|
---|
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
W ENTERGY y " """" " '""'
- ,4 e .6 > ,
_ . . . . _ . . . . - . . . . - - - - - ..-.__,-_____.__._m_ . _ _ . . . _ _ .
Ross P. Barkhurst W3F1-94-0132 A4.05 PR i
i August 19, 1994 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-38-157 Gentlemen:
9 The attached description and safety analysis support a change to the Waterford 3 Technical Specifications (TS).
The proposed change modifies the Waterford 3 TS by relocating the requirements of specification 3/4.3.4 Turbine Overspeed Protection from the TS pursuant to the NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors. i The proposed change has been evaluated in accordance with 10CFR50.91(a)(1) using criteria in 10CFR50.92(c).and it has been determined that the proposed change involves no signi.ficant hazards considerations. The Plant Operations Review and Safety RevieN' Committees have reviewed and accepted the proposed change based on the evalu'ation mentioned above.
The circumstances surrounding this request, as discussed below, are such that your expeditious review is respectfully requested.
In NUREG 1366, " Improvements to Technical Specifications Surveillance l Requirements," dated December 1992, the NRC Staff recommended that where )
the turbine manufacture agrees, the turbine valve testing frequency should i be changed from monthly to quarterly. In early 1993 Waterford 3 contacted l 2.7 D 01 1 0{
9408240339 940919 1 i
PDR p
ADOCK 050003B2 PDR I) .
l
4 Technical Specification Change Request NPF-38-157 W3F1-94-0132 Page 2 August 19, 1994 C
Westinghouse Electric Corp. (the Waterford 3 turbine manufacture) in an effort to obtain an agreement to extend the monthly turbine valve test. 1 Unfortunately, Westinghouse was unable to accommodate this request until just recently. Currently, Westinghouse is conducting an analysis (should be completed by early September 1994) to extend the Waterford 3 turbine ,
valve testing interval. Westinghouse was able to provide preliminary results that indicate that the analysis will support the reduced turbine valve test frequency.
Waterford 3 is especially concerned with turbine valve testing for the remainder of Fuel Cycle 7 due to increased Dose Equivalent Iodine (DEI) in the Reactor Coolant System (RCS). Shortly after start-up following Refuel 6, a small amount of DEI was observed in the RCS indicating the presence of a fuel leak. The observed DEI is well below the Technical Specification limit. However, turbine valve testing requires a reduction in power.
Waterford 3 reduces power to 90% for turbine valve testing which causes a DEI spike in the RCS. During the last test at Waterford 3 in July 1994, DEI increased by a factor of 2.5 (see attached figure) before returning to approximately the previous level by Chemical Volume Control System (CVCS) purification. RCS activity spikes such as these result in the potential for increased personnel exposure, increased radioactive wastes, and increases in the plant's contaminated areas. Additionally, Waterford 3 is interested in minimizing unnecessary transients that could worsen the condition of the fuel . -
Waterford 3 will conduct. turbine valve testing as required this Saturday, August 20, 1994. Precautions will be. taken such as installing new resin beds and reducing DEI in the RCS (through the use of 2 charging pumps) to as low as possible prior to the test. Turbine valve testing will not be required for another 38 days or until September 27, 1994 (i.e., TS 31 day surveillance requirement plus 25%). If this proposed change is approved by 1 September 27, 1994 the turbine valve test interval extension can be implemented with the completed Westinghouse analysis via 10 CFR 50.59.
l
\
l I
l i
Technical Specification Change Request NPF-38-157 W3F1-94-0132 Page 3 August 19, 1994 Should you have any questions or comments concerning this request, please contact Paul Caropino at (504)739-6692.
Very truly yours,
',/-
[ ./
gprg
~~
k R.P. Barkhurst Vice President, Operations Waterford 3 RPB/PLC/ssf
Attachment:
Affidavit NPF-38-157 Reference List cc: L.J. Callan, NRC Region IV D.L. Wigginton, NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office Administrator Radiation Protection Division (State of Louisiana)
American Nuclear Insurers
?
