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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy-4 Fuel Cladding Matl ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) ML20092F9141995-09-12012 September 1995 Application for Amend to License NPF-86,TS Bases for RCS Safety Valves Bases Section 3/4.4.2 Were Made to Clarify What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6251995-09-0505 September 1995 Application for Amend to License NPF-86,revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20086R2091995-07-24024 July 1995 LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual ML20085L1101995-06-16016 June 1995 Application for Amend to License NPF-86.Amend Would Increase Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5391995-06-0707 June 1995 Application for Amend to License NPF-86,consisting of Amend Request 95-02,revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9501995-05-30030 May 1995 Application for Amend to License NPF-86.Amend Will Allow Operation of Core W/Positive Moderator Temp Coefficient ML20082L5001995-04-17017 April 1995 Application for Amend to License NPF-86,revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20078E0351995-01-25025 January 1995 Application for Amend to License NPF-86,to Revise Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20076G2691994-10-0707 October 1994 License Amend Request 94-03 to License NPF-86,modifying TS Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20059H6321994-01-14014 January 1994 LAR 93-20 to License NPF-86,changing Administrative Controls in TS Section 6.0 to Redefine Composition of Sorc,Create Station Qualified Reviewer Program,Delete Requirement to Perform Periodic Procedure Reviews & Revise TS 6.4.2.9 ML20058C2991993-11-23023 November 1993 LAR 93-18 to License NPF-86,allowing Operation of Core within Axial Flux Difference Band Expanded from Current Band in TSs & Improved Fuel Cycle Mgt Through Implementation of Core Design Enhancements ML20059C5191993-10-28028 October 1993 LAR 93-14 to License NPF-86,changing TS to Implement 13 Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20057F2981993-10-0404 October 1993 Application for Amend to License NPF-86,proposing Changes to TS Correcting Inconsistency within TS by Deleting Requirement to Verify EDG Speed ML20056F7641993-08-26026 August 1993 LAR Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045C5541993-06-18018 June 1993 LAR 93-08 to License NPF-86,changing Title of TS 6.2.3 to Independent Technical Reviews & Deleting Requirement to Maintain Five Person Organization,Iseg ML20045D5831993-06-18018 June 1993 LAR Proposing Changes to Seabrook Station Tech Specs to Reduce Frequency of Surveillances Which Are Required to Verify Integrity of CST Enclosure ML20127F8071993-01-13013 January 1993 License Amend Request 92-015 to License NPF-86,changing TS 6.8.1.4, Semiannual Radioactive Effluent Release Rept, to Change Submittal Frequency from Semiannually to Annually ML20117A7941992-11-25025 November 1992 License Amend Request 92-14 to License NPF-86,revising TS to Allow Fixed Incore Detectors to Be Used as Independent Sys to Perform TS Surveillances ML20106E4151992-11-0303 November 1992 Application for Amend to License NPF-86,consisting of License Amend Request 92-04,changing TS to Revise Current Requirement That Operations Manager Hold Senior Reactor Operator License ML20115J4301992-10-22022 October 1992 License Amend Request 92-12 to License NPF-86,changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates ML20118B9391992-09-30030 September 1992 License Amend Request 92-13 to License NPF-86,increasing TS Temp Limit for Cooling Tower Basin Water from 67.3 F to 70 F & Permitting Cooling Tower Sprays & Fans to Be Manually Operated Following Cooling Tower Actuation 1999-06-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy-4 Fuel Cladding Matl ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092F9141995-09-12012 September 1995 Application for Amend to License NPF-86,TS Bases for RCS Safety Valves Bases Section 3/4.4.2 Were Made to Clarify What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6251995-09-0505 September 1995 Application for Amend to License NPF-86,revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20086R2091995-07-24024 July 1995 LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual ML20085L1101995-06-16016 June 1995 Application for Amend to License NPF-86.Amend Would Increase Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5391995-06-0707 June 1995 Application for Amend to License NPF-86,consisting of Amend Request 95-02,revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9501995-05-30030 May 1995 Application for Amend to License NPF-86.Amend Will Allow Operation of Core W/Positive Moderator Temp Coefficient ML20082L5001995-04-17017 April 1995 Application for Amend to License NPF-86,revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20078E0351995-01-25025 January 1995 Application for Amend to License NPF-86,to Revise Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20076G2691994-10-0707 October 1994 License Amend Request 94-03 to License