. Thadani (NRC) to A. E.
Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
N.A.
N.A.
April 10, 1990 N.A.
11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
NFM-005 1
August 2007 N.A.
12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)
CE-NPD 282-P-A Vols. 1 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
CE-NPD 282-P-A Vols. 2 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)
CE-NPD 282-P-A Vols. 3 2
March 2005 N.A.
13 Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (N001-1900-01329)
CENPD-404-P-A 0
November 2001 N.A.
13 Optimized ZIRLOTM (N001-0203-00611)
CENPD-404-P-A Addendum 1-A 0
July 2006 N.A.
13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOTM (N001-0205-00006)
CENPD-404-P-A Addendum 2-A 0
October 2013 N.A.
14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)
CENPD-188-A N.A.
July 1976 N.A.
15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (N001-1301-01202)
CENPD-161-P-A N.A.
April 1986 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 22 Page 9 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 16 CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (N001-1301-01185)
CEN-160(S)-P 1-P September 1981 N.A.
17 Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) and Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005).
N.A.
N.A.
September 29, 2003 November 16, 2005 N.A.
18 CPC Methodology Changes for the CPC Improvement Program (N001-1303-02283)
CEN-310-P-A 0
April 1986 N.A.
19 Loss of Flow, C-E Methods for Loss of Flow Analysis (N001-1301-01203)
CENPD-183-A 0
June 1984 N.A.
20 Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (N001-0201-00035)
CENPD-382-P-A 0
August 1993 N.A.
21 Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)
CEN-386-P-A 0
August 1992 N.A.
22 CE 16x16 Next Generation Fuel Core Reference Report (N001-0203-00614)
August 2007 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 22 Page 10 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 22 Application of CE Setpoint Methodol-ogy for CE 16x16 Next Generation Fuel (NGF)
(N001-0205-00063)
December 2010 1
Rev 1 22 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (N001-0205-00048)
June 2016 2-P-A 23 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (N001-0205-00002)
October 1999 N.A.
23 Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (N001-0205-00003)
WCAP-14565-P-A, Addendum 1-A 0
August 2004 N.A.
23 Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Cor-relation and Modified ABB-NV Correla-tion WLOP for PWR Low Pressure Applications (N001-0205-00004)
WCAP-14565-P-A, Addendum 2-P-A 0
April 2008 N.A.
24 ABB Critical Heat Flux Correlations for PWR Fuel (N001-0205-00042)
CENPD-387-P-A 0
May 2000 N.A.
25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup-ported Mixing Vanes (N001-0203-00615)
August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (N001-0205-00226)
August 2004 N.A.
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 T.S Ref#a Title Report No.
Rev Date Suppl
Revision 22 Page 11 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.
3.1.1 - Shutdown Margin (SDM) - Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.
3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.
3.1.4 - Moderator Temperature Coefficient (MTC)
The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.
3.1.5 - Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.
3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1, 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.1, 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
Revision 22 Page 12 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and
>145.25 (RSPT indication). No further CEA withdrawal above FW is required for CEAs to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit 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.
Revision 22 Page 13 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 AS 0.17 for power > 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 ASI 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 3000 ppm.
Revision 22 Page 14 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 1.0)
(500, 5.0)
Revision 22 Page 15 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 4.0)
(500, 6.5)
Revision 22 Page 16 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT
-4.5
-4.0
-3.5
-3.0
-2.5
-2.0
-1.5
-1.0
-0.5 0.0 0.5 0
10 20 30 40 50 60 70 80 90 100 MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 MTC AREA OF ACCEPTABLE OPERATION (0%,0.5)
(100%,0)
(50%, 0.0)
(100%,-0.2)
(0%,-4.4)
(100%,-4.4)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit
Revision 22 Page 17 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0
5 10 15 20 0
10 20 30 40 50 60 MINIMUM REQUIRED POWER REDUCTION
(% OF RATED THERMAL POWER)
TIME AFTER DEVIATION, MINUTES FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20 100% to
>80% RTP 16 12 8
4 0
15 80% to
>70% RTP 12 9
6 3
10 70% to
>45% RTP 8
6 4
2 5
45% RTP 4
3 2
1
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- > 95 % RATED THERMAL POWER
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION
Revision 22 Page 18 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 70.87%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power 20% and < 70.87%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equation:
TIL5 = (172.5" x Fractional Power) - 64.5" (for power 37.39% and 100%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 22 Page 19 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 54.97%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (250.9" x Fractional Power) + 9.82" (for power 20% and < 54.97%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) - 80.18" (for power 31.96% and 75.00%).
