Proposed Tech Specs Revising TS 3/4.2.3, Azimuthal Power Tilt, Action Statements & BasesML20058M202 |
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Waterford |
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Issue date: |
12/14/1993 |
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ENTERGY OPERATIONS, INC. |
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Shared Package |
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ML20058M195 |
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References |
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NUDOCS 9312200194 |
Download: ML20058M202 (7) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217K9011999-10-18018 October 1999 Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20211F3701999-08-24024 August 1999 Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207 ML20211F5501999-08-24024 August 1999 Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220 ML20210M9681999-08-0404 August 1999 Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions ML20210M9861999-08-0404 August 1999 Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown ML20210H2371999-07-29029 July 1999 Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20209H3191999-07-15015 July 1999 Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves ML20210D1071999-07-15015 July 1999 Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20209D4091999-07-0707 July 1999 Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207 ML20195B1811999-05-20020 May 1999 Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12 ML20203C4891999-02-0505 February 1999 Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension ML20199E0861999-01-12012 January 1999 Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174 ML20199D9851999-01-12012 January 1999 Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel ML20198G2401998-12-23023 December 1998 Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20196D2181998-11-30030 November 1998 Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants ML20154E4171998-10-0606 October 1998 Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle ML20154E1141998-10-0101 October 1998 Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys ML20153D5771998-09-23023 September 1998 Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable ML20153B4441998-09-18018 September 1998 Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation ML20151W5971998-09-11011 September 1998 Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7921998-08-12012 August 1998 Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7361998-07-29029 July 1998 Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model ML20236H1501998-07-0202 July 1998 Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition ML20249C8321998-06-29029 June 1998 Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432 ML20249C7901998-06-29029 June 1998 Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls ML20249A3101998-06-12012 June 1998 Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls ML20248B7611998-05-28028 May 1998 Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys ML20247P2431998-05-21021 May 1998 Proposed Tech Specs Re Design Feature Suppl ML20217P8411998-05-0101 May 1998 Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal ML20217D5181998-03-25025 March 1998 Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8 ML20198R1251998-01-21021 January 1998 Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys ML20198R3081998-01-21021 January 1998 Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements ML20197C6431997-12-22022 December 1997 Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section ML20199A1101997-11-13013 November 1997 Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20199A0011997-11-13013 November 1997 Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21 ML20217G2421997-10-0707 October 1997 Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8141997-09-25025 September 1997 Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G7131997-07-0707 July 1997 Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3 ML20141D8551997-06-26026 June 1997 Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases ML20140B1671997-06-0303 June 1997 Proposed Tech Specs,Modifying Action Requirements for TS 3/4.3.2 for SI Sys Sump Recirculation Actuation Signal ML20148G6631997-06-0303 June 1997 Proposed Tech Specs,Requesting Minimum Required Level in Condensate Storage Pool Be Increased from 82% to 91% to Account for Vortexing & Instrumentation Measurement Uncertainties ML20141K1741997-05-24024 May 1997 Proposed Tech Specs 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1-1, Removing Cycle Dependent Boron Concentration ML20141K1951997-05-24024 May 1997 Proposed Tech Specs 3/4.7.4 Modifying Ultimate Heat Sink, Table 3.7-3,by Incorporating More Restrictive Dry Cooling Tower Fan Requirements & Changes Wet Cooling Tower Water Consumption in TS Bases ML20140H0831997-05-0606 May 1997 Proposed Tech Specs Modifying Wording of SR 4.5.2.j by Replacing Venting ECCS Pump Casings & Discharge Piping High Points, with Verifying ECCS Piping Is Full of Water ML20140C8881997-04-17017 April 1997 Proposed Tech Specs,Replacing Attachment to Waterford 3 Submittal W3F1-97-0067,dtd 970407,correcting Oversight ML20137T4051997-04-11011 April 1997 Proposed Tech Specs,Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20137T4541997-04-11011 April 1997 Proposed Tech Specs Making TS 3.6.2.2 & Surveillance Requirement 4.6.2.2 Consistent W/Containment Cooling Assumptions in Waterford 3 Containment Analysis 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217K9011999-10-18018 October 1999 Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20211F5501999-08-24024 August 1999 Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220 ML20211F3701999-08-24024 August 1999 Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207 ML20210M9681999-08-0404 