W3F1-2013-0032, Core Operating Limits Report - Cycle 19 Revision 1

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Core Operating Limits Report - Cycle 19 Revision 1
ML13240A127
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/26/2013
From: Pellegrin B
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2013-0032
Download: ML13240A127 (48)
v • d • e


Text

J Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6203 Fax 504 739 6698 bpelleg@entergy.com Bryan Pellegrin Licensing Manager, Acting Waterford 3 W3F1-2013-0032 August 26, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Core Operating Limits Report - Cycle 19 Revision 1 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

Waterford 3 Core Operating Limits Report for Cycle 19 was revised to correct a typographical error in Section 3.2.7, Axial Shape Index. Cycle 19 Axial Shape Index limit for COLSS Operable (when greater than 250 EFPD) required ASI to be "less than" +0.13 and greater than or equal to -0.16 when Thermal Power was greater than or equal to 50% of Rated Thermal Power; this was revised as follows: Cycle 19 Axial Shape Index limit for COLSS Operable (when greater than 250 EFPD) requires ASI to be "less than or equal to" +0.13 and greater than or equal to -0.16 when Thermal Power is greater than or equal to 50% of Rated Thermal Power. Please note that Waterford 3 has not reached 250 EFPD for Cycle

19. Attached is Revision 1 to Core Operating Limits Report for Cycle 19.

Please note that even though the attached Waterford 3 Cycle 19 Core Operating Limits Report Revision 1 is complete, there is a pagination error which has been captured in the Corrective Action Program.

There are no new commitments contained in this submittal. If you have any questions concerning this submittal, please contact Bryan Pellegrin at 504-739-6203.

Sincerely, BJfE

Attachment:

Waterford 3 Cycle 19 Core Operating Limits Report Revision 1

i W3F11-2013-0032 Page 2 cc: Mr. Steven A. Reynolds RidsRgn4MailCenter@nrc.gov Regional Administrator, Acting U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4125 NRC Senior Resident Inspector marlone.davis@nrc.gov Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Kaly.Kalyanam@nrc.gov Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001

Attachment W3F1-2013-0032 Waterford 3 Cycle 19 Core Operating Limits Report Revision 1 (Attachment contains 45 pages)

Engineering Report No. WF3-NE-12-00002 Rev. 1 Page 1 of 46

-Eideqiry ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report

Title:

WSES-3 Cycle 19 Core Operating Limits Report Engineering Report Type:

New Er Revision 0 Cancelled El Superseded [I Superseded by:

Applicable Site(s) uIP Er IP2 Fr IP3 El JAF Er PNPS 11 VY ErWPO ANO1 ANO2 [] ECH Er GGNS Er RBS [I WF3 0PLP i EC No. 44168 Report Origin: Z Entergy El Vendor Vendor Document No.:

Quality-Related: 0 Yes 0 No C. G. Eastus/ -L Prepared by: Date: ,) j/,. "

Responsible Engineer (PrihrlýameSign)

Design Verified: P.0.Loehrf -"lŽ'('

, ,. Date: _/t____

Design Verifier (if requi;t, i.nt Name/Sign)

Reviewed by: M. E Mason, / Date: ________

Reviewer (PrTt Name/Sign)

Approved by R E. Griffith ," 6ý,, -7 - Date: ____

Superv:sor ' Manager (7lint Name/Sign)

WF3-NE-12-00002, Revision 1 Page 2 of 46 Revision Summary Revision 0 Initial issue of the report.

Revision 1 Revision to correct a typographical error in COLR Section 3.2.7.

WF3-NE-12-00002, Revision 1 Page 3 of 46 Table of Contents Revision Summary ...................................................................................................................... 2 1.0 Scope and Objectives ................................................................................................................. 4 2 .0 Inp u t Do c um e n ts ......................................................................................................................... 4 3 .0 Assu m ptio n s ............................................................................................................................... 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 R e fe re n ce s ................................................................................................................................. 4 9 .0 Atta c hm e nts ................................................................................................................................ 4

WF3-NE-12-00002, Revision 1 Page 4 of 46 1.0 Scope and Obiectives This report describes the development of the Waterford-3 Cycle 19 (W3C19) Rev.1 Core Operating Limits Report (COLR). The report is developed by updating the Cycle 19 Rev. 0 COLR (Input Document (ID) 2.1) with information from the W3C19 Setpoints Document (ID 2.2).

