View source for W3F1-2014-0033, Core Operating Limits Report Cycle 20 Revision 0, Waterford Steam Electric Station, Unit 3

{{Adams
| number = ML14132A130
| issue date = 05/12/2014
| title = Core Operating Limits Report Cycle 20 Revision 0, Waterford Steam Electric Station, Unit 3
| author name = Jarrell J
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000382
| license number = NPF-038
| contact person = 
| case reference number = W3F1-2014-0033
| document type = Fuel Cycle Reload Report, Letter type:W
| page count = 51
}}

=Text=
{{#Wiki_filter:Enteigy W3F1-2014-0033 May 12, 2014 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

==Subject:==
Core Operating Limits Report-Cycle 20 Revision 0 Waterford Steam Electric Station, Unit 3 Docket No.50-382 License No.NPF-38 Entergy Operations, Inc.17265 River Road Killona, LA 70057-3093 Tel 504 739 6685 Fax 5047396698 jjarrel@entergy.com John P.Jarrell III Manager-Regulatory Assurance Waterford 3 

==Dear Sir or Madam:==
Waterford 3 Technical Specification 6.9.1.11.3 requires submittal of the Core Operating Limits Report for each reload cycle including any mid-cycle revisions or supplements thereto.Attached is the Waterford 3 Core Operating Limits Report for reload cycle 20.If you have any questions concerning this submittal, please contact John P.Jarrell, Regulatory Assurance Manager, at (504)739-6685.There are no new commitments contained in this submittal.
Sincerely,/JPJ/LLB 

==Attachment:==

Waterford 3 Core Operating Limits Report Cycle 20 Revision 0 NUCLEAR QUAUTY RELATED EN-Ll-106 REV.13---En!ergy MANAGEMENT
.MANUAL INFORMATIONAL USE NRC Correspondence ATTACHMENT 9.4 NRC SuBMITrAL REvIEw Sheet 1 of 2 (Typical)Letter#: W3F1-2014-0033 Response Due: 5/14/2014 

==Subject:==
Core Operating Limits Report (COLR)-Date Issued for Review: 5/11/2014 Cycle 20 Revision 0.Per TS 6.9.1.11.3 including any mid-cycle revisions or supplements thereto.Correspondence Preparer I Phone#: Lillian Brown!504-739-7384 Section I Letter Concurrence and Agreement to Perform Actions POSITION I NAME Action Signature (concurrence, certification, etc.)(sign, interoffice memo, e-mail, or telecom)NA NA NA COMMENTS Enclosure to this correspondence does not require certification since the report was reviewed and approved in accordance with an established process.(Reference EN-LI-I 06 section 5.3 notes)I Section II Correspondence Screening Does this letter contain commitments?
If"yes,"identify the commitments with due Yes El dates in the submittal and in Section III.When fleet letters contain commitments, a No PCRS LO (e.g., LO-LAR, LO-WT)should be initiated with a CA assigned to each applicable site to enter the commitments into the site's commitment management system.Does this letter contain any information or analyses of new safety issues performed at NRC Yes El request or to satisfy a regulatory requirement?