NPF-86,modifying TS Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20059H6321994-01-14014 January 1994 LAR 93-20 to License NPF-86,changing Administrative Controls in TS Section 6.0 to Redefine Composition of Sorc,Create Station Qualified Reviewer Program,Delete Requirement to Perform Periodic Procedure Reviews & Revise TS 6.4.2.9 ML20058C2991993-11-23023 November 1993 LAR 93-18 to License NPF-86,allowing Operation of Core within Axial Flux Difference Band Expanded from Current Band in TSs & Improved Fuel Cycle Mgt Through Implementation of Core Design Enhancements ML20059C5191993-10-28028 October 1993 LAR 93-14 to License NPF-86,changing TS to Implement 13 Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20057F2981993-10-0404 October 1993 Application for Amend to License NPF-86,proposing Changes to TS Correcting Inconsistency within TS by Deleting Requirement to Verify EDG Speed ML20056F7641993-08-26026 August 1993 LAR Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045D5831993-06-18018 June 1993 LAR Proposing Changes to Seabrook Station Tech Specs to Reduce Frequency of Surveillances Which Are Required to Verify Integrity of CST Enclosure ML20045C5541993-06-18018 June 1993 LAR 93-08 to License NPF-86,changing Title of TS 6.2.3 to Independent Technical Reviews & Deleting Requirement to Maintain Five Person Organization,Iseg ML20127F8071993-01-13013 January 1993 License Amend Request 92-015 to License NPF-86,changing TS 6.8.1.4, Semiannual Radioactive Effluent Release Rept, to Change Submittal Frequency from Semiannually to Annually ML20117A7941992-11-25025 November 1992 License Amend Request 92-14 to License NPF-86,revising TS to Allow Fixed Incore Detectors to Be Used as Independent Sys to Perform TS Surveillances ML20106E4151992-11-0303 November 1992 Application for Amend to License NPF-86,consisting of License Amend Request 92-04,changing TS to Revise Current Requirement That Operations Manager Hold Senior Reactor Operator License ML20115J4301992-10-22022 October 1992 License Amend Request 92-12 to License NPF-86,changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates ML20118B9391992-09-30030 September 1992 License Amend Request 92-13 to License NPF-86,increasing TS Temp Limit for Cooling Tower Basin Water from 67.3 F to 70 F & Permitting Cooling Tower Sprays & Fans to Be Manually Operated Following Cooling Tower Actuation 1999-06-23
[Table view] |
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- j_. ,f New llampshire Yankee June 10, 1992 l
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.- l SEABROOK STATION UNIT 1 New Hampshire Yankee Facility Operating License-NPF 86 Docket No. 50-443 Supplement 1 to '.icense Amendment Request No. 92-01 RTD Bypass System . Elimination This License Amendment Request la submitted by New Hampshiro Yankee pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
.Section I - Introduction and Description of Proposed Changes
.Section II -
Markup of Proposed Changes Section ill -
Retype of Proposed Changes
.Section IV -
Safety Evaluation of Proposed Changes
.Section V - Determination of Significant Hazards for Proposed Changes
.Section VI - Proposed Schedule for License Amendment issuance and Effectiveness
. Section Vl! -
Environmental impact Assessment
- s
,- )
Sworn and Subscribed , ,/
to before me this '
/'7f/1 dsy of (dn = c - , if)9;l /e' V, & 7, /r G cs fMA / ,i. b_ f / h(c[f A V sruce L. Drawbridgb J Notary Public Executive Director Ruc!cardroduction l i
m orf/ A. D W . Dico, f : ten Put!'c l My Ccmm:40a rnpitc5 oct:,xt a 1995
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- 1. Int roduct ion and Descr ip' ton of pr oposed Chn.imentjup.plement 1 t o hieense Amendinent Request q ,.01 A. Introdurtion The purpose of Supplement I to License Amendment Request 9?-01 is to pr opose changes to the Seabrook St a t ion Technical Specif ications a ssot iated with a plant design change (DCR 90-03) that will eliminate the Resistance Temperature Detector (RTD) Bypash Syst ern which is cut t ent ly ut.ed f or the measurement of narr ow range Reactor Coolant System (RCS) hot leg and cold leg temperatures. The design change will remove the RTD Eypass, Systen piping and install new thetmevell tounted fast response RTDs in the hot leg and cold leg piping. The replace nent RTD/ thetmowell combinat ion meet s the f unctional ard qualification requirements of the existing RTDs mounted in the bypa s s pi%.ig. Additional instrumentation is added to pr ocess and average the new hot leg temperature input s. The colo leg and average hot -
leg temperature signals are input t o the existing reactor protection and '
reactor contro? , stems. Changes in the Westinghouse methodology ior treating hot a .. cold leg streaming, technical differences in the d
instrumentation, and allowance for operation with one hot leg RTD inoperable have resulted in a chango in instrumentatloa uncertainties. The proposed Technical Specification c hanges ref lect these differences in the instrumentation uncertainties associated with the new temperature measurement system and delete requirements f or verification of RTD bypas, loop flow.