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the matter of )
)
Entergy Operations, Incorporated ) Docket No. 50-382 Waterford 3 Steam Electric Station )
AFFIDAVIT D.F. Packer, being duly sworn, hereby deposes and says that he is General Manager, Plant Operations - Waterford 3 of Entergy Operations, Incorporated; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Technical Specification Change Request NPF-38-157; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
w D.F. Packer rm General Manager, Plant Operations -
Waterford 3 STATE OF LOUISIANA )
) ss PARISH OF ST. CHARLES )
Subscribed and sworn to before me, a Notary Public in and for the Parish and State above named this /9 " day of avg vm , 1994.
l l.
IL SfYl % '
l Notary Public My Commission expires r" 'M .
. >+hn r " Q zW g8W?Sw IEA 3
\
l T94i4 l
TT3'$
l T 3' M g
l 3'8 n
it s
e T
E N
V e n
ib l
T93'
D T u
O I
T N i T$3'8 E
L A
V I
U l e Q T93'
E o E
S O k D a e
l T9C46n L
l e
u F
f r o e e l
.C44a w c o n P a r
k
% a c
a e
p 0
bt 0 p u 1 A T@C46u C t o
r e d -
w e o n r
P u r
o t
e Y 49C44-t R c
a e
R Y[ T9C46-1 1 1 2 2 2 2 0 0- 0 -
0- 0- 0- 0- 0- 0 E E E E E E E +
0 0 O O O O O E 4 2 O. O. O. O O. O.
1 1 1 8 6 4 2 O.
0 T8s I ! '
DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-38-157 This proposed change modifies the Waterford 3 Technical Specifications' by removing the requirements associated with 3/4.3.4 Turbine Valve Overspeed Protection. The proposed change will relocate these requirements to the Waterford 3 updated Final Safety Analysis Report (FSAR) to further the goal of Technical Specifications Improvements as delineated in NRC policy statements.
Existina Specification See Attachment A Proposed Specification See Attachment B Backaround On February 6, 1987, the NRC published its Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors in the Federal Register (Reference 1). In late 1987, based on the Interim Policy Statement, each of the four nuclear steam supply system (NSSS) owners groups submitted proposals identifying requirements in the existing Standard Technical Specifications (STS) that could be relocated from the TS to licensee controlled documents. The staff reviewed these submittals and published its conclusion in the report "NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups' Application of the Commission's Interim Policy Statement Criteria to Standard Technical Specifications", or " Split Report"(Reference 2).
The NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (Reference 3) provides criteria to be utilized in determining which requirements need to be governed by TS. The goal is to assure that TS requirements are consistent with 10 CFR 50.36 and have a sound safety basis. The Split Report identified which STS requirements must be ;
retained in the new STS (having met one or more criteria) and those requirements that could be relocated (having met none of the criteria).
Following the guidance of the Split Report, the owners groups proposed improved STS thaj were subsequently approved and published by the staff as improved STS NUREG reports.
l I
CEN-355 Vol. 5 " Restructured Technical Specifications, Discussion of Changes" (Reference 4), indicates that the Turbine Valve Overspeed Protection I requirements are relocated per the criteria application. The CE restructured I STS were approved by the staff and issued via NUREG-1432 " Standard Technical Specifications Combustion Engineering Plants." Therefore, Waterford 3 proposes to relocate the identified requirements consistent with NRC approved TS improvements. j Description j l
The proposed change removes the Limiting Condition For Operation (LCO) I 3/4.3.4, the associated Surveillance Requirements, and Bases information from the TS. This information and requirements will be incorporated into the Waterford 3 Updated Final Safety Analysis Report (UFSAR) and maintained under the provisions of 10 CFR 50.59.
The proposed change deletes TS page 3/4 3-68 and Bases sections 3/4.3.4.
Index page V is revised to remove reference to Turbine Overspeed Protection.
The Turbine Overspeed Protection specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are operable and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment, or structures.