If"yes,"reflect requirement to update the No UFSAR in Section III.Does this letter require any document changes (e.g., procedures, DBDs, FSAR, TS Bases, Yes El etc.), if approved?If"yes,"indicate in Section Ill an action for the responsible No department to determine the affected documents.(The Correspondence Preparer may indicate the specific documents requiring revision, if known or may initiate an action for review.)Does this letter contain information certified accurate?If"yes,"identify the information Yes El and document certification in an attachment.(Attachment 9.5 must be used.)No EN-LI-I 06 REV 13 NUCLEAR I QuALIrv RELATED EN-LI-106 REV.13 Entergy MANAGEMENT 1 MANUAL INFORMATIONAL USE NRC Correspondence ATTAcHMENT 9.4 NRC SUBMITTAL REvIEw Sheet 2 of 2 Section III Actions and Commitments Commitments Due Date Responsible Dept.Note: When fleet letters contain commitments, a PCRS LO should be initiated with a CA assigned to each applicable site to enter the commitments into the sites commitment management system.NA NA NA Required Actions Note: Actions needed upon approval should be captured in the appropriate action trackinq system NA Due Date NA Responsible Dept.NA EN-LI-I 06 REV 13 W3FI-20 14-0033 Page 2 cc: Mr.Marc L.Dapas Regional Administrator U.S.Nuclear Regulatory Commission Region IV 1600 E.Lamar Blvd.Arlington, TX 7601 1-4511 RidsRgn4MailCenternrc.gov NRC Senior Resident Inspector Water-ford Steam Electric Station Unit 3 Marlone.Davis@nrc.gov Chris.Speer@nrc.gov NRC/NRR Project Manager for Water-ford 3 Michael.Orenaknrc.gov Alan.Wangnrc.gov Attachment to W3FI-2014-0033 Waterford 3 Core Operating Limits Report Cycle 20 Revision 0 (Attachment contains 46 pages)
Engineering Report No, WF3-NE-14-00002 Rev.0 Page 1 of 46 Entergy ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report Title: WSES-3 Cycle 20 Core Operating Limits Report Engineering Report Type: New Revision El Cancelled El Superseded
[]Superseded by:_______________
Applicable Site(s)IP1 P2 El P3 El JAF El PNPS El vv El wpo El ANO1 ANO2 El ECH Q GGNS El RBS El WF3 PLP El EC No.4j4 Report Origin: Entergy El Vendor Vendor Document No.: Quality-Related:
Yes El No Prepared by: C.G.Eastus/L-".E 9 t')Date:________Responsible Engineer (Print Name/Sign)
Design Verified: N.Pazooki/P--Date:________Design Verifier-(f required)rint Name/Sign)
Revied by: L.E.Muster I 4&Date: 1//I)Reviewer P nt Nam1S?1)Approved bV F H Smith/, Date:.j/2'iJO (j Supervisor) anager (Pnnt Name/Sign)
Revision Summary WF3-NE-14-00002, Revision 0 Page 2 of 46 Revision 0 Initial issue of the report WF3-NE-14-00002, Revision 0 Page 3of46 Table of Contents Revision Summary 2 1.0 Scope and Objectives 4 2.0 Input Documents 4 3.0 Assumptions 4 4.0 Detailed Discussion 4 5.0 Operating Experience 4 6.0 Summary of Results 4 7.0 Conclusions and Recommendations 4 8.0 References 4 9.0 Attachments 5
WF3-NE-14-00002, Revision 0 Page 4 of 46 1.0 Scope and Objectives This report describes the development of the Waterford-3 Cycle 20 (W3C20)Core Operating Limits Report (COLR).The report is developed by updating the previous cycle COLR (Input Document (ID)2.1)with information from the W3C20 Reload Analysis Report (ID 2.2)and the W3C20 Setpoints Document (ID 2.3).2.0 Input Documents The input documents used to develop the W3C20 COLR include the following:
2.1."Entergy Operations Waterford-3 Core Operating Limits Report for Cycle 19 Revision 2,"October 24, 2013.2.2.Letter, R.A.Loretz to C.Eastus,"Waterford Steam Electric Station Unit 3 Cycle 20 Final Reload Analysis Report,"NF-WTFD-14-5, February 17, 2014.See also Engineering Report WF3-NE-14-00001 2.3.Letter, R.A.Loretz to C.Eastus,"Startup Test and Setpoints Transmittal for Waterlord-3 Cycle 20,"NF-WTFD-14-12, April 11, 2014.3.0 Assumptions Historically, information for the COLR update is included in the cycle specific RAR and the cycle specific setpoints analysis.4.0 Detailed Discussion ID 2.2 contains the non-setpoints related information necessary to update the COLR.The document has sections specifically addressing the information necessary to update the COLR based upon the cycle specific analysis performed by the fuel vendor (Westinghouse).
Setpoints related changes are provided in ID 2.3.The received information was applied to 1D2.1.The resulting W3C20 COLR is found in Attachment 9.1.5.0 Operating Experience A PCRS search was performed looking for issues related to the development of a COLR as described here.None were found.6.0 Summary of Results Using vendor provided information; the W3C1 9 Rev.2 COLR was updated to reflect Cycle 20 information.