2.0 Input Documents The input documents used to develop the W3C19 Rev.1 COLR include the following:

2.1. "Entergy Operations Waterford-3 Core Operating Limits Report for Cycle 19 Revision 0,"

December 13, 2012.

2.2. Letter, R. A. Loretz to C. Eastus, "Startup Test and Setpoints Transmittal for Waterford-3 Cycle 19," NF-WTFD-12-32, November 30, 2012.

3.0 Assumptions None 4.0 Detailed Discussion The information presented in ID2.2 was used to update Section 3.2.7 in the COLR so that the entire section is consistent in its application of the limits. The resulting W3C19 Rev.1 COLR is found in Attachment 9.1.

5.0 Operatinq 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 W3C19 Rev.0 COLR was updated to Revision 1.

7.0 Conclusions and Recommendations The W3C19 Revision 1 COLR has been developed and is acceptable to use.

8.0 References None 9.0 Attachments 9.1 W3C19 Revision I COLR (using formatting and numbering appropriate for the COLR).

WF3-NE-12-00002, Revision 1 Page 5 of 46 Attachment 9.1 Waterford-3 Cycle 19 COLR Revision 1

ENTERGY OPERATIONS WATERFORD 3 CORE OPERATING LIMITS REPORT FOR CYCLE 19 REVISION I

WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 19, REVISION 1 INDEX PAGE INTRODUCTION 5 I1. AFFECTED TECHNICAL SPECIFICATIONS 6 3.1.1.1 Shutdown Margin -Any CEA Withdrawn COLR 3/4 1-1 3.1.1.2 Shutdown Margin - All CEAs Fully Inserted COLR 3/4 1-3 3.1.1.3 Moderator Temperature Coefficient COLR 3/4 1-4 3.1.2.9 Boron Dilution COLR 3/4 1-15 3.1.3.1 Movable Control Assemblies - CEA Position COLR 3/4 1-18 3.1.3.6 Regulating and Group P CEA Insertion Limits COLR 3/4 1-25 3.2.1 Linear Heat Rate COLR 3/4 2-1 3.2.3 Azimuthal Power Tilt - Tq COLR 3/4 2-4 3.2.4 DNBR Margin COLR 3/4 2-6 3.2.7 Axial Shape Index COLR 3/4 2-12 3.9.1 Boron Concentration COLR 3/4 9-1 II1. METHODOLOGIES 38 LIST OF EFFECTIVE PAGES Revision 0 Pages 3-4,6, COLR 3/4 1-1, 1-3, 1-4, 1-15, 1-18, 1-25, 2-1, 2-4, 2-6, 9-1, and Pages 38 -40 Revision 1 1-2, 5, 2-12 WATERFORD 3 Page 2 CYCLE 19 REVISION 1

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 2-1A COLR Figure 7 Not Used COLR 3/4 2-1 B 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, 2-1A, 2-1B, 2-6A, 2-6B, 2-6C, 2-6D, 2-6E, 2-6F, 2-6G, 2-6H WATERFORD 3 Page 3 CYCLE 19 REVISION 1

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 1-15D 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 1-15E 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 19 REVISION 1

WATERFORD 3 CORE OPERATING LIMITS REPORT CYCLE 19, REVISION I 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 19. The core operating limits have been developed using the NRC approved methodologies specified in Section II1.This is Revision 1 of the Cycle 19 COLR.

The major changes between the Cycle 19, Revision 1, COLR and the Cycle 19, Revision 0, COLR are listed below:

Section 3.2.7 was revised to correct a typographical error in the COLSS Operable, greater than 250 EFPD positive ASI limit for >-50% power condition.

WATERFORD 3 Page 5 CYCLE 19 REVISION 1

II.AFFECTED TECHNICAL SPECIFICATIONS WATERFORD 3 Page 6 CYCLE 19 REVISION 1

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% Ak/k when Tavg is greater than 200 °F or 2.0% Ak/k when Tavg is less than or equal to 200 OF.