August 1999 Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions ML20210M9861999-08-0404 August 1999 Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown ML20210H1771999-07-29029 July 1999 Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days ML20210H2371999-07-29029 July 1999 Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210B3411999-07-19019 July 1999 Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps ML20210D0521999-07-15015 July 1999 Proposed Tech Specs Creating New TS for Feedwater Isolation Valves ML20210D1071999-07-15015 July 1999 Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20209H3191999-07-15015 July 1999 Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY ML20209D4091999-07-0707 July 1999 Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207 ML20196E9971999-05-24024 May 1999 Rev 3 to NTP-203, Emergency Plan Training ML20195B1811999-05-20020 May 1999 Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12 ML20204H2591999-03-16016 March 1999 Rev 0 to STD-100-237, Procedure for Modification of RCS Pressure Boundary for Installation of Mechanical Nozzle Seal Assemblies (Mnsa) for Waterford Nuclear Generating Station Unit 3 ML20204H2511999-03-16016 March 1999 Rev 1 to C-NOME-EP-0189, Engineering Procedure for Installation of Mechanical Nozzle Seal Assemblies for Waterford 3 ML20203C4891999-02-0505 February 1999 Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension ML20199D9851999-01-12012 January 1999 Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel ML20199E0861999-01-12012 January 1999 Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174 ML20198G2401998-12-23023 December 1998 Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20196D2181998-11-30030 November 1998 Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants ML20154E4171998-10-0606 October 1998 Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle ML20154E1141998-10-0101 October 1998 Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys ML20153D5771998-09-23023 September 1998 Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable ML20153B4441998-09-18018 September 1998 Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation ML20151W5971998-09-11011 September 1998 Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7921998-08-12012 August 1998 Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7361998-07-29029 July 1998 Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model ML20236H1501998-07-0202 July 1998 Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition ML20249C8321998-06-29029 June 1998 Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432 ML20249C7901998-06-29029 June 1998 Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls ML20249A3101998-06-12012 June 1998 Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls ML20248B7611998-05-28028 May 1998 Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys ML20248H7871998-05-25025 May 1998 Rev 1 to Waterford Unit 3 Second Interval ISI Plan ML20247P2431998-05-21021 May 1998 Proposed Tech Specs Re Design Feature Suppl ML20217P8411998-05-0101 May 1998 Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal ML20217L9971998-04-30030 April 1998 Small Break LOCA ECCS Performance Analysis Using Abb/Ce Suppl 2 Model ML20217D5181998-03-25025 March 1998 Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8 ML20198R3081998-01-21021 January 1998 Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements ML20198R1251998-01-21021 January 1998 Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys ML20197C6431997-12-22022 December 1997 Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section ML20202C2911997-12-0101 December 1997 Rev 0 to Pump & Valve Inservice Test Plan for Second 10-Yr Interval. Page 23 of Incoming Submittal Not Included ML20199A0011997-11-13013 November 1997 Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21 ML20199A1101997-11-13013 November 1997 Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20217M0221997-10-28028 October 1997 Rev 8 to RW-001-210, Process Control Program ML20217H5931997-10-14014 October 1997 Revised Page of App B of FOL, Environ Protection Plan (Nonradiological) ML20217G2421997-10-0707 October 1997 Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8141997-09-25025 September 1997 Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G7131997-07-0707 July 1997 Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3 ML20141D8551997-06-26026 June 1997 Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases 1999-08-04
[Table view] |
Text
O NPF-38-147 ATTACHMENT A 1
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,f 9312200194 931214 PDR ADOCK 05000382 P PDR x
i POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - Tq l
LIMITING CONDITION FOR OPERATION l 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the AZIMUTHAL q
POWER TILT Allowance used in the Core Protection Calculators (CPCs). ],
APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.* j ACTION: ,
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- a. With the measured AZIMUTHAL POWER TILT determined to exceed the J AZIMUTHAL POWER TILT Allowance used in the CPCs but less than or equal ,
to 0.10, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either correct the power tilt or adjust the ;
AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.
- b. With the measured AZIMUTHAL POWER TILT determined to exceed 0.10: j
- 1. Due to misalignment of either a part length or full length CEA, I within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS) (when.COLSS is being used to monitor the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.
- 2. Verify that the AZIMUTHAL POWER TILT is within its ' limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Linear Power Level - High trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or-until verified acceptable at- ,
95% or greater RATED THERMAL POWER. j i
A See Special Test Exception 3.10.2.