7.0 Conclusions and Recommendations The W3C20 Revision 0 COLR has been developed and is acceptable to use.8.0 References None WF3-NE-14-00002, Revision 0 Page 5 of 46 9.0 Attachments 9.1 W3C20 Revision 0 COLR (using formatting and numbering appropriate for the COLR).
Attachment 9.1 Waterford-3 Cycle 20 COLR Revision 0 WF3-NE-14-00002, Revision 0 Page 6 of 46 ENTERGY OPERATIONS WATERFORD 3 CORE OPERATING LIMITS REPORT FOR CYCLE 20 REVISION 0 WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 20, REVISION 0 INDEX PAGE I.INTRODUCTION 5 II.6 3.1.1.1 COLR3/4 1-1 3.1.1.2 COLR3/4 1-3 3.1.1.3 COLR 314 1-4 3.1.2.9 COLR3/4 1-15 3.1.3.1 COLR 3/4 1-18 3.1.3.6 COLR 3/4 1-25 3.2.1 COLR 3/4 2-1 3.2.3 COLR3!42-4 3.2.4 COLR 3/4 2-6 3.2.7 COLR 3/4 2-12 3.9.1 COLR3/49-1 III.METHODOLOGIES 38 LIST OF EFFECTIVE PAGES Revision 0 Pages 1-6, COLR3/4 1-1, 1-3, 1-4, 1-15, 1-18, 1-25, 2-1, 2-4, 2-6, 2-12, 9-1, and Pages 38-40 AFFECTED TECHNICAL SPECIFICATIONS Shutdown Margin-Any CEA Withdrawn Shutdown Margin-All CEAs Fully Inserted Moderator Temperature Coefficient Boron Dilution Movable Control Assemblies
-CEA Position Regulating and Group P CEA Insertion Limits Linear Heat Rate Azimuthal Power Tilt-Tq DNBR Margin Axial Shape Index Boron Concentration WATERFORD 3 Page 2 CYCLE 20 REVISION 0 LIST OF FIGURES PAGE COLR Figure 1 Shutdown Margin Versus Cold Leg Temperature COLR 3/4 1-3A COLR Figure 2 Moderator Temperature Coefficient Versus%of COLR 3/4 1-4A Rated Thermal Power COLR Figure 3 Required Power Reduction After Single CEA COLR 3/4 1-18A Deviation COLR Figure 4 Regulating CEA Group Insertion Limits Versus COLR 3/4 1-25A Thermal Power COLR Figure 5 Group P CEA Group Insertion Limits Versus COLR 3/4 1-25B Thermal Power COLR Figure 6 Not Used COLR 3/4 2-lA COLR Figure 7 Not Used COLR 3/4 2-lB COLR Figure 8 Allowable DNBR with Any CEAC Operable COLR 3/4 2-6A (COLSS Out of Service)COLR Figure 8A Subset of Allowable DNBR with Any CEAC Operable COLR 3/4 2-6B (COLSS Out of Service)COLR Figure 8.1 Not Used COLR 3/4 2-6C COLR Figure 8.1A Not Used COLR 3/4 2-6D COLR Figure 9 Allowable DNBR with No CEAC(s)Operable COLR 3/4 2-6E (COLSS Out of Service)COLR Figure 9A Subset of Allowable DNBR with No CEAC(s)Operable COLR 3/4 2-6F (COLSS Out of Service)COLR Figure 9.1 Not Used COLR 3/4 2-6G COLR Figure 9.1A Not Used COLR 3/4 2-6H LIST OF EFFECTIVE FIGURE PAGES Revision 0 COLR 3/4 1-3A, 1-4A, 1-18A, 1-25A, 1-25B, 2-lA, 2-1B, 2-6A, 2-6B, 2-6C, 2-6D, 2-6E, 2-6F, 2-6G, 2-6H WATERFORD 3 Page 3 CYCLE 20 REVISION 0 LIST OF TABLES PAGE COLR Table 1 Required Monitoring Frequencies for Backup COLR 3/4 1-15A Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff Greater Than 0.98.COLR Table 2 Required Monitoring Frequencies for Backup COLR 3/4 1-15B Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff Greater Than 0.97 and Less Than or Equal to 0.98.COLR Table 3 Required Monitoring Frequencies for Backup COLR 3/4 1-15C Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff Greater Than 0.96 and Less Than or Equal to 0.97.COLR Table 4 Required Monitoring Frequencies for Backup COLR 3/4 1-1 5D Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff Greater Than 0.95 and Less Than or Equal to 0.96.COLR Table 5 Required Monitoring Frequencies for Backup COLR 3/4 1-1 5E Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff Greater Than or Equal to 0.95.LIST OF EFFECTIVE TABLE PAGES Revision 0 COLR 3/4 1-15A through COLR 3/4 1-15E WATERFORD 3 Page 4 CYCLE 20 REVISION 0 WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 20, REVISION 0 I.INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR)has been prepared in accordance with the requirements of Waterford 3 Technical Specification 6.9.1.11 for Waterford 3 Cycle 20.The core operating limits have been developed using the NRC approved methodologies specified in Section III.This is Revision 0 of the Cycle 20 COLR.The major changes between the Cycle 20, Revision 0, COLR and the Cycle 19, Revision 2, COLR are listed below: Section 3.2.7 was revised to remove a burnup restriction on the COLSS Operable ASI Limits for 50%power conditions.
