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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 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] |
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w 8 Atlantic SEABROOK STATION UNIT 1 Facility Operating License NPF-86 Docket No. 50-443 License Amendment Request No. 95-05 Positive Moderator Temperature Coefficient This License Amendment Request is submitted by North Atlantic Energy Service Corporation pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
Section 1 -
Introduction and Safety Evaluation for the Proposed Changes Section 11 -
Markup of Proposed Changes Section lli -
Retype of Proposed ChangesSection IV -
Determination of Significant Hazards for License Amendment Request 95-05 Proposed ChangesSection V -
Proposed Schedule for License Amendment Issuance and EffectivenessSection VI -
EnvironmentalImpact Assessment Sworn and Subscribed to before me thism 4 / day of M/2t4/ ,1995 Q / #O 0
/S h /Ar k b /[toer Efruce L. Drawbridge /
/ Nothry Public Executive Director hlycle3r Vroduction 9506080171 950530 PDR ADOCK 05000443 P PDR
1
- 1. INTRODUCTION AND SAFETY EVALUATION OF PROPOSED CHANGES A. Introduction The purpose of License Amendment Request (LAR) 95-05 is to propose changes to the Seabrook Station Technical Specifications to allow operation of the core with a positive moderator temperature coefficient (PMTC) at low power. Technical Specification 3.1.1.3 currently requires the moderator temperature coefficient (MTC) to be within the limits specified in the COLR with .
a maximum upper limit of 0 Ak/krF at all power levels. The implementation of this change will provide significant improvement in fuel utilization by reducing the amount of burnable neutron absorber required to control core reactivity. This reduction will result in a savings of approximately $800,000 per operating cycle. Therefore, North Atlantic has determined that LAR 95-05 qualifies as a Cost Beneficial Licensing Action (CBLA) as defined in NRC Administrative Letter 95-02.
In LAR 93-18m, North Atlantic proposed a PMTC for Seabrook Station. The proposed change to the Technical Specifications followed the example of other Westinghouse PWRs which were already licensed with a PMTC. LAR 93-18 included supporting material, i.e. YAEC-1871m, which referenced a Westinghouse topical report, WCAP-11993*, as a basis for demonstrating compliance with the risk goal of the ATWS RuleN while operating with a PMTC. Concurrent with the approvalm of LAR 93-18, the NRC stated that WCAP-11993 had not been reviewed and therefore could not be used as a basis for supporting a Technical Specification change to include operation with a PMTC. LAR 93-18 has been approved and License Amendment No. 33 was issued" without the proposed change to a PMTC. With the exception of the section which demonstrates compliance with the ATWS Rule, the safety analysis in YAEC-1871 with its approval in License Amendment No. 33 provides assurance that Seabrook Station can be safely operated with a PMTC.
LAR 95-05 renews the previously proposed (LAR 93-18) change to Technical Specification 3.1.1.3 to allow a maximum upper MTC limit of +0.5 x 10d Ak/k/ F with all rods withdrawn, beginning of cycle (BOC), for power levels up to 70% rated thermal power with a linear ramp to 0 Ak/krF at 100% rated thermal power. However, additional changes to the Basis for Technical Specification 3.1.1.3 identify a commitment to compliance with the ATWS Rule and the basis for the Rule by assuring that the ATWS core damage frequency is below the target of 4
1.0 x 10 per reactor year established in SECY-83-293m. This is achieved by determining a more restrictive cycle specific upper MTC limit which ensures compliance with the ATWS Rule and placing the MTC limit in the COLR. A cycle specific upper MTC limit will be determined using a proposed analytical method identified by reference in Technical Specification 6.8.1.6.b.,
Administrative Controls. The proposed method is described below.
In 1979, Westinghouse submitted two letter reports " on generic ATWS analysis and sensitivity j studies to the NRC. ATWS analyses were performed with a 95% MTC (-8 pcmrF). Actual MTC l values were determined to be more negative than this value 95% of the time for all Westinghouse plants. Results showed that the calculated peak Reactor Coolant System (RCS) pressure remained within acceptance criteria during a postulated limiting ATWS event. The analysis results were used in the formulation of the final ATWS Rule. The 1979 analysis and sensitivity studies were previously reviewed to ensure their applicability to Seabrook Station. This review included consideration of plant specific design features. The conclusion of the review was that peak RCS pressure during a postulated limiting ATWS event would remain within acceptance criteria, i.e.
no reactor vessel failure. This conclusion is true provided the MTC is more negative than .
1 1
l
. - _ _ . _ _ _ _ - - - - - _ _ _____ l
-8 pcmrF 95% of the time. Cycles can be designed such that the MTC remains within the limits of Technical Specification 3.1.1.3 as well as remaining more negative than -8 pcmrF 95% of the time.
He methodology proposed above is very similar to that used by Kewaunee to demonstrate the acceptability of a PMTC, which the NRC issued as Amendment 117 to Operating License DPR
- 043 on April 3,1995.
This section describes the proposed changes to the Facility Operating License to allow operation with a positive moderator temperature coefficient (PMTC) at low power. In summary, the proposed changes affect:
- 1) Technical Specification 3.1.1.3, Moderator Temperature Coefficient;
- 2) the Basis to Technical Specification 3.1.1.3;
- 3) Technical Specification 6.8.1.6.b, Administrative Controls; and I
- 4) the Core Operating Limits Report (COLR).
A detailed description of each proposed change is provided below.
- 1. Technical Specification 3.1.1.3. Moderator Temperature Coefficient i Technical Specification 3.1.1.3 states that the MTC shall be within the limits specified in the COLR and the maximum upper limit shall be less positