|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217K8901999-10-18018 October 1999 TS Change Request NPF-38-224 for License NPF-38,modifying TS 3.6.2.2 LCO to Allow Plant to Operate with Two Independent Trains of Containment Cooling,Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20210M9761999-08-0404 August 1999 Application for Amend to License NPF-38,to Modify TS 3.5.2 to Extend Allowed Outage Time to Seven Days for One HPSI Train Inoperable & TS 3.5.3 to Change end-state to Hot Shutdown with at Least One Operable Shutdown in Operation ML20210M9601999-08-0404 August 1999 Application for Amend to License NPF-38,to Modify TS 3.5.2 to Extend Allowed Outage Time to Seven Days for One LPSI Train Inoperable & Allowed Outage Time of 72 Hours Imposed for Other Conditions ML20210H1401999-07-29029 July 1999 TS Change Request NPF-38-220 to License NPF-38,modifying TS 3.8.1.1 & Associated Bases by Extending EDG Allowed AOT from 72 H to Ten Days ML20210H2091999-07-29029 July 1999 TS Change Request NPF-38-221 to License NPF-38,modifying TS 3.6.2.1 to Extend Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210B3181999-07-19019 July 1999 TS Change Request NPF-38-219 for License NPF-38,modifying TS 4.5.2.f.2 by Increasing Performance Requirement for LPSI Pumps ML20210D0831999-07-15015 July 1999 TS Change Request NPF-38-216 to License NPF-38,adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20210D0341999-07-15015 July 1999 TS Change Request NPF-38-217 to License NPF-38,creating New TS for Feedwater Isolation Valves to Ts.Unreviewed Safety Question Re Crediting of Rt Override Feature & AFW Pump High Discharge Pressure Trip,Provided ML20209H3051999-07-15015 July 1999 Application for Amend to License NPF-38 to Modify TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 Efpy.Proprietary Rept 51-1234900-00 Encl.Proprietary Encl Withheld,Per 10CFR2.790 ML20195B1771999-05-20020 May 1999 Application for Amend to License NPF-38 to Change TS 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 ML20198G2311998-12-23023 December 1998 Application for Amend to License NPF-38,modifying LCO for TS 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20154E1011998-10-0101 October 1998 Tech Spec Change Request NPF-38-211 to License NPF-38, Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20153D5571998-09-23023 September 1998 Emergency TS Change Request NPF-38-210 to License NPF-38, Addressing Functional Requirements of 10-4% Bistable of Rps. TS Change Request NPF-38-21 Replaces 980918 Request Entirely ML20153B4381998-09-18018 September 1998 Emergency Application for Amend to License NPF-38,modifying Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints & Table 3.3-1 Re Reactor Protective Instrumentation.Application Supersedes 980911 Submittal ML20151W5791998-09-11011 September 1998 TS Change Request NPF-38-210 to License NPF-38,modifying Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7901998-08-12012 August 1998 Application for Amend to License NPF-38,increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7281998-07-29029 July 1998 Application for Amend to License NPF-38 to Revise TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model.Request Associated W/Methodology Used to Obtain SBLOCA Results ML20249C7861998-06-29029 June 1998 TS Change Request NPF-38-205 to License NPF-38,modifying TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection & Associated Bases ML20249C8301998-06-29029 June 1998 Application for Amend to License NPF-38,revising Control Room Ventilation TS to Be More Consistent w/NUREG-1432 ML20248B7441998-05-28028 May 1998 Application for Amend to License NPF-38 to Change TS 3.7.1.2,surveillance Requirement 4.7.1.2 & Bases Change for Emergency Feedwater Sys ML20217D4921998-03-25025 March 1998 Rev 1 to 960718 TS Change Request NPF-38-177 to License NPF-38,correcting Discrepancy in Original Submittal & Incorporating Addl Changes to Improve Clarity of TS 3.9.8.1 & TS 3.9.8.2 ML20199A1031997-11-13013 November 1997 TS Change Request NPF-38-202 to License NPF-38,modifying TS 6.8.4.a, Primary Coolant Sources Outside