WATERFORD 3 Page 5 CYCLE 20 REVISION 0 Ii AFFECTED TECHNICAL SPECIFICATIONS WATERFORD 3 Page 6 CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT SHUTDOWN MARGIN-ANY CEA WITHDRAWN 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 5.15%/xklk when Tavg is greater than 200&deg;F or 2.0%Ak/k when Tavg is less than or equal to 200&deg;F.WATERFORD 3 COLR 3/4 1-1 CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT SHUTDOWN MARGIN-ALL CEAs FULLY INSERTED 3.1.1.2 The SHUTDOWN MARGIN shall be maintained within the region of acceptable operation of COLR Figure 1.WATERFORD 3 COLR 3/4 1-3 CYCLE 20 REVISION 0 5 4 I 0 z C,)2 I COLR Figure 1 600 6 Shutdown Margin Versus Cold Leg Temperature (All CEAs Fully Inserted)0 0 100 200 300 400 500 Cold Leg Temperature
(&deg;F)WATERFORD 3 COLR 3/4 1-3A CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT MODERATOR TEMPERATURE COEFFICIENT 3.1.1.3 The Moderator Temperature Coefficient (MTC)shall be maintained within the region of acceptable operation of COLR Figure 2.WATERFORD 3 COLR 3/4 1-4 CYCLE 20 REVISION 0 Moderator Temperature Coefficient Versus%of Rated Thermal Power a.&deg;-2 x C-)-2.5-3-3.5-4-4.5 0 10 (0.0, 0.5)0.5 0-0.5-1 Unacceptable Operation___z:h-r Acceptable Operation: (0.0, 39)(100,-3.9)Unacceptable Operation 20 30 40 50 60 70 80 90 100%of Rated Thermal Power COLR Figure 2 WATERFORD 3 COLR 3/4 1-4A CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT BORON DILUTION 3.1.2.9 See COLR Tables 1 through 5 for required RCS boron concentration monitoring frequencies and Charging Pump operation limits.SURVEILLANCE REQUIREMENTS Each required boron dilution alarm shall be adjusted to less than or equal to 1.75 times (1.75x)the existing neutron flux (cps)at the following frequencies:
a.No sooner than one half hour after shutdown and no later than 1 hour after shutdown.b.At least once per one-half (1/2)hour if the reactor has been shut down>0.5 hour but<2 hours c.At least once per hour if the reactor has been shutdown 2 hours but<10 hours.d.Atleastonce per 5 hours if the reactor has been shutdown>10 hours but<25 hours.e.At least once per 24 hours if the reactor has been shut down 25 hours but<21 days.f.At least once per 7 days, if the reactor has been shutdown 21 days.WATERFORD 3 COLR 3/4 1-15 CYCLE 20 REVISION 0 COLR TABLE I REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff GREATER THAN 0.98 Keff>0.98 OPERATIONAL Number of Operating Charging Pums*MODE 0 1 2 3 3 12 hours 0.75 hours Operation not allowed**4 12 hours Operation not allowed**5 8 hours Operation not allowed**RCS filled 5 8 hours Operation not allowed**RCS partially drained 6 Operation not allowed***Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.