WATERFORD 3 COLIR 3/4 1-1 CYCLE 19 REVISION 1

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 19 REVISION 1

Shutdown Margin Versus Cold Leg Temperature (All CEAs Fully Inserted) 6 5

(500 OF, 4.6%)

4 Acceptable Operation 0

C,-

2 (400 OF, 1.5%)

1 Unacceptable Operation 0

0 100 200 300 400 500 600 Cold Leg Temperature (0 F)

COLR Figure 1 WATERFORD 3 COLR 3/4 1-3A CYCLE 19 REVISION 1

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 19 REVISION 1

Moderator Temperature Coefficient Versus % of Rated Thermal Power 0.5 (0.0,0.5) .Unacceptable Operation 0

(100, -0.2)

-0.5

-1 C -1.5 Q -2 Acceptable Operation

  • -2.5

-3

-3.5 (0.0, -3.9) (100, -3.9)

-4 Unacceptable Operation

-4.5 0 10 20 30 40 50 60 70 80 90 100

% of Rated Thermal Power COLR Figure 2 WATERFORD 3 COLR 3/4 1-4A CYCLE 19 REVISION 1

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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after shutdown.
b. At least once per one-half (1/2) hour if the reactor has been shut down > 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> but < 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
c. At least once per hour if the reactor has been shutdown > 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> but < 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
d. At least once per 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> if the reactor has been shut down > 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> but < 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
e. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the reactor has been shut down > 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 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 19 REVISION 1

COLR TABLE 1 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 Pumps*

MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed **

4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Operation not allowed**

5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Operation not allowed RCS filled 5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 19 REVISION 1

COLR TABLE 2 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 > Keff >0.97 OPERATIONAL Number of Operating Charging Pumps*

MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Operation not allowed**

4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed**

5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed**

RCS filled 5 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 /> 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 19 REVISION 1

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 _>Keff >0.96 OPERATIONAL Number of Operating Charging Pumps*

MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4 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 /> Operation not allowed**

5 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 /> Operation not allowed**

RCS filled 5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 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 19 REVISION 1

COLR TABLE 4 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 0.96 Ž_Keff >0.95 OPERATIONAL Number of Operating Charging Pumps*

MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed**

5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed**

RCS filled 5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 19 REVISION 1

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. 9 5 OPERATIONAL Number of Operating Charging Pumps*

MODE 0 1 2 3 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 5.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Operation not allowed**

5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> RCS filled 5 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 /> 0.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Operation not allowed**

RCS partially drained 6 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 19 REVISION 1

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 19 REVISION 1

Required Power Reduction After Single CEA Deviation 30 no 25 20 0

4-U 2

0 U

0 E

0-

. 1E5 15 0.

0 0

0 15 30 45 60 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.

WATERFORD 3 COLR 3/4 1-18A CYCLE 19 REVISION 1

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 19 REVISION 1

Regulating CEA Group Insertion Limits Versus Thermal Power 108" GR.

100 90 80 70 --

49 co

" 60 U 0"

0o oE a.50 U)E~

Ci Transient Insertion Limit 0 E

40 1 0E 1

30 Cf-E 20 60" GR.5 /5 10 60" GR. 6 120" GR. 6 0

Group 6 1

Group 5 0 30 60 90 120 150 0 30 60 90 120 150 Regulating CEA Group Position (Inches)

COLR Figure 4 WATERFORD 3 COLR 3/4 1-25A CYCLE 19 REVISION 1

Group P CEA Group Insertion Limits Versus Thermal Power 108", 120" 100 90 80 108", 72% ..

70 60 Transient Insertion Limit E 0

0.

w=-

50 z~

Eu 0 60" O,

0) 40 K Short Term Steady State 1 1 30 Insertion Limit 30" __oo__'00_0*

20 10 + + +/- 4 +/- + +

0 I + I I + I I- t 0 15 30 45 60 75 90 105 120 135 150 Group P CEA Group Position (Inches)

COLR Figure 5 WATERFORD 3 COLR 3/4 1-25B CYCLE 19 REVISION 1

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 0F but greater than or equal to 900 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 19 REVISION 1

COLR Figure 6 (Not Used)

WATERFORD 3 COLR 3/4 2-1 A CYCLE 19 REVISION 1

COLR Figure 7 (Not Used)

WATERFORD 3 COLR 3/4 2-1 B CYCLE 19 REVISION 1

CORE OPERATING LIMITS REPORT AZIMUTHAL POWER TILT- Tq 3.2.3 The measured AZIMUTHAL POWER TILT shall be maintained _<

0.03.