Containment, to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20217G2351997-10-0707 October 1997 Application for Amend to License NPF-38,modifying TS 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8091997-09-25025 September 1997 Application for Amend to License NPF-38,modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G6951997-07-0707 July 1997 Application for Amend to License NPF-38,supplementing TS Change Request NPF-38-179 by Modifying Value Previously Submitted to Prevent Vortexing & Value for Short Term Requirements of CCW Makeup Sys & Expand Applicability of TS ML20141D8471997-06-26026 June 1997 Application for Amend to License NPF-38,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 ML20148G6221997-06-0303 June 1997 Suppl to 960717 TS Change Request NPF-38-179,providing Updated Info Based on Min Required Level in Condensate Storage Pool.Attachment a Contains Original Vortexing Calculation & Attachment B Contains Revised Calculation ML20140B1591997-06-0303 June 1997 Application for Amend to License NPF-38,consisting of TS Change Request NPF-38-108,revising Action Requirements for TS 3/4.3.2 for Safety Injection Sys Sump RAS ML20141K1911997-05-24024 May 1997 TS Change Request NPF-38-197 to License NPF-38,modifying TS 3/4.7.4 Re 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 ML20141K1611997-05-24024 May 1997 TS Change Request NPF-38-196 to License NPF-38,modifying Specifications 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1-1 by Removing Cycle Dependent Boron Concentration & Boration Flow Rate from Action Statements ML20137T4251997-04-11011 April 1997 Application for Amend to License NPF-38,deleting TS 3.7.1.3, Action (B) & Associated Surveillance Requirement ML20137T4451997-04-11011 April 1997 Application for Amend to License NPF-38,making TS 3.6.2.2 & Surveillance Requirement 4.6.2.2 Consistent W/Containment Cooling Assumptions in Waterford 3 Containment Analysis ML20137T3971997-04-11011 April 1997 Application for Amend to License NPF-38-195,modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20137P2561997-04-0707 April 1997 Application for Amend to License NPF-38,deleting TS 4.8.1.1.2a.7 & Incorporating 184 Day Fast Start Test Requirement as 4.8.1.1.2d,renumber Subsequent Requirements & Adding Footnote as Indicated ML20137G4711997-03-27027 March 1997 TS Change Request NPF-38-192 to License NPF-38,modifing TS 3/4.5.2, ECCS Subsystems Modes 1,2 & 3 ML20137F9201997-03-27027 March 1997 TS Change Request NPF-38-191 to License NPF-38,modifying TS Surveillance Requirements 4.5.2.d.3 & 4.5.2.d.4 Re Granular Trisodium Phosphate Dodecahydrate ML20137G2021997-03-27027 March 1997 Application for Amend to License NPF-38,increasing SFP Storage Capacity & Increasing Maximum Fuel Enrichment from 4.9 W/O to 5.0 W/O U-235.Proprietary & Nonproprietary Repts HI-971628 Encl.Proprietary Rept Withheld ML20134F7091997-02-0505 February 1997 Application for Amend to License NPF-38,requesting to Increase Minimum Boron Concentration in Safety Injection Tanks & Refueling Water Storage Pool to 2050 Ppm ML20135A7661996-12-0202 December 1996 Application for Amend to License NPF-38,permitting Use of 10CFR50,App J,Option B Re performance-based Containment Leakage Testing for Type A,B & C Leak Rate Testing ML20134L6771996-11-18018 November 1996 Application for Amend to License NPF-38,requesting Rev to Change Testing Requirement for Shutdown Cooling Sys Suction Line Relief Valves to Test in Accordance W/Ts 4.0.5 ML20134L1901996-11-15015 November 1996 Application for Amend to License NPF-38,requesting Revision to Scope of Limiting Condition for Operation 3.6.3 Re Containment Isolation ML20128Q1661996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 185,expanding Applicability for CPC Operability & Allowing for Application of Cycle Independent Shape Annealing Matrix ML20128Q2221996-10-16016 October 1996 Application for Amend to License NPF-38,requesting That Change Request 182,permit Use of 10CFR50,App J,Option B, Performance-Based Containment Leakage Testing ML20128Q1871996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 