TIL5 = 108" (for power lever 75.00%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 22 Page 20 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN)
FRACTION OF RATED THERMAL POWER FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION RESTRICTED LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES)
TRANSIENT INSERTION LIMIT (75.0 INCHES)
(50% RATED THERMAL POWER)
Revision 22 Page 21 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0.0 5.0 10.0 15.0 20.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 AZIMUTHAL POWER TILT (%)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)
REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION
Revision 22 Page 22 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 0
5 10 15 20 25 50 60 70 80 90 100 COLSS DNBR POWER OPERATION LIMIT REDUCTION
(% OF RATED THERMAL POWER)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)
(80, 5)
(70, 0)
Revision 22 Page 23 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)
(-0.1, 1.93)
(-0.1, 2.28)
(0.06, 2.38)
(0.05, 2.00)
(0.1, 2.38)
(0.1, 2.00)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 22 Page 24 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 3.0 3.1 3.2 3.3 3.4 3.5 3.6
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)
(-0.1, 3.27)
(0.0, 3.41)
(0.1, 3.41)
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 22 Page 25 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 22 Page 26 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 Keff > 0.97 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 22 Page 27 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 Keff > 0.96 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 22 Page 28 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Keff > 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 22 Page 29 of 29 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Enclosure Unit 3 Core Operating Limits Report Revision 25
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- Bodnar, Walter S(Z06432)
Digitally signed by Bodnar, Walter S(Z06432)
DN: cn=Bodnar, Walter S(Z06432)
Reason: I am the author of this document Date: 2019.06.28 07:37:15
-07'00'
- Arias, Joseph R(V02724)
Digitally signed by Arias, Joseph R(V02724)
DN: cn=Arias, Joseph R(V02724)
Reason: I have reviewed this document Date: 2019.06.28 08:27:45
-07'00'
- Karlson, Charles F(V55086)
Digitally signed by Karlson, Charles F(V55086)
DN: cn=Karlson, Charles F(V55086)
Reason: I am approving this document Date: 2019.06.28 09:17:22
-07'00'
Revision 25 Page 2 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1
Table of Contents 2
List of Figures 3
List of Tables 4
Affected Technical Specifications 5
Analytical Methods 6
CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13
Revision 25 Page 3 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 14 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 15 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 16 Figure 3.1.5-1 Core Power Limit After CEA Deviation 17 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 18 (COLSS in Service)
Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 19 (COLSS Out of Service)
Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 20 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 21 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 22 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 23 Protection Calculators (COLSS Out of Service, CEAC(s)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 24 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)
Revision 25 Page 4 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 28 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 29 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95
Revision 25 Page 5 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 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 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
Revision 25 Page 6 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:
T.S Ref#a Title Report No.
Rev Date Suppl 1
CE Method for Control Element Assem-bly Ejection Analysis (N001-1301-01204)
CENPD-0190-A N.A.
January 1976 N.A.
2 The ROCS and DIT Computer Codes for Nuclear Design (N001-1900-01412)
CENPD-266-P-A N.A.
April 1983 N.A.
3 Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470 NUREG-0852 N.A.
November 1981 March 1983 September 1983 December 1987 N.A.
1 2
3 4
Modified Statistical Combination of Uncertainties (N001-1303-01747)
CEN-356(V)-P-A 01-P-A May 1988 N.A.
4 System 80TM Inlet Flow Distribution (N001-1301-01228)
Enclosure 1-P to LD-82-054 N.A.
February 1993 1-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
August 1974 N.A.
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.
February 1975 1
5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132-P N.A.
July 1975 2-P 5
Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS CENPD-132 N.A.
June 1985 3-P-A
Revision 25 Page 7 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-1900-01192)
CENPD-132 N.A.
March 2001 4-P-A Rev. 1 5
Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (N001-0205-00046)
CENPD-132 N.A.
August 2007 4-P-A Adde-ndum 1-P-A 5
Revision 4 to the Supplement to Appen-dix A of CENPD-132 Supplement 4-P-A (N001-0205-00229)
CENPD-132 N.A.
