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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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This License Amendment Request is submitted by North Atlantic Energy Service Corporation i pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
. Section 1 - Introduction and Safety Assessment for Proposed Change
. Section 11 - Markup of Proposed Change
. Section lli - Retype of Proposed Change
. Section IV -
Determination of Significant Hazards for Proposed Change
. Section V - Proposed Schedule for License Amendment issuance and Effectiveness
. Section VI - Enviroamentalimpact Assessment Sworn and Subscribed before me this
- 2n Wday of [h(L ' .1998 ,.
O hdd41 ' ' '
- 1. n ;t%d fed C. Felgeni.aun[
() Notaiy Public Executive Vice President and Chief Nuclear Officer 9805290190 990520 J PDR ADOCK 0500044a P PDR ,
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ f
5 Section i Introduction and Safety Assessment for the Proposed Change i
l PageI l
s
L INTRODUCTION AND SAFETY ASSESSMENT OF TIIE PROPOSED CHANGE A. Introduction License Amendment Request (LAR) 97-07 proposes a change to the Seabrook Station Technical Specifications (TS), Engineered Safety Features Actuation System Instrumentation Trip Setpoints, Table 3.3-4, Functional Unit 8.b, RWST Level--Low-Low, and associated Bases Section 3/4.3.2. The proposed change will revise the Refueling Water Storage Tank (RWST) setpoint associated with Automatic Switchover to the Containment Sump. The proposed setpoint is the result of a revised setpoint calculation which increases design margin and enhances the setpoint by providing both an upper and lower allowable value to more closely satisfy design basis requirements.
Currently, TS Table 3.3-4, Functional Unit 8.b, specifies the RWST Level Low-Low setpoint as 122,5.26 gallons with an Allowable Value of 2121,609 gallons. The proposed new setpoint will be 120,478 gallov with an Allowable Value band of 2119,435 to $ 121,521 gallons. Also revised is the Total Allowance (TA) and Sensor Error (S). The proposed changes are enhancements to account for the design bases of the setpoint and a revised drift value to accommodate a 24-month fuel cycle surveillance interval extension.
H. Safety Assessment of the Proposed Change The design bases for the RWST Level Low-Low setpoint, which initiates automatic ECCS transfer switchover, is to ensure that the minimum volume of water to support the assumptions made in the safety analysis is injected prior to switchover; and that there is adequate time available for the operators to complete the manual actions necessary to complete the switchover to the recirculation mode prior to reaching the level in the RWST where the onset of vortexing is of concern. Switchover from the RWST l to the containment recirculation sumps must occur before the RWST empties to prevent damage to the ECCS pumps and a loss of core cooling capability. For similar reasons, switchover must not occur before there is sufficient water in the containment sump to provide sufficient net positive suction head (NPSil) to support ECCS pump operation. Furthermore, early switchover must not occur to ensure that sufficient borated water is injected from the RWe~. This ensures the reactor remains shut down in the recirculation mode.
The RWST is a dual function component. For normal operation it is used to fill the refueling pool and canal for refueling operations, and to provide makeup to the spent fuel pool. For accident ec'iditions it is the source of borated water for the Emergency Core Cooling System (ECCS) pumps during the injection phase. When the water level in the RWST reaches the Low-Low setpoint, automatic ECCS transfer from the injection mode to the recirculation mode is initiated, i.e., the containment sump isolation valves are opened automatically and alarms are provided to alert 9 operators to begin the manual actions necessary to complete the transfer to the recirculation mode. Should full transfer (automatic and manual) i not be completed in sufficient time an RWST EMPTY alarm is provided to alert the operators to provide l adequate time to secure the ECCS pumps taking suction from the RWST prior to potential vortexing
- j. conditions occurring.
To satisfy the aforementioned requirements, the RWST Level Low-Low Allowable Value/ Trip Setpoint has both upper and lower limits. The engineering calculation that derived the RWST Level Low-Low Allowable Valueffrip Setpoint established an upper safety analysis limit (USAL) and a lower safety analysis limit (LSAL). The USAL is set at the minimum volume of borated water in the RWST that Page 2
6 must be injected into the reactor coolant system (RCS) during the injection phase to satisfy desigt basis requirements prior to initiation of automatic switchover to the containment building recirculation sumps.
The USAL is based on the TS limit alarm setpoint, minus instrument uncertainty and minimum injection allowance volume. The LSAL is set at the minimum volume of water in the RWST at which initiation of automatic switchover must occur in order to afford sufGeient time for the manual portion of switchover to the recirculation phase prior to reaching the level in the RWST where the onset of vortexing is of concern. The LSAL is based on the vortexing level plus an allocated transfer allowance volume to account for the manual transfer to the recirculauon mode, plus an allocated ECCS pump shutoff allowance volunie to account for securing the ECCS pumps after receipt of the RWST EMPTY alarm,
- and the instrument uncertainty band for the RWST EMPTY bistable. The LSAL includes the instrument uncertainty band for the RWST EMPTY bistable since the design basis for the lower limit is to provide adequate time to complete the switchover to the recirculation mode prior to receipt of the RWST
, EMPTY alarm. The proposed RWST Level Low-Low setpoint accounts for instrument uncertainty and l was selected to fall between the USAL and LSAL.
In addition, the new setpoint takes into account a revised drift value to accommodate a 24-month fuel cycle surveillance interval extension. The instrument uncertainty calculations used to support determination of the RWST Level Low-Low setpoint are based on the on-going Westinghouse effort in support of the surveillance interval extension to 24 months. Westinghouse speci0 cations for the current RWST level transmitters associated with the RWST Level Low-Low setpoint specify a value of 1% as the limit for drift over a 12-month interval. The 1% value, originally for a 12-month interval, is currently applied to the instrument uncertainty calculation for an 18-month interval. For the 24-month surveillance interval, a value of 2% is used. The Westinghouse drift analysis for these transmitters indicates a bias of 0.2% with a random uncertainty of 1.2%. Therefore, the 2% drift value used is conservative as compared with the Westinghouse analysis. Furthermore, the quarterly Trip Actuating Device Operational Test (TADOT) surveillance test will check for drift of the transmitter "Zero." This will provide additional assurance the transmitters are performing as expected.
Since the design bases place limits on the RWST Level Low-Low setpoint in both the upward and downward direction two Total Allowance and two Allowable Values were derived for TS Table 3.3-4.
These values reDect the USAL and LSAL. One Allowable Value places a limit on the setpoint in the upward direction and the other Allowable Value places a limit on the setpoint in the downward direction.
Correspondingly, TS Table 3.3-4 was also revised to reflect a new sensor error.
Overall, the proposed new RWST Level Low-Low setpoint increases the potential total volume of water injected from the RWST into the reactor coolant system (RCS) and/or containment by approximately 2000 gallons. It has been determined that the containment Hood level assumptions following a LOCA will not be adversely affected by the revised setpoint. The effect on sump pil and containment spray pH for accident conditions were evaluated with the conclusion that the change in pH is negligible. Therefore, there is no impact on Containment Building Spray (CBS) System performance or the parameters used for Environmental Qualification of electrical equipment.
Page 3
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