183,extending Allowable Time for Core Operating Limit Supervisory Sys OOS by Monitoring for Adverse Trends ML20128Q2091996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 186,relocating Certain Adminstrative Controls to QA Program Manual & Changing Shift Coverage from 8 H day,40 H Wks to Option of 8 or 12 H Days & Nominal 40 H Wks ML20116B0461996-07-25025 July 1996 Application for Amend to License NPF-38,modifying TS 3/4.7.4 Ultimate Heat Sink by Incorporating More Restrictive Fan Operability Requirements & Lower Basin Temp ML20115G5071996-07-18018 July 1996 Application for Amend to License NPF-38,revising TS 3.9.8.1, Shutdown Cooling & Coolant Circulation High Water Level & TS 3.9.8.2, Shutdown Coolant Circulation Low Water Level ML20116D0071996-07-17017 July 1996 Application for Amend to License NPF-38,consisting of Change Request 174,extending Surveillance Interval for Rtbs from Monthly to Quarterly & Increasing AOT for Operation W/Inoperable Rtb from One H to Two H ML20115G2811996-07-17017 July 1996 Application for Amend to License NPF-38,reflecting That Name La Power & Light Co Has Been Changed to Entergy Louisiana,Inc ML20115G4901996-07-17017 July 1996 Application for Amend to License NPF-38,modifying Spec 3/4.7.1.3 Condensate Storage Pool by Increasing Minimum Required Contained Water Vol from 82% to 91% Indicated Level 1999-08-04
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217K8901999-10-18018 October 1999 TS Change Request NPF-38-224 for License NPF-38,modifying TS 3.6.2.2 LCO to Allow Plant to Operate with Two Independent Trains of Containment Cooling,Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4 ML20210M9761999-08-0404 August 1999 Application for Amend to License NPF-38,to Modify TS 3.5.2 to Extend Allowed Outage Time to Seven Days for One HPSI Train Inoperable & TS 3.5.3 to Change end-state to Hot Shutdown with at Least One Operable Shutdown in Operation ML20210M9601999-08-0404 August 1999 Application for Amend to License NPF-38,to Modify TS 3.5.2 to Extend Allowed Outage Time to Seven Days for One LPSI Train Inoperable & Allowed Outage Time of 72 Hours Imposed for Other Conditions ML20210H1401999-07-29029 July 1999 TS Change Request NPF-38-220 to License NPF-38,modifying TS 3.8.1.1 & Associated Bases by Extending EDG Allowed AOT from 72 H to Ten Days ML20210H2091999-07-29029 July 1999 TS Change Request NPF-38-221 to License NPF-38,modifying TS 3.6.2.1 to Extend Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable ML20210B3181999-07-19019 July 1999 TS Change Request NPF-38-219 for License NPF-38,modifying TS 4.5.2.f.2 by Increasing Performance Requirement for LPSI Pumps ML20210D0831999-07-15015 July 1999 TS Change Request NPF-38-216 to License NPF-38,adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019 ML20210D0341999-07-15015 July 1999 TS Change Request NPF-38-217 to License NPF-38,creating New TS for Feedwater Isolation Valves to Ts.Unreviewed Safety Question Re Crediting of Rt Override Feature & AFW Pump High Discharge Pressure Trip,Provided ML20209H3051999-07-15015 July 1999 Application for Amend to License NPF-38 to Modify TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 Efpy.Proprietary Rept 51-1234900-00 Encl.Proprietary Encl Withheld,Per 10CFR2.790 ML20195B1771999-05-20020 May 1999 Application for Amend to License NPF-38 to Change TS 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 ML20198G2311998-12-23023 December 1998 Application for Amend to License NPF-38,modifying LCO for TS 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm ML20154E1011998-10-0101 October 1998 Tech Spec Change Request NPF-38-211 to License NPF-38, Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20153D5571998-09-23023 September 1998 Emergency TS Change Request NPF-38-210 to License NPF-38, Addressing Functional Requirements of 10-4% Bistable of Rps. TS Change Request NPF-38-21 Replaces 980918 Request Entirely ML20153B4381998-09-18018 September 1998 Emergency Application for Amend to License NPF-38,modifying Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints & Table 3.3-1 Re Reactor