**The precluded number of charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.WATERFORD 3 COLR 3/4 1-15A CYCLE 20 REVISION 0 COLRTABLE2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff GREATER THAN 0.97 AND LESS THAN OR EQUAL TO 0.98 0.98 Kff>0.97 OPERATIONAL Number of Operating Charging Pumps*MODE 0 1 2 3 3 12 hours 2.0 hours 0.5 hours Operation not allowed**4 12 hours 0.75 hours Operation not allowed**5 8 hours 0.75 hours Operation not allowed**RCS filled 5 8 hours 0.5 hours Operation not allowed**RCS partially drained 6 Operation not allowed***Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.
**The precluded number of charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.WATERFORD 3 COLR 3/4 1-15B CYCLE 20 REVISION 0 COLR TABLE 3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff GREATER THAN 0.96 AND LESS THAN OR EQUAL TO 0.97 0.97 Kff>0.96 OPERATIONAL Number of Operatincj Charcjing Pumps*MODE 0 1 2 3 3 12 hours 3.0 hours 1.25 hours 0.5 hours 4 12 hours 1.5 hours Operation not allowed**5 8 hours 1.5 hours Operation not allowed**RCS filled 5 8 hours 0.75 hours Operation not allowed**RCS partially drained 6 Operation not allowed***Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.
**The precluded number of charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.WATERFORD 3 COLR 3/4 1-15C CYCLE 20 REVISION 0 COLRTABLE4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff GREATER THAN 0.95 AND LESS THAN OR EQUAL TO 0.96 O.96 Keff>O.9 S OPERATIONAL Number of Operating Charging Pumps*MODE 0 1 2 3 3 12 hours 4.0 hours 2.0 hours 1.0 hours 4 12 hours 2.25 hours 0.75 hours Operation not allowed**5 8 hours 2.0 hours 0.75 hours Operation not allowed**RCS filled 5 8 hours 2.0 hours 0.5 hours Operation not allowed**RCS partially drained 6 Operation not allowed***Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.
**The precluded number of charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.WATERFORD 3 COLR 3/4 1-15D CYCLE 20 REVISION 0 COLR TABLE 5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff LESS THAN OR EQUAL TO 0.95 Keff 0.95 OPERATIONAL Number of Operating Charging Pums*MODE 0 1 2 3 3 12 hours 5.0 hours 2.0 hours 1.0 hours 4 12 hours 2.75 hours 1.0 hours Operation not allowed**5 8 hours 3.0 hours 1.0 hours 0.5 hours RCS filled 5 8 hours 2.5 hours 0.75 hours Operation not allowed**RCS partially drained 6 24 hours 2.25 hours 0.5 hours Operation not allowed***Charging pump OPERABILITY for any period of time shall constitute OPERABILITY for the entire monitoring frequency.
**The precluded number of charging pumps shall be verified to be inoperable by racking out their motor circuit breakers.WATERFORD 3 COLR 3/4 1-15E CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT MOVABLE CONTROL ASSEMBLIES
-CEA POSITION 3.1.3.1.a With one CEA trippable but misaligned from any other CEA in its group by more than 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with COLR Figure 3.3.1.3.1.b With one or more CEAs trippable but misaligned from any other CEAs in its group by more than 7 inches but less than or equal to 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with COLR Figure 3.NOTES 1.Item 3.1.3.1.a corresponds with ACTION"c"of Technical Specification 3.1.3.1.2.Item 3.1.3.1.b corresponds with ACTION"d"of Technical Specification 3.1.3.1.WATERFORD 3 COLR 3/4 1-18 CYCLE 20 REVISION 0 30 0 0 E a, I a)Ca 20 0 t a, E a)U&#xa3;15 0 4-U D a, I Required Power Reduction After Single CEA Deviation*
Time After CEA Deviation (Minutes)COLR Figure 3*When thermal power is reduced to 60%of rated thermal power per this limit curve, further reduction is not required by this Technical Specification.