December 2008 SUPP 4-P-A APP A-REV 004 6
Calculative Methods for the C-E Small Break LOCA Evaluation ModeL CENPD-137-P N.A.
August 1974 N.A.
6 Calculative Methods for the C-E Small Break LOCA Evaluation Model CENPD-137 N.A.
January 1977 1-P 6
Calculative Methods for the ABB C-E Small Break LOCA Evaluation Model (N001-1900-01185)
CENPD-137 N.A.
April 1998 2-P-A 7
Letter: O.D. Parr (NRC) to F. M. Stern (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:
5.6.5.b.6.
N.A.
N.A.
June 13, 1975 N.A.
8 Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
N.A.
N.A.
September 27, 1977 N.A.
9 Fuel Rod Maximum Allowable Pressure (N001-0201-00026)
CEN-372-P-A N.A.
May 1990 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 25 Page 8 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 10 Letter: A. C. Thadani (NRC) to A. E.
Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.
N.A.
N.A.
April 10, 1990 N.A.
11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)
NFM-005 1
August 2007 N.A.
12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)
CE-NPD 282-P-A Vols. 1 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)
CE-NPD 282-P-A Vols. 2 2
March 2005 N.A.
12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)
CE-NPD 282-P-A Vols. 3 2
March 2005 N.A.
13 Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (N001-1900-01329)
CENPD-404-P-A 0
November 2001 N.A.
13 Optimized ZIRLOTM (N001-0203-00611)
CENPD-404-P-A Addendum 1-A 0
July 2006 N.A.
13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOTM (N001-0205-00006)
CENPD-404-P-A Addendum 2-A 0
October 2013 N.A.
14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)
CENPD-188-A N.A.
July 1976 N.A.
15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (N001-1301-01202)
CENPD-161-P-A N.A.
April 1986 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 25 Page 9 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 16 CETOP-D Code Structures and Model-ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (N001-1301-01185)
CEN-160(S)-P 1-P September 1981 N.A.
17 Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) and Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:
Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005).
N.A.
N.A.
September 29, 2003 November 16, 2005 N.A.
18 CPC Methodology Changes for the CPC Improvement Program (N001-1303-02283)
CEN-310-P-A 0
April 1986 N.A.
19 Loss of Flow, C-E Methods for Loss of Flow Analysis (N001-1301-01203)
CENPD-183-A 0
June 1984 N.A.
20 Methodology for Core Designs Contain-ing Erbium Burnable Absorbers (N001-0201-00035)
CENPD-382-P-A 0
August 1993 N.A.
21 Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16 x 16 PWR Fuel (N001-0201-00042)
CEN-386-P-A 0
August 1992 N.A.
22 CE 16x16 Next Generation Fuel Core Reference Report (N001-0203-00614)
August 2007 N.A.
T.S Ref#a Title Report No.
Rev Date Suppl
Revision 25 Page 10 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 22 Application of CE Setpoint Methodol-ogy for CE 16x16 Next Generation Fuel (NGF)
(N001-0205-00063)
December 2010 1
Rev 1 22 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (N001-0205-00048)
June 2016 2-P-A 23 VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (N001-0205-00002)
October 1999 N.A.
23 Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (N001-0205-00003)
WCAP-14565-P-A, Addendum 1-A 0
August 2004 N.A.
23 Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Cor-relation and Modified ABB-NV Correla-tion WLOP for PWR Low Pressure Applications (N001-0205-00004)
WCAP-14565-P-A, Addendum 2-P-A 0
April 2008 N.A.
24 ABB Critical Heat Flux Correlations for PWR Fuel (N001-0205-00042)
CENPD-387-P-A 0
May 2000 N.A.
25 Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup-ported Mixing Vanes (N001-0203-00615)
August 2007 N.A 26 Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (N001-0205-00226)
August 2004 N.A.
- a. Corresponds to the reference number specified in Technical Specification 5.6.5 T.S Ref#a Title Report No.
Rev Date Suppl
Revision 25 Page 11 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.
3.1.1 - Shutdown Margin (SDM) - Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.
3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.
3.1.4 - Moderator Temperature Coefficient (MTC)
The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.
3.1.5 - Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.
3.1.7 - Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn1, 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.1, 3 1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:
a) Regulating Group 4 position is between 60 and 150 inches withdrawn.
Revision 25 Page 12 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.
c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).