Protective Instrumentation.Application Supersedes 980911 Submittal ML20151W5791998-09-11011 September 1998 TS Change Request NPF-38-210 to License NPF-38,modifying Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation ML20237A7901998-08-12012 August 1998 Application for Amend to License NPF-38,increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm ML20236U7281998-07-29029 July 1998 Application for Amend to License NPF-38 to Revise TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model.Request Associated W/Methodology Used to Obtain SBLOCA Results ML20249C8301998-06-29029 June 1998 Application for Amend to License NPF-38,revising Control Room Ventilation TS to Be More Consistent w/NUREG-1432 ML20249C7861998-06-29029 June 1998 TS Change Request NPF-38-205 to License NPF-38,modifying TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection & Associated Bases ML20248B7441998-05-28028 May 1998 Application for Amend to License NPF-38 to Change TS 3.7.1.2,surveillance Requirement 4.7.1.2 & Bases Change for Emergency Feedwater Sys ML20217D4921998-03-25025 March 1998 Rev 1 to 960718 TS Change Request NPF-38-177 to License NPF-38,correcting Discrepancy in Original Submittal & Incorporating Addl Changes to Improve Clarity of TS 3.9.8.1 & TS 3.9.8.2 ML20199A1031997-11-13013 November 1997 TS Change Request NPF-38-202 to License NPF-38,modifying TS 6.8.4.a, Primary Coolant Sources Outside Containment, to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program ML20217G2351997-10-0707 October 1997 Application for Amend to License NPF-38,modifying TS 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys ML20211F8091997-09-25025 September 1997 Application for Amend to License NPF-38,modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2 ML20141G6951997-07-0707 July 1997 Application for Amend to License NPF-38,supplementing TS Change Request NPF-38-179 by Modifying Value Previously Submitted to Prevent Vortexing & Value for Short Term Requirements of CCW Makeup Sys & Expand Applicability of TS ML20141D8471997-06-26026 June 1997 Application for Amend to License NPF-38,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 ML20148G6221997-06-0303 June 1997 Suppl to 960717 TS Change Request NPF-38-179,providing Updated Info Based on Min Required Level in Condensate Storage Pool.Attachment a Contains Original Vortexing Calculation & Attachment B Contains Revised Calculation ML20140B1591997-06-0303 June 1997 Application for Amend to License NPF-38,consisting of TS Change Request NPF-38-108,revising Action Requirements for TS 3/4.3.2 for Safety Injection Sys Sump RAS ML20141K1911997-05-24024 May 1997 TS Change Request NPF-38-197 to License NPF-38,modifying TS 3/4.7.4 Re 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 ML20141K1611997-05-24024 May 1997 TS Change Request NPF-38-196 to License NPF-38,modifying Specifications 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1-1 by Removing Cycle Dependent Boron Concentration & Boration Flow Rate from Action Statements ML20137T4251997-04-11011 April 1997 Application for Amend to License NPF-38,deleting TS 3.7.1.3, Action (B) & Associated Surveillance Requirement ML20137T3971997-04-11011 April 1997 Application for Amend to License NPF-38-195,modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Detection Sys ML20137T4451997-04-11011 April 1997 Application for Amend to License NPF-38,making TS 3.6.2.2 & Surveillance Requirement 4.6.2.2 Consistent W/Containment Cooling Assumptions in Waterford 3 Containment Analysis ML20137P2561997-04-0707 April 1997 Application for Amend to License NPF-38,deleting TS 4.8.1.1.2a.7 & Incorporating 184 Day Fast Start Test Requirement as 4.8.1.1.2d,renumber Subsequent Requirements & Adding Footnote as Indicated ML20137G4711997-03-27027 March 1997 TS Change Request NPF-38-192 to License NPF-38,modifing TS 3/4.5.2, ECCS Subsystems Modes 1,2 & 3 ML20137F9201997-03-27027 March 1997 TS Change Request NPF-38-191 to License NPF-38,modifying TS Surveillance Requirements 4.5.2.d.3 & 4.5.2.d.4 Re Granular Trisodium Phosphate Dodecahydrate ML20137G2021997-03-27027 