Additionally, the pt oposed Technical Specification changes modif y the requirements f or the perf ormance of a precision heat balance which is used to determine RCS flow rate and to normalize t he RCS flow instrumentation.
The curront Technical Specifica, ion requirement s specif y that t b precision heat balance must be performed prior to opecation above 75% of rated thermal power after each fuel loading. Wes t inghet.se ha s reconct. ended tha t the precision heat balanca be performed abo"e 902 of rated aermal power t o minimize measut ement uncert ainties that are exacerbated a - lowet power levels. New Hampshire Yankee is, therefore, proposing a change to its Technical Specifications to requit? that the precision heat balance for determination of RCS flou rate be perf ormed prior to exceeding 95% of rated thermal power.
New Hampshire Yankee has also proposed to increase the Reactor Coolant System flow rate requirement of Technical Specification Limiting Condition for Operation (LCO) 3.2.5 from the current value of 391.000 gpm to a new value of 392,000 gpm to reflect the increase in flow mee.surement encertainty as documented in WCAp-13101 The proposed 2.41 flow measurement uncert ainty value includes an additional penalt y of 0.11 flow to account f or uudetected feedwater venturi t,uling as stat ed in the Bases for Technical Specification 3/4.2.5. /
The elimination of the RTD Bypass Sys;em has been implement ed by numerous licensees with Westinghouse Fuclear Steam Supply Systems. New Hampshire Yankee is aware of the follou ng licensees which have eliminated the RTD Eypass System:
1 I
b .
/ ,.
Duke Power Company (Catawba 1/2, McGuire 1/2)
Duquesne Light Company (Beaver Valley 1/2)
Florida Power & Light Company (Tutkey Point 3/4) 11ouston Lighting & Power Company (South Texas Project 1/2)
New York Power Authority (Indian Point 3)
Tennessee Valley Authority (Sequoyah 1/2)
Volf Creek Nuclear Operating Corporatien (Wolf Creek)
Northeast Utilities (Millstone 3)
Carolina Power & Light (H.B. Robinson)
South Carolina Electric & Gas (V.C. Sutume r )
Alabama Power Company (Farley 1. Farley 2 scheduled for Spring 92)
Georgia Power Cone ty (Vogtle 1 Vogtle 2 scheduled for Spring 9?)
Westinghouse has prepared a licensing report for N!!Y in support of the elimination of the RTD Bypass System at Seabrook Station. The Westinghouse -
licenalng report WCAP-13181, *RTD Bypa ss Elf mination Licensing Repot t for Seabrook Noclear Station * (Proprietary) is enclosed in Section VIII.
Yankee Atomic Electric Company (YAEC) has also evaluated the RTD Bypass Syster .11mination rela tive t o cont ainment tosponse, steam Jenerator Tube Rupture and Baron Dilution events. The YAEC evaluation conclusions and documentatic.) are discussed in Section V.
B. Description of Proposed Channes License Amendment Request 92-01 and Supplement I thereto propose changes to the following Technical Specificati'ns:
- 1. Table 2.2-1, " REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS,"
Pages 2-4, 5, 7 B, and 10 Technical Specification Table 2.2-1 terms associated with instrumentation uncertainty (TA, Z, S, ellowable value, and associated notes) have been revised due to technical differences in the RTD instrumentation, dif ferences in the We stinghouse methodology -
for treating hot leg and cold leg streaming and allowance for operation with one hot leg RTD inoperable. All values have been rounded to the nearest 0.12 in accordance with the latest Westinghouse format.
The value for the K 6 term in the overpower AT trip setpoint calculation was increased (conservative direction) . K6 is a penalty term that reduces the overpower AT trip setpoint when 'Javg is above the nominal Tavg. The setpoint when operating at or below the nominal Tavg is determined by a constant., R, 4 in the overpower AT trip setpoint calculation.