9 WATERFORD - UNIT 3 3/4 2-4
1 POWER DISTRIBUTION LIMITS l
BASES l .
3/4.2.2 PLANAR RADIAL PEAKING FACTORS Limiting the values of the PLANAR RADIAL PEAKING FACTORS (Fc ) used'in the l
l COLSS and CPCs to galues equal to or greater than'the measured PLANAR RADIAL-PEAKING FACTORS (Fxy) provides assurance that the limits calculated by COLSS' and the CPCs remain valid. Data from the incore detectors are used for t
4 determining the measured PLANAR RADIAL PEAKING FACTORS.- A minimum core power at 20% of RATED THERMAL' POWER is assumed in detarmining the PLANAR RADIAL-PEAKING FACTORS.
flux detector system The 20%inaccurate being RATED THERMAL below 20% POWER threshold is due to the. neutron core power. Core noise level at low power is too large to obtain usable detector readings. The periodic )
Surveillance Requirements for determining the measured' PLANAR RADIAL PEAKING FACTORS provide assurance that the PLANAR RADIAL PEAKING FACTORS used in )
COLSS and the CPCs remain valid throughout the fuel cycle.-' Determining the measured PLANAR RADIAL PEAKING FACTORS after each fuel loading prior to exceeding 70% of RATED THEJtMAL POWER provides additional assurance that the e
core was properly loaded.
3/4.2.3 . AZIMUTHAL POWER TILT - Tq The limitations on the AZIMUTHAL POWER TILT. are provided to ensure that design safety margins are maintained. An AZIMUTHAL POWER TILT greater than- I.
0.10 is not expected and if it should occur, operation is restricted to only those conditions required to identify the cause of ~ the tilt. The tilt is normally calculated by COLSS. A minimum core power of 20% of RATED THERMAL 4
POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT.
The 20% RATED THERMAL POWER threshold is due to the
- neutron flux detector system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector readings. The Surveillance Requirements specified when COLSS is out of service provide an- )
acceptable means of detecting the presence of a steady-state tilt. It is necessary to explicitly account for power asymmetries because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.
AZIMUTHAL POWER TILT is measured by assuming that the ratio of the power !
at any core location in the presence of a tilt to the untilted power at the-location is of the form:
P /P +T q g cos (0 - 0,)
tilt untilt where:
T q is the peak fractional tilt amplitude at the core periphery gistheradialnormaliiingfactor e is the azimuthal core location 0, is the azimuthal core location of maximum tilt '
I WATERFORD - tlNIT 3 8 3/4 2-2 ,
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4 NPF-38-147 )
ATTACHMENT B ,
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POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT -T q LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (Tq ) shall be less than or equal to the FOLLOWING LIMITS:
l a, AZIMUTHAL POWER TILT Allowance used in the Core Protection i Calculators (CPCs), and ,
l l b. 0.03 (3%). l l ,
APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.*
ACTION:
- a. With the measured AZIMUTHAL POWER TILT determined to exceed the j i
AZIMUTHAL POWER TILT Allowance used in the CPCs but lez than or equal to 0.10. within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either correct the power tilt or ;
adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to !
greater than or equal to the measured value.
- b. With the measured AZIMUTHAL POWER TILT determined to exceed 0.03: l i
- 1. Due to misalignment of either a part length or full length CEA. within 30 minutes verify that the Core Operating Limit i Supervisory System (COLSS) (when COLSS is being used to monitor the core power distribution per Specifications 4.2.1.2 and 4.2.4.2) is detecting the CEA misalignment.
- 2. Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for a CEA misalignment event) after exceed 4ng the Sw4t or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Linear Power Level - high trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER: subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within i its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.
- See Special Test Exception 3.10.2.
WATERFORD - UNIT 3 3/4 2-4
POWER DISTRIBUTION LIMITS
, BASES 1
l 3/4.2.2 PLANAR RADIAL PEAKING FACTORS l Limiting the values of the PLANAR RADIAL PEAKING FACTORS (fcxy) used in the COLSS and CPCs to values equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (Fm y) provides assurance that the limits calculated by COLSS and the CPCs remain valid. Data from the incore detectors are used for determining the measured PLANAR RADIAL PEAKING FACTORS A minimum core power at 20% of RATED THERMAL POWER is assumed in determining the PLANAR RADIAL i PEAKING FACTORS. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector l system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector readings. The periodic Surveillance Requirements for detemining the measured PLANAR RADIAL PEAKING FACTORS provide assurance that the PLANAR RADIAL PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the fuel cycle. Determining the measured PLANAR RADIAL PEAKING FACTORS af ter each fuel loading prior to exceeding 70% of RATED THERMAL POWER provides additional assurance that the core was properly loaded.