March 1997 Application for Amend to License NPF-38,increasing SFP Storage Capacity & Increasing Maximum Fuel Enrichment from 4.9 W/O to 5.0 W/O U-235.Proprietary & Nonproprietary Repts HI-971628 Encl.Proprietary Rept Withheld ML20134F7091997-02-0505 February 1997 Application for Amend to License NPF-38,requesting to Increase Minimum Boron Concentration in Safety Injection Tanks & Refueling Water Storage Pool to 2050 Ppm ML20135A7661996-12-0202 December 1996 Application for Amend to License NPF-38,permitting Use of 10CFR50,App J,Option B Re performance-based Containment Leakage Testing for Type A,B & C Leak Rate Testing ML20134L6771996-11-18018 November 1996 Application for Amend to License NPF-38,requesting Rev to Change Testing Requirement for Shutdown Cooling Sys Suction Line Relief Valves to Test in Accordance W/Ts 4.0.5 ML20134L1901996-11-15015 November 1996 Application for Amend to License NPF-38,requesting Revision to Scope of Limiting Condition for Operation 3.6.3 Re Containment Isolation ML20128Q2091996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 186,relocating Certain Adminstrative Controls to QA Program Manual & Changing Shift Coverage from 8 H day,40 H Wks to Option of 8 or 12 H Days & Nominal 40 H Wks ML20128Q2221996-10-16016 October 1996 Application for Amend to License NPF-38,requesting That Change Request 182,permit Use of 10CFR50,App J,Option B, Performance-Based Containment Leakage Testing ML20128Q1871996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 183,extending Allowable Time for Core Operating Limit Supervisory Sys OOS by Monitoring for Adverse Trends ML20128Q1661996-10-16016 October 1996 Application for Amend to License NPF-38,consisting of Change Request 185,expanding Applicability for CPC Operability & Allowing for Application of Cycle Independent Shape Annealing Matrix ML20116B0461996-07-25025 July 1996 Application for Amend to License NPF-38,modifying TS 3/4.7.4 Ultimate Heat Sink by Incorporating More Restrictive Fan Operability Requirements & Lower Basin Temp ML20115G5071996-07-18018 July 1996 Application for Amend to License NPF-38,revising TS 3.9.8.1, Shutdown Cooling & Coolant Circulation High Water Level & TS 3.9.8.2, Shutdown Coolant Circulation Low Water Level ML20116D0071996-07-17017 July 1996 Application for Amend to License NPF-38,consisting of Change Request 174,extending Surveillance Interval for Rtbs from Monthly to Quarterly & Increasing AOT for Operation W/Inoperable Rtb from One H to Two H ML20115G2811996-07-17017 July 1996 Application for Amend to License NPF-38,reflecting That Name La Power & Light Co Has Been Changed to Entergy Louisiana,Inc ML20115G4901996-07-17017 July 1996 Application for Amend to License NPF-38,modifying Spec 3/4.7.1.3 Condensate Storage Pool by Increasing Minimum Required Contained Water Vol from 82% to 91% Indicated Level 1999-08-04
[Table view] |
Text
- - - .
,
m I Louh Power & Ught Coy.pany 317 Barorve Street
P.O. Boa 60M0 Now Orleans, LA 70160 0MO Tel 604 695 2781 J. G. Dewease Genum Vee Pepsedent-uaw ovaesm l
W3P88-1849 A4.05 '
October 16, 1989 QA
U.S. Nuclear Regulatory Commission ATTN! Document Control Desk Washington, D.C. 20555 ;
Subject:
Waterford 3 SES ,
Docket No. 50-382 License No. NPF-38 Technical Specification Change Request NPF-38-l_03_
Gentlement
'
In accordance with 10 CFR Part 50.90 Louisiana Power & Light company i submits a request to amend Facility. Operating License NPF-38.
This minendment revises the Reactor Protective System (RPS) Inotrumentation Surveillance Requirements (Table 4.3-1 of Technical Specification 3/4.3.1
'
" Reactor Protective Instrumentation") and the Engineered Safety Feature i Actuation System.(ESTAS) Inntrumentation Surveillance Requirements (Table 4.3-2 of Technical Specification 3/4.3.2 " Engineered Safety Feature Actut4 tion System Instrumentation"). The proposed amendment changes the surveillance frequency for several of the channel functional tests from ,.
monthly to quarterly. The basis for this chenge comes from CEN-327: ,
RPS/ESFAS Extended Test Interval Evaluation, submitted by the Combustion !