The value of the K 6 term in the overpower AT trip setpoint ,
calculation was increased as stated above. The overpower AT trip is intended to limit transient overpower during Condition and 1 s overpower transients / operator errors to 1181 power. As discussed in UFSAR section 4.3.2.2f and 4.4.2.11f, limiting overpower to 1181 2
t ,.
ensures that peak f uel rod lin ct heat generation rates during such an occut:ence will not exceed the 1ineat powerfot pt evention of f uel centerline melting. The K t term of the overpower AT trip is a penalty term that teduces the trip setpoint when T,y is above the nominal 7,y . An inctease in K, 5 is thetetore a thange in the conservative direttien. The need to modify Ks is explained below.
The overpower AT trip setpoint when operating at or below t he nominal T,y is determined by the E constant of the overpower AT trip t set point equatlon. The inct en se in the inst rument ation uncer t aint les associated with temoval of the RTD Bypass System results in an incresce in the safety analysis limit value for K t. This f ric r e a s e is reflected by the increase in the Technical Specif ication TA value for overpowet AT (the saf ety analysis limit value for K,cortesponds to the nominal K value plus the f ractional f ull power AT equiva. lent of the Technical Speciffration Th va1ue). Accommodation of the increased instrumentation uncertainty by increasing the safety analysis limit value f or K, allows the Technical Specification value for the nominal K 4 netpoint to t emnin unaf f ected by the removal of the RTD Bypane tystem.
The increase in tha saf ety analysis limit for K wa s accommodat ed in 5 the analysis by reducing margin available in the fit of the over power AT t r ip setpoint equation t o the 1181 powet loop LT data at average temperatures less than or equal to the nominal T,y. The increase in the saf ety analysis limit for K4 however necessit ated an increase in the Ko penalty term in order to maintain the t rip set point at or below 1182 for a range of average temperatures greater than the nominal T,y. The propobed increase in the 1erhnical Specification value for K6 ensures that the 1182 power limit will be protected at all average tempera ures.
Since the overpower AT trip with the modified setpoints will continue to ensure that the lle: overpower limit is protected for all ranges of operation, there in no decrease in the margin of safety.
- 2. 3/4.2.5. "D!lB PARAMETERS
- Page 3/4 2 10 The cur rent Technical Specificatien Surveillance Requit ement 4.2.5.3 specifies that the precision heat balance must be pettotmed prior tr " :tation above 75% of rated thermal power after each !uel Ic . Vestinghouse has recommended that the precision heat balm. e be performed tbove 901 of rated thermal power to minimize measurement uncertainties that are exacerbated at lower power level s .
11ew Hampshire Yankee has theref ore proposed a change to Surveillance Requirement 4.2.5.3 to require that the precision heat balance for determination of RCS flow rate be performed prior to exceeJing 952 cf rated thermal power.
New Hampshire Yankee has also proposed to increase tP' Reactot Coolant System flow rate requirement of Technical Specification Limiting Condition tor Operation 3.2.Sc from the current value of 3
391,000 gpm to a new value of 392,000 gpm to reflect the increase in flow measurement uncertainty as documented in VCAP-13181. The proposed 2.41 flow measurement uncertainty value includas an additional penalty of- 0.11 flow to account f or undetected f eedwates' venturi fouling as stated in the Bases for Technical Specification 3/4.2.5.
- 3. Table 4.3 1 ' REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS,* Pages 3/4 3-9 and 13 Note 12, relating to verification of RTD bypass loop flow rate. has been deleted since the RTD Bypass System is being eliminated.
4 BASES 3/4.2.5, 'DNB PARAMETERS," Page B.3/4 2-4 As discussed above. NHY has proposed to increase the DNB parameter -
limit on RCS flow rate from the current value of 391.000 gpm which includes 2.12 measurement uncertainty to 392.000 gpm which includes 2.42 measurement uncertainty. The revised value for RCS flow measurement uncertainty has been reflected in the BASED f or Technical Specification 3/4.2.5.
New Hampshire . Yankee notes that the deletion of the Technical Specification f or the Low RCS Tavg coincide t with teactor trip f eedwater isolation Functional Unit (Table 3.3-4.- Functional init 6.b) that was - recome.cnded in WCAP-13181 will be addressed in a future license amendment request.
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