WATERFORD 3 COLR 3/4 2-4 CYCLE 19 REVISION 1

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

1. 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 19 REVISION 1

Allowable DNBR with Any CEAC Operable (COLSS Out of Service) 8.50 8.50 Acceptable AAcceptable Operation 8.25 8.25 Operationhe Operation 20% S Powerpe-*~o S 100% 20% S Power < 50%

20%:5 Power < 50% t___ 15, 7.94) 8.00 8.00

(-0.04, 7.94) (+0.12, 7.94 7.75 7.75

(-0.12, 7.65) 7.50 7.50 4 IDNBR = (3.778 x ASI) + 8.091 +0.22 7.34 7.25 7.25 (-0.22, 7.26) FDNBR= (-8.572 x ASI) + 9.226 7.00 7.00 6.75 6.75 6.50 6.50 Acceptable Operation 6.25 6.25 50% S Power:< 100%

6.00 6.00 5.75 5.75 W.5.50 5.50 00 E

5.25 5.25 5.00 DNBR = (2.046 x ASI)+ 4.520 5.00 0~

E, 4.75 4.75 (0.00.4.52) 4.50 (+0.12, 4.52) 4.50 4.25 4.25

(-0.12, 4.28)

Acceptable Ooeration 4.00 4.00 DNBR = (1.400 x ASQ)+ 3.288 70% < Power < 100%

3.75 3.75 3.50 (+0.03, 3.33) 3.50

(+0.12, 3.33) 3.25 3.25

(-0.12, 3.12) Acceptable Operation 3.00 3.00 DNBR = (1.000 x ASI)+ 2.740 .-- 80% < Power < 100% (+0.07, 2.81) (+0.12, 2.81) 2.75 2.75

(-0.12, 2.62)

Acceptable Operation 2.50 1.5

=(0.7x90%

< Power < 100% (+ , .7) (+0.12, 2.37)125 Eý --------- s-- 0% 2.25 2.25

(-012 2.2

(+0.12, 2.17) 20 2.00 (-0.12, 2.04) Uncepal-Oeato D-NBR-=(0"542x Asl) + 2.105 1.75 Uncepal Oprto 150 1.50

-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 Core Average ASI (COLR Figure 8)

WATERFORD 3 COLR 3/4 2-6A CYCLE 19 REVISION 1

Subset of Allowable DNBR with Any CEAC Operable (COLSS Out of Service)

E E

a.

L)

-0.2 -0.1 0.0 0.1 0.2 Core Average ASI (COLR Figure 8A)

WATERFORD 3 COLR 3/4 2-613 CYCLE 19 REVISION 1

COLR Figure 8.1 (Not Used)

WATERFORD 3 COLR 3/4 2-6C CYCLE 19 REVISION 1

COLR Figure 8.1A (Not Used)

WATERFORD 3 COLR 3/4 2-6D CYCLE 19 REVISION 1

Allowable DNBR with No CEAC(s) Operable (COLSS Out of Service)

O.ZD 8.25 Acceptable Operation Acceptable Operation Acceptable Operation 20% 5 Power <100% 20%5 Power <50%

8.00 20% < Power < 50% 8.00

(-0.04, 7.94) (+0.12, 7.94) 7.75 7.75 7.50 (-0.12, 7.65X 7.50 7.255 7DNBR= (3.778 A0) + 8.091 7.25

(-0.22, 7.26) 7.00 7.00 IDNBR= (-8.572 x AS1).+ 226 6.75 Acceptable Operation 6.75 50% 5 Power 5 100%