Engineering Owners Group.
,
Please feel free to direct any questions or comments on this matter to [
Steven E. Farkas at (504) 464-3383. l truly yours,
,
(
> IO J. . Dewcase wu a- :
S for Vice President clear Operations
,M JGD/SEF/pi [
! qsn Attachmentst NPF-38-103 '
coo A60/
'0% cc Messrs R.D. Martin i M F.J. Hebdon I i
gN D.L. Wigginton E.L. Blake
'
1r W.M. Stevenson [
'g,h NRC Resident Inspectors Office I Administrator Nuclear Energy Division (State of Louisiana)
,American Nuclear Insurers
[ ,
)
4 . ,
,
,
UNITED STATES OF AMERICA NUCLF.AR REGULATORY COMMISSION l
I
.{ "
In the matter of )
)
( Louisiana Power & Light Company ) Docket No. 50-382 ,
! Waterford 3 Stet.m Electric Station )
'
I AFFIDAVIT
.
(
- J.G. Dewease, being duly sworn, hereby deposes and says that he is Senior Vice President - Nuclear Operations of Louisiana Power 6 Light Companyl i
-
that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Technical Specification Change Request NPF-38-103; !
that he is familiar with the content thereof and that the matters set :
forth therein are true and cerrect to the best of his knowledge, information and belief. ,
f
_ ! WC IJC.Dewtase senior Vice President
/ Nuclear Operations !
STATE OF LOUISIANA) '
'.
).ss PARIS!! 0F ORLEANS )
a Notary Publi 1. d or the Parish Subscribed and and named State above sworn to before this /dme,I,
/ day of ,
'
~
1989. i
_,
b' ' 4 ~
otary Public" C
,
My Commission expires ,. .
!
V
,
L . .
- _--
,
y' l s
, ... ,,
.1
-
k 9, .
-.-
L DESCRIPTION AND SAFETY ANALYSIS r
OF PROPOSED CHANGE NPF-38-103 h
This document justifies a revision ~to Table 4.3-1 of Technical Specification 3/4.3.1: Reactor Protective Instrumentation and Table 4.3-2 g of Technical Specification 3/4.3.2 Engineered Safety Features Actuation
,.
i System Instrumentation, t ..
Existing Specificatiens
, ,
See Attachment A U Proposed Speeffications f
'
See Attachment B
?
i ' Description,
The operability of the Reactor Protective System (RPS) and Engineered Safety Features Actuation System (ESTAS) instrumentation and bypasses ensures thatt l . "- 1) the~ associated Reactor Trip and Engineered Safety Features Actuation
!> actions perform when the parameter monitored by each channel, or p- combination thereof, reaches its setpoint
s2) the specified coincidence logic is maintained
- 3) redundancy permits a channel to be out-of-service for either testing or maintenance 1 4) sufficient system functional capability is available from diverse
'
parameters.
ESTAS and RPS operability criteria assure the reliability, redundancy and diverst:y assumed in the facility design for the protection against, and 21cigation of, accident and transient conditions.
-
The surveillance requirements ensure the system capability stays comparable to the original design standards. The RPS and ESFAS instrumentation channel functional tests are performed monthly. These surveillances are time consuming. More importantly, they collectively throughout the industry cause many inadvertent reactor trips and engineered safeguards actuations challenging safety systems. Therefore, this high frequency results in an adverse impact on equipment life and unit availability. The proposed license amendment increases the interval for these surveillances from monthly to quarterly and maximites instrumentation reliability.
l l
1
__ _ _ _ _ ,
e
.
- .. ,
,
i
'
T -
'
- The NRC recognized the burden imposed by some technical specifications I
'
and is evaluating how to modify or restructure technical specifications to l reduce that burden without affecting the health and safety of the public.
In 1982. Westinghouse and the Westinghouse owners Group submitted a generic !