3/4.2.3 AZIMUTHAL POWER TILT - T ThelimitationsontheAZIMhHALPOWERTILTareprovidedtoensurethatdesignsafety margins are maintained. The LC0 places a 3t limit on the maximum azimuthal tilt during normal steady state power operation. With An AZIMUTHAL POWER TILT greater than 3% 0-10-i+
nct 0:pected and " it should occur operation is restricted to only those conditions required to identify the cause of the tilt. However. Action item b.2 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the tilt to less than 3% following a CEA misalignment event (i.e., CEA drop). A CEA misalignment event causes an asymetric core power generation and an increase in xenon concentration in the vicinity of the dropped rod. This event may cause the azimuthal tilt to exceed 3%. The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action time to reduce core power is not sufficient to recover from the xenon transient. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period allows for correction of the misaligned CEA and allows time for the xenon redistribution effects to dampen out due to radioactive decay and absorption. The reduction in xenon concentration (which is aided by operation at full power) will in turn reduce the tilt below the 3t limit.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is applicable only to a CEA misalignment where the cause of the tilt has been identified. It is based on the time required for the expected xenon transient to dampen out. All other conditions (not due to a CEA misalignment) where the azimuthal tilt exceeds 3% require action within the specified 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
The tilt is normally calculated by COLSS. A minimum core power of 20% of RATED THERMAL POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT.
The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector readings. The Surveillance Requirements specified when COLSS is out of - service provide an acceptable means of detecting the presence of a steady-state tilt. It is necessary to explicitly account for power asymmetries in the COLSS and CPCs because the l radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.
WATERFORD - UNIT 3 B 3/4 2-2
POWER DISTRIBUTION LIMITS ,
I BASES AZIMUTHAL POWER TILT - Tq (Continued)
AZIHLfTHAL POWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form: i I
Pg /PuM -1+T q g cos (0 - O )
g where:
Tq is the peak fractional tilt amplitude at the core periphery 9 is the radial normalizing factor e is the azimuthal cor; ioc3 tion l
Gois the azimuthal core location of maximum tilt Ptilt untilt is the ratio of the power at a core location in the presence of a tilt ;
to the power at that location with no tilt. l 3/4.2.4 DNBR MARGIN The limitation on DNBR as a function of AXIAL SHAPE INDEX represents a conservative ;
envelope of operating conditions consistent with the safety analysis assumptions and which J have been analytically demonstrated adequate to maintain an acceptable minimum DNBR ,
throughout all anticipated operational occurrences. Operation of the core with a DNBR at or '
above this limit provides assurance that an acceptable minimum DNBR will be maintained. l Either of the two core power distribution monitoring systems. the Core _0perating Limit l' Supervisory System (COLSS) and the DNBR channels in the Core Protection Calculators (CPCs).
provides adequate monitoring of the core power distribution and is capable of verifying that the DNBR does not violate its limits. The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable minimum DNBR. The COLSS calculation of core power operating limit based on ;
the minimum DNBR limit includes appropriate penalty factors which provide a 95/95 i probability / confidence level that the core power calculated by COLSS. based on the minimum j DNBR limit. is conservative with respect to the actual core power limit. These penalty '
factors are determined from the uncer- tainties associated with planar radial peaking measurements. state parameter measurement. software algorithm modelling, computer processing, rod bow, and core power measurement.
Parameters required to maintain the margin to DNB and total core power are also monitored by the CPCs. Therefore. in the event that the COLSS is not being used, operation within the limits of Figure 3.2.2 or Figure 3.2-3 can be maintained by utilizing a predetermined DNBR as a function of AXIAL SHAPE INDEX and by monitoring the CPC trip channels. The above !
listed uncertainty and penalty factors plus those associated with startup test acceptance criteria are also included in the CPCs which assume a minimum core power of 20% of RATED THERMAL POWER. The 20% RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20% core power. Core noise level at low power is too large to obtain usable detector readings.
WATERFORD - UNIT 3 B 3/4 2-2 AHENDHENT 12
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