The NRC Policy Statement on Technical Specification Improvements for Nuclear Power Reactors provides the following criteria that delineate those constraints on design and operation of nuclear power plants that are derived from the plant safety analysis or probabilistic safety assessments and that belong in Technical Specifications in accordance with 10 CFR 50.36:
Criterion 1: Installed ins'trumentat.ioif.That is use'd to detect, and
'. indicate in' the ,co,ntro'l room,'a significant a~bnormal degradation of the reactor coolant pressure boundary.
Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a Design ~ Basis Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 3: A structure, system, or component that is part of the primary success path and which functions to actuate or mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to a fission product barrier.
Criterion 4: A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
An evaluation of the of the Turbine Overspeed Protection System at Waterford 3 determined that this system does not meet any of the criterion listed above.
Therefore, Specification 3/4.3.4 may be relocated from the Waterford 3 TS to the UFSAR pursuant to the NRC Final Policy Statement on Improved Technical Specifications.
Safety Analysis The proposed change described above shall be deemed to involve a significant hazards consideration if there is a positive finding in any of the following areas:
- 1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of any accident previously evaluated?
Response: No The proposed change relocates the Turbine Valve Overspeed Protection requirements from the TS to the Waterford 3 UFSAR consistent with the NRC Policy Statement on Technical Specification Improvements. Testing and inspections of the turbine Overspeed Protection System will remain governed by an approved turbine maintenance program, described in the VFSAR. This proposed change has no affect on the current Turbine Overspeed Protection requirements other then to relocate them to the ,
UFSAR. Thus, the probability of a turbine missile causing damage to a j safety-related component or structure at Waterford 3 as described in the 1 FSAR analysis (Reference 5) is not affected. The purpose of the Turbine Overspeed Protection System is to prevent an overspeed event, the precursor to a potential turbine fragment missile. Since the purpose of this system is preventive, it serves no function to mitigate any accident previously evaluated.
Therefore, the proposed change will not involve a significant increase
-in the probability or consequences of any accident previously evaluated.
- 2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different type of accident from any accident previously evaluated?
Response: No The proposed change does not involve any change to the configuration or methorj of operation of any plant equipment. No new failure modes or limiting failures have been identified as result of the proposed change.
The proposed change will not alter the operation of the plant or the manner in which it is operated. Any subsequent change to the Turbine Overspeed Protection System requirements will undergo a review in accordance with the criteria of 10 CFR 50.59 to ensure that the change does not involve an unreviewed safety question.
Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change will relocate Turbine Overspeed Protection System requirements from the TS to the Waterford 3 UFSAR on the basis that the Turbine Overspeed Protection System does not meet the criteria of the NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Reactors. The requirements that will reside in the UFSAR for the Turbine overspeed Protection System will ensure that the system !
. remains capable of protecting the turbine from excessive overspeed. The proposed change will have no adverse impact on any protective boundary l or safety limit.
I Therefore, the proposed change will not involve a significant reduction in a margin of safety.
1 Safety and Sianificant Hazards Determination J
Based on the above safety analysis, it is concluded that: (1) the proposed l chango does not constitute a significant hazards consideration as defined by 10CFR50.92; and (2) there is a reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (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.
+
- 1. 10 CFR Part 50 " Proposed Policy Statement on Technical Specification Improvements for Nuclear Power Reactors" (Federal Register / Volume 52, No. 25 / Friday, February 6,1987 / Rules and Regulations).
- 2. "NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups Application of the Commissions Interim Policy Statement Criteria to Standard Technical Specifications" dated May 9, 1988.
- 3. 10 CFR Part 50 " Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (Federal Register / Volume 58, No. 139 / Thursday, July 22, 1993 / Rules and Regulations).
- 4. CEN-355 Volume 5 "C-E Owners Group Restructured Standard Technical Specifications Discussion of Changes" May, 1989.
- 5. Waterford 3 Final Safety Analysis Report Section 3.5.1.3 Turbine Missiles; Subsection 3.5.1.3.3 Turbine Failure Missile - Probability Analysis i
l
+ 6 - + .-.s> .+ n - nL .
,u-.= a..--s-.m -. - sua.1 a an-- . . __. ,___ _ _ _, _
1 4
NPF-38-157 ATTACHMENT A