'
j- topical report requesting test interval extensions for selected components l in the RPS and EST/.S. This request was supported through the use of ,
probabilistic risk assessment methodologies. As a result, the NRC
'
l foitiated a renarch project to determine how probabilistic risk assessment ;
methodologies can lead to optimal technical specification surveillance ;
intervals and allowed component outage times. Plus, the project evaluates !
how to grant requests for technical specification relief based on such
, probabiliotic risk analyses. Pending completion of this research, the NRC ,
'
i indicated that they will favorably review technical specification relief requests based on probabilletic risk analyses, as long as these analyses demonstrate no significant increase in the risk to the public. .
[' Following the low power ATWS event in 1983, the NRC issued Generic Letter 83-28 specifying actions for licensees and applicants. One of these ,
actions reviews the Reactor Trip System (RTS) test intervals to deterutne i, if they help achieve high RTS availability. CE, under contract to the CE Owners Group.(CE00), performed an analysis on RTS availability given the thirty day test interval required by the Technical Specifications.
Sensitivity analyses indicated that the RTS unavailability is insensitive to changes in individual component failure rates. That conclusion affects
!
the RTS test program rationale. Less testing reduces challenges to safety systems and improves plant availability. In January 1985, CE, under contract to the CEOG, began an analysis on the impact of extending the surveillance test intervals for selected components in the RPS and ESFAS.
This analysis became LEN-327: RPS/ESFAS Extended Test Interval 1. valuation.
In CEN-327, each of the four RPS fault tree models developed previously for the CEOG expanded to cover all RPS electronic trip parameters. The new models were then used to determine the RPS reliability for the current and the proposed test interval. The model takes into account common mode failures, operator errors, reduced redundancy, and random component failures. The analysis intends to justify extending the surveillance test intervals from thirty days to ninety days. Based on the NRC position at that time, the CE00 declared acceptable analysis results if extending the test intervals did not increase the risk to the public (as measured by the core damage frequency). Trip parameter circuits (between the sensors and actuated device) were analyzed assuming a ninety day test interval with staggered testing and a sixty day test interval with sequential testing.
Both of these test schemes passed the "no increase in core damage frequency" criteria.
- Fault tree models were also constructed for each of the ESFAS signals.
l Similar to the RPS fault tree models, each ESFAS fault tree model specifically addressed common mode failures, operator errors, reduced l redundancy, and random component failures. Once the models were l constructed CE measured the ESTAS reliability assuming the current and proposed test intervals. For ESFAS, CEN-327, Section 5.e, specifically I recommended increasing the surveillance frequency for the bistables.
I bistable relays, logic matrix relays, actuation logic circuits and manual l- actuation devices. See the enclosed figure. However, CEN-327 holds that
!, the test interval for process measurement sensors and subgroup actuation I relays remain the way technical specifications currently require.
2
( . ,
'
H . i
<* .
.; ; .
l
-
CEOG submitted CEN-327 to the NRC for review in June 1986. The NRC l
,s contracted with EC&G Idaho to perform an er. tensive technical evaluation. l q EC&G Idahe then submitted their report to the NRC. The NRC then performed additional reviews and prepared a draft Safety Evaluation Report (SER). '
The SER concluded that extending the RPS and ESTAS test intervals was ,
acceptable, j
!
The NRC reviewed CEN-327 and felt that changes in the RPS reliability that l result from extending the test interval from thirty days to ninety days I were acceptable. And, they were inclined to approve a ninety day RPS test j
, interval with sequential testing. Later, CE received additional feedback i from the NRC. While the NRC was inclined to find acceptable the RPS test '
i interval extention from thirty days to ninety days, with sequential testing, they could not include this in the SER for CEN-327 because CEN-327 ,
recommended more restrictive test intervals for certain trip parameters. 4 However, the NRC proposed to move forward on the 'M if CE issued a l i:upplement to CEN-327. The supplement to CEN-327 (sent to the NRC on March d 4 3, 1989) presents updated system reliability information for the RPS. And ,
it recommends a ninety day test interval with sequential testing for KPS. l L
The analysis results presented in CEN-327 and CEN-327 Supplement 1 ,
demonstrate that the surveillance test intervals for RpS and ESFAS
[
components can be increased without increasing public risk. In fact, for !
the test intervals propooed, the overall impact is a slight decrease in f public risk as measured by a net decrease in core melt frequency. !