3 Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and
>145.25 (RSPT indication). No further CEA withdrawal above FW is required for CEAs to meet the Transient Insertion Limit (TIL) requirements.
3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.
3.2.1 - Linear Heat Rate (LHR)
The linear heat rate limit 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.
Revision 25 Page 13 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 3.2.5 - Axial Shape Index (ASI)
The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
-0.18 AS 0.17 for power > 50%
-0.28 < ASI < 0.17 for power >20% and < 50%
-0.10 ASI 0.10 for power >20%
3.3.12 - Boron Dilution Alarm System (BDAS)
With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.
3.9.1 - Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 3000 ppm.
Revision 25 Page 14 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 1.0)
(500, 5.0)
Revision 25 Page 15 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
1 2
3 4
5 6
7 0
100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)
COLD LEG TEMPERATURE (F)
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 4.0)
(500, 6.5)
Revision 25 Page 16 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT
-4.5
-4.0
-3.5
-3.0
-2.5
-2.0
-1.5
-1.0
-0.5 0.0 0.5 0
10 20 30 40 50 60 70 80 90 100 MODERATOR TEMPERATURE COEFFICIENT (x 104/°F)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 MTC AREA OF ACCEPTABLE OPERATION (0%,0.5)
(100%,0)
(50%, 0.0)
(100%,-0.2)
(0%,-4.4)
(100%,-4.4)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit
Revision 25 Page 17 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
5 10 15 20 0
10 20 30 40 50 60 MINIMUM REQUIRED POWER REDUCTION
(% OF RATED THERMAL POWER)
TIME AFTER DEVIATION, MINUTES FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20 100% to
>80% RTP 16 12 8
4 0
15 80% to
>70% RTP 12 9
6 3
10 70% to
>45% RTP 8
6 4
2 5
45% RTP 4
3 2
1
- WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:
- > 95 % RATED THERMAL POWER
- COLSS IN SERVICE AND CEACS IN SERVICE
- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %
- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION
Revision 25 Page 18 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 70.87%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power 20% and < 70.87%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equation:
TIL5 = (172.5" x Fractional Power) - 64.5" (for power 37.39% and 100%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 25 Page 19 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Fully Withdrawn (FW) is defined as > 147.75 (Pulse Counter) and > 145.25 (RSPT).
No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150* 120 90 60 150*
30 120 0
90 150*
60 120 30 90 0
60 150*
30 120 0
90 150*
60 120 30 90 0
60 30 0
FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%.
CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 54.97%.
CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (250.9" x Fractional Power) + 9.82" (for power 20% and < 54.97%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) - 80.18" (for power 31.96% and 75.00%).
TIL5 = 108" (for power lever 75.00%).
TRANSIENT INSERTION LIMIT GROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMIT GROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMIT GROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
Revision 25 Page 20 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN)
FRACTION OF RATED THERMAL POWER FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION RESTRICTED LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES)
TRANSIENT INSERTION LIMIT (75.0 INCHES)
(50% RATED THERMAL POWER)
Revision 25 Page 21 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0.0 5.0 10.0 15.0 20.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 AZIMUTHAL POWER TILT (%)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)
REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION
Revision 25 Page 22 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 0
5 10 15 20 25 50 60 70 80 90 100 COLSS DNBR POWER OPERATION LIMIT REDUCTION
(% OF RATED THERMAL POWER)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)
(80, 5)
(70, 0)
Revision 25 Page 23 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)
(-0.1, 1.93)
(-0.1, 2.28)
(0.06, 2.38)
(0.05, 2.00)
(0.1, 2.38)
(0.1, 2.00)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 25 Page 24 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT 3.0 3.1 3.2 3.3 3.4 3.5 3.6
-0.20
-0.15
-0.10
-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)
(-0.1, 3.27)
(0.0, 3.41)
(0.1, 3.41)
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
Revision 25 Page 25 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 25 Page 26 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 Keff > 0.97 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 25 Page 27 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 Keff > 0.96 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour ONA 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1 hour ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 25 Page 28 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Keff > 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed
Revision 25 Page 29 of 29 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 0
1 2
3 3
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4 hours 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1 hour 4 not on SCS 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 not on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 & 5 on SCS 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2 hours 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> ONA 6
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ONA ONA Notes:
SCS = Shutdown Cooling System ONA = Operation Not Allowed