60 0 0 15 30 45 WATERFORD 3 COLR 3/4 1-18A CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT REGULATING AND GROUP P CEA INSERTION LIMITS 3.1.3.6 The regulating CEA groups and Group P CEAs shall be limited to the withdrawal sequence and to the insertion limits shown on COLR Figure 4 (regulating groups)and Figure 5 (Group P).WATERFORD 3 COLR 3/4 1-25 CYCLE 20 REVISION 0 Regulating CEA Group Insertion Limits Versus Thermal Power 108"100 90 80 70 60 a)0 D 50 E a 40.I-30 20 10 0 0-30 I I Group6 Group 5 0 30 60 90 60 90 120 150 Regulating CEA Group Position (Inches)COLR Figure 4 120-J 150 WATERFORD 3 COLR 3/4 1-25A CYCLE 20 REVISION 0 Group P CEA Group Insertion Limits Versus Thermal Power I 0 0 E 0)I-80 70 30 100 90 108"120"60 50 40 20 10 0 0 15 30 45 60 75 90 105 120 135 Group P CEA Group Position (Inches)COLR Figure 5 150 WATERFORD 3 COLR 3/4 1-25B CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT LINEAR HEAT RATE 3.2.1 The linear heat rate shall be maintained:
a.12.9 kW!ft when COLSS is in service b.13.2 kW/ft when COLSS is out of service In accordance with Technical Specification 3.6.1.5 Action a, with the minimum containment average air temperature less than 95&deg;F but greater than or equal to 90&deg;F, the linear heat rate shall be maintained:
a.12.7 kW/ft when COLSS is in service b.13.0 kW!ft when COLSS is out of service WATERFORD 3 COLR 3/4 2-1 CYCLE 20 REVISION 0 COLR Figure 6 (Not Used)WATERFORD 3 COLR 3/4 2-lA CYCLE 20 REVISION 0 COLR Figure 7 (Not Used)WATERFORD 3 COLR 3/4 2-1 B CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT AZIMUTHAL POWER TILT-Tq 32.3 The measured AZIMUTHAL POWER TILT shall be maintained 0.03.WATERFORD 3 COLR 3/4 2-4 CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT DNBR MARGIN 3.2.4 The DNBR margin shall be maintained by one of the following methods: a)When COLSS is in service and neither CEAC is operable: maintain COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 13%RATED THERMAL POWER.b)When COLSS is out of service and at least one CEAC is operable: operate within the region of acceptable operation shown on COLR Figure 8 (or 8A as appropriate), using any operable CPC channel.c)When COLSS is out of service and neither CEAC is operable: operate within the region of acceptable operation shown on COLR Figure 9 (or 9A as appropriate), using any operable CPC channel.NOTES The various DNBR limit lines shown between the vertical ASI limit lines at+/-0.12 and+/-0.22 on Figures 8, 8A, 9, and 9A represent the minimum CPC-calculated DNBR value required for operation in the power range displayed in the area above each line.Operation at lower power levels requires that a larger DNBR value be maintained.
For example, with ASI equal to-0.12 and a core power of 85%, CPC calculated DNBR must be a minimum of 2.62 with any CEAC Operable.At 79%power and the same ASI value with any CEAC Operable, the calculated DNBR must be at least 3.12.At 65%power and the same ASI value, DNBR must be a minimum of 4.28.At 90%power and an ASI value of+0.08, DNBR must be no less than 2.37.2.The vertical ASI limit lines shown at+/-0.12 and+/-0.22 on Figures 8, 8A, 9, and 9A may be considered as extending beyond the maximum DNBR value on the Y axis of the charts.Therefore, when monitoring DNBR with these figures, compliance is achieved at all power levels shown on a given figure when DNBR is greater than the largest DNBR value on the vertical scale.3.Figure 8A is provided to offer better resolution for the four power ranges in the lower portion of Figure 8.Figure 9A is provided to offer better resolution for the four power ranges in the lower portion of Figure 9.4.Equations are provided on Figures 8, 8A, 9, and 9A to assist in determining DNBR limits in the sloped portions of the plots.WATERFORD 3 COLR 3/4 2-6 CYCLE 20 REVISION 0 z E E C)0 C)Core Average ASI (COLR Figure 8)CYCLE 20 REVISION 0 Allowable DNBR with Any CEAC Operable (COLSS Out of Service)------Accptabie-Operation----