Extending the test interval does not change the trip per test frequency, ;
but it does reduce the trip per year frequency, j The analyses and conclusions presented in both CEN-327 documents support this license amendment request to extend logic test frequencies as shown in i Attachment B. ESTAS actuation logic stays at the sequential monthly test j interval because the CEN-327 analysis did not include those relays. '
Supplement I showed the analysis applied to RPS from sensor (not including 1 the sensor) to CEDM breaker (not including the breakers). RPS logic can be tested through the final contact in the breaker opening logic. A similar .
test in ESFAS would start equipment in the plant.
[
t This submittal closely follows the rationale provided in CEN-327. That ,
topical report has extensive applications to all CE plants. If the NRC !
approves CEN-327, many plants will realize a significant safety benefit by ,
reducing the net core melt risk. Specifically, Waterford seeks to reduce its core melt risk by proposing this technical specification amendment. l l :
.
Safety Analysis ,
- 1. Will operation of the facility in accordance with the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? i Responset No.
,
Increasing the surveillance interval for RpS and ESTAS has two i principle effects with opposing impacts on core melt risk. The first l
< impact is a slight increase in core melt frequency that results from the increased unavailability of the instrumentation in i
3 5
.
^
. - _ . .
. . . _ _ _ _ - _ _ _
i .
' '
.
, !
- i. *.
u
"-
5 question. The unavailability of the tested instrumentation translates to a failure of the reactor to trip (AWS) or a failure of the l appropriate engineered safety feature to actuate when required. The l opposing impact is the corresponding reduction in core melt frequency !
..that would result because of the reduced exposure to test induced ;
transients. ;
Representative fault tree models for Waterford and the corresponding j core melt frequency increases and decreases were quantified in CEN-327. The unavailability assumption described above includes the j
' increased relay service time (relays are normally energized). For the j specific relaxations proposed in Attachment B, an extended l surveillance interval was found to result in a net reduction in core :
nelt risk. A lower potential for test induced trips over-shadows negative effects from increasing relay operating time.
!
Therefore, the proposed chsnge will not involve a significant increase i in the probability or consequences of any accident previously !
evaluated. l i
L 2. Will operation of the Facility in accordance with this proposed change !
create the possibility of a new or different kind of accident from any j
'
accident previously evaluated?
Response: No.
>
This amendment request does not involve any changes in equipment and will not alter the manner in which the plant will be operated. For l this reasou, this, amendment will not create the possibility of a new i or different kind of accident from any previously evaluated. ;
- 3. Will operation of the facility in accordance with this proposed change l involve a significant redaction in a margin of safety? ,
Response No.
F !
No margin of safety, based on the analyses of record and the existing ;
r limits of the technical specifications, will be reduced. There are no changes to the equipment or plant operations that will result. The i only impact of this change, an described in detail above, is a ,
reasoned balance between two factors. One, increased core melt risk .
because of slightly increased equipment unavailability. And two, an [
even larger reduced core melt risk because of a reduction in plant
)
'
exposure to test-induced trancients. The conclusions in the Waterford 3 FSAR remain valid and the safety limits continue to be met. Margins of safety are, therefore, not reduced.
, {
i
.
I
.
!
4 p
'
,
y_ ,
- -- - _ _ _ _ _ _ _ _ _ _
i F
'
- ,
- e .a , ,
6.- .. .:.- ,
.
Safety and Stanificant Hagards Determination
%. l y,.', - Based.pn the above Safety Analysis, it is' concluded thatt (1) the proposed 9e '
change:does not constitute a significant hazards consideration as defined
.,
by 10 CFR 50.923 and (2) there is a reasonable assurance that the health 4:.' and safety'of,the public wil) not,be endangered by the proposed change and .i (3) this action will not result in a condition.which significantly alters ;
,
'
'the impact of the station on the environment as described in the NRC Final Environmental Statement.' .
<i
@:' ,
+
1 i
i
" ;
, ' ,
I. , :
e, :
r L I
6- .,. ;
i 1
(
l P
,
P I
,.
t
..
- i. t t
u i
!
,
.;
f f
,
,
.i i
e
'
t l lt 3 {
d
'
l'.
1:' :
!
'
l
!
'
. . , <
' '
1 . 5 l- . i L-r $
5