6.50 6.50 6.25 6.25 6.00 6.00 5.75 5.75 DNBR =(2.765 xASI) 5618 5.75 5.7 z

a 5.50 5.50 E (-0.05, 5.48) (+0.12, 5.48) 5.25 (-0.12, 5.28) 5.25 5.00 Acceptable Operation 5.00 70% 5 Power < 100%

a.) 4.75 4.75 4.50 4.50 4.50 DNBR =(1.923 x ASI)+ 4.091 45 4.25 1 4.25 4.00 1+0.01, 4.11) (+0.12, 4.11) 4.00 3.75 (-0.12, 3.86) 3.75 90% < Power 5 100%

3.50 3.50 3.25 DNBR=(1.176xASI)+2.941 3.25 3.00I .-- (+0.05. 3.001 9"."ow-<oo < I30(+0.12, 3.00) 3.00 95%8 Power 8 100%

2.75 2.7572.9 (-0.12, 2.80) O+012 2.79! 2.75 2.75

(-0.12, 2.60) Unacceptable 2.50 .......... 2.50 JUNB = (1.U05 X AN1) + 2.120

-42.25

-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 Core Average ASI (COLR Figure 9)

WATERFORD 3 COLR 3/4 ME CYCLE 19 REVISION 1

Subset of Allowable DNBR with No CEAC(s) Operable (COLSS Out of Service) 5.75 5.75 Acceptable Operation 50%:5 Power<5 100%

5.50 .50

(+0.12, 5.48)

(-0 .0.55 48)

(-0.12, 5.28) 5.25 5.25 DNBR = (2.765 x ASI) + 5.618 5.00 5.00 4.75 Acceptable Operation 4 .75 70% S Power< '100%

4.50 4 .50 ONBR = (1.923 x ASI) + 4.091 1 4.25 4 .25 z

E (+0.01, 4.11) (+0.12, 4.11)

E 4.00 44.00 C.)

(-0.12, 3.86)

0. 3.75 '*7R Acceptable Operation 90% 5 Power<5 100%

3.50 3.50 3.25 3.25 FDNBR =(1.176 xASI) + 2".1 (+0.05, 3.00) (+0.12, 3.00) 3.00 3.00 Acetal Oprto .07, 2.79)

(-0.12, 2.80) ** 95%: <Power S 100% __N2.75 (+0.12, 2.79) 2.75

(-0.12, 2.60) BR = (1.000 x ASl) +2.720 2.50 2.50 Unacceptable Operation 2.25 ' 225

-0.2 -0.1 0.0 0.1 0.2 Core Average ASI (COLR Figure 9A)

WATERFORD 3 COLR 3/4 2-6F CYCLE 19 REVISION 1

COLR Figure 9.1 (Not Used)

WATERFORD 3 COLR 3/4 2-6G - CYCLE 19 REVISION 1

COLR Figure 9.1A (Not Used)

WATERFORD 3 COLR 3/4 2-61-1 CYCLE 19 REVISION 1

CORE OPERATING LIMITS REPORT AXIAL SHAPE INDEX 3.2.7 The AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS Operable, through 250 EFPD

-0.16 - ASI -<+0.16 for THERMAL POWERS >-50% of RATED THERMAL POWER

-0.26 < ASI < +0.26 for THERMAL POWERS from 20% to <50%

of RATED THERMAL POWER COLSS Operable, greater than 250 EFPD

-0.16 <ASI < +0.13 for THERMAL POWERS > 50% of RATED THERMAL POWER

-0.26 < ASI < +0.26 for THERMAL POWERS from 20% to <50%

of RATED THERMAL POWER COLSS Out of Service

-0.12 < ASI < +0.12 for THERMAL POWERS > 50% of RATED THERMAL POWER

-0.22 < ASI < +0.22 for THERMAL POWERS from 20% to <50%

of RATED THERMAL POWER WATERFORD 3 COLR 3/4 2-12 CYCLE 19 REVISION 1

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 19 REVISION 1

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, April 1989. (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-1 32, 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-1 5996-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 44 CYCLE 19 REVISION 1

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 ASI).
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 ZIRLOTM, WCAP-12610-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-16523-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 45 CYCLE 19 REVISION 1

a P

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-1 32, 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 16x1 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 46 CYCLE 19 REVISION 1

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