20%S Power S 100%(-0.04, 7.94)(-0.12, 7.65)\1.50-0.3-0.2-0.1 0.0 0.1 0.2 0.3 WATERFORD 3 COLR 3/4 2-6A Subset of Allowable DNBR with Any CEAC Operable (COLSS Out of Service)Core Average ASI (COLR Figure 8A)WATERFORD 3 COLR 3/4 2-6B CYCLE 20 REVISION 0 Acceptable Operation 70%5 PowerS 100%=(1.400 x AOl)+.200 4.00 3.75-----F.-----3.50 (+0.12, 3.33)3.25 (+0.03, 3.33)(.0.12, 3.12)cceptable Operation 80%5 Power 100%z E E C.)0 C.)4.00 3.75 3.50 3.25 3.00 2.75 2.50 2.25 2.00 1.75 1.50 (.0.12, 2.62)(.12, 2.81)Acceptable Operation 90%5 PowerS 100%DNBR=(0.750x ASI)+2310 (+0.08, 2.37)(+0.12, 2.37)(.0.12, 2.22)Acceptable Operation (.0.12, 2.04)(+0.12, 2.17)ONBR=(O.5420ASI)*2.105 Unacceptable Operation 3.00 2.75 2.50 2.25 2.00 1.75 1.50-0.2-0.1 0.0 0.1 0.2 COLR Figure 8.1 (Not Used)WATERFORD 3 COLR 3/4 2-60 CYCLE 20 REVISION 0 COLR Figure 8.IA (Not Used)WATERFORD 3 COLR 3/4 2-6D CYCLE 20 REVISION 0 Ix z E E ci a ci Allowable DNBR with No CEAC(s)Operable (COLSS Out of Service)AptbIe Opertiofl 20%5 Power 50%20%SPower<50%
(+0.15, 7.94-_________
(-0.04, 7.94)(+0.12, 7.94)---------(-0.12, 7.65)-fl.,fi,,,, Acceptable Operation 20%S Power 5100%8.25=8.00 7.75-7.50 7.25 7.00 6.75 6.50 6,25 6.00 8.25 8.00 7.75 7.50 7.25___________loNeR=(3.778e ASh+8001 ,j (+0.22, 7.34)(-0.22, 7.26)X+I)'Acceptable Operation 50%5 Power 5100%Core Average ASI (COLR Figure 9)WATERFORD 3 COLR 3/4 2-6E CYCLE 20 REVISION 0 WATERFORD 3 COLR 3/4 2-6F CYCLE 20 REVIS!ON 0 (-0.12, 5.28)Subset of Allowable DNBR with No CEAC(s)Operable (COLSS Out of Service)Acceptable Operation 50%Power 100%05, 5.48)IDNBR=(2765 x AS)*56191 (+0.12, 5.48)5.75 5.50 5.25 5.00 flL_L.ejJLdLJI iJJtI dLIttIt-70%PowerS 100%DNBR=(1.923 x ASI(*4.091 5 75 5.50 5.25 5.00 4.75 4.50 4.25 E 4.00 C C-)a.3.75 C.)3.50 3.25 3.00 2.75 2.50 2.25 4 n 1,4.11)(-0.12, 3.86)(+0.12, 4.11)Acceptable Operation 90%5 Power 5100%1.25 4.00 3.75 3.50 3.25 3.00 2.75 2.50 2.25 x ASI(+2 941 (+0.12, 3.00)(-0.12, 2.80)l1 176 Acceptable operati:: (+07, 2.79)(+0 12 (-0.12, 2.60)Unacceptable Operation-0.2-0.1 0.0 0.1 0.2 Core Average ASI (COLR Figure 9A)
COLR Figure 9.1 (Not Used)WATERFORD 3 COLR 3/4 2-6G CYCLE 20 REVISION 0 COLR Figure 9.IA (Not Used)WATERFORD 3 COLR 3/4 2-6H CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT AXIAL SHAPE INDEX 3.2.7 The AXIAL SHAPE INDEX (ASI)shall be maintained within the following limits: COLSS Operable-0.16 ASI S+016 for THERMAL POWERS 50%of RATED THERMAL POWER-0.26 5 ASP 5+0.26 for THERMAL POWERS from 20%to<50%of RATED THERMAL POWER COLSS Out of Service-0.12 5 ASI 5+012 for THERMAL POWERS 50%of RATED THERMAL POWER-0.22 ASI 5+0.22 for THERMAL POWERS from 20%to<50%of RATED THERMAL POWER WATERFORD 3 COLR 3/4 2-12 CYCLE 20 REVISION 0 CORE OPERATING LIMITS REPORT BORON CONCENTRATION 3.9.1 While in Mode 6, the RCS boron concentration shall be maintained sufficiently to ensure that the more restrictive of the following reactivity conditions is met: a.Either Keff of 0.95 or less, or b.A boron concentration of greater than or equal to 2050 ppm.WATERFORD 3 COLR 3/4 9-1 CYCLE 20 REVISION 0 III.METHODOLOGIES The analytical methods used to determine the core operating limits listed above are those previously reviewed and approved by the NRC in: 1."Qualification of the PHOENIX-P!ANC Nuclear Design System for Pressurized Water Reactor Cores,"WCAP-1 1596-P-A, June 1988;"ANC: A Westinghouse Advanced Nodal Computer Code,"WCAP-1 0965-P-A, September 1986;and"ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery,"
WCAP-1 0965-P-A Addendum 1, April1989.(Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC and IBW), and 3.9.1 Boron Concentration).
2."C-E Method for Control Element Assembly Ejection Analysis,"
CENPD-190-A, Revision 0, January 1976.(Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt.)3."Modified Statistical Combination of Uncertainties" CEN-356(V)-P-A, Revision 1-P-A, May 1988.(Methodology for Specification 3.2.4.c and 3.2.4.d for DNBR Margin and 3.2.7 for ASI.)4."Calculative Methods for the CE Large Break LOCA Evaluation Model For the Analysis of C-E and W Designed NSSS,"CENPD-132, Supplement 3-P-A, June 1985.(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI.)5."Calculative Methods for the ABB CE Small Break LOCA Evaluation Model,"CENPD-137-P, August 1974;Supplement 2-P-A, April 1998.(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI.)6."Technical Description Manual for the CENTS Code,"WCAP-15996-P-A, Revision 1, March 2005.(Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies
-CEA Position, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, and 3.2.4.b for DNBR Margin)WATERFORD 3 Page 38 CYCLE 20 REVISION 0 7."Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs,"CENPD-404-P-A, November 2001.(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for AS I).8."Qualification of the Two-Dimensional Transport Code PARAGON,"WCAP 16045-P-A, August 2004.(Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and Group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC&IBW), 3.2.4.b for DNBR Margin and 3.9.1 Boron Concentration).
9."Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs,"WCAP-1 6072-P-A, Revision 0, August 2004 (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).10."CE 16 x 16 Next Generation Fuel Core Reference Report,"WCAP-1 6500-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse)
Topical Report (TR)WCAP-16500-P, Revision 0,"CE[Combustion Engineering]
16x16 Next Generation Fuel[(NGF)]Core Reference Report,"(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI).11."Optimized ZIRLO TM ,"WCAP-1 2610-P-A and CENPD-404-P-A Addendum 1-A, July 2006.(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI.)12."Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes,"WCAP-1 6523-P-A Revision 0, August 2007;and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse)
Topical Report (TR), WCAP-1 6523-P,"Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes,"(Methodology for Specification 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin.)13."ABB Critical Heat Flux Correlations for PWR Fuel,"CENPD-387-P-A Revision 0, May 2000.(Methodology for Specification 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI.)WATERFORD 3 Page 39 CYCLE 20 REVISION 0 14."Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model-Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood"CENPD-132, Supplement 4-P-A, Addendum 1-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse)
Topical Report (TR)CENPD-1 32 Supplement 4-P-A, Addendum 1-P,"Calculative Methods for the CE[Combustion Engineering]
Nuclear Power Large Break LOCA Evaluation Model-Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood,"(Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).15."Application of CE Setpoint Methodology for CE 1 6x1 6 Next Generation Fuel (NGF),"WCAP 16500 P-A, Supplement 1, Revision 1, December 2010.(Methodology for Specification 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin.)WATERFORD 3 Page 40 CYCLE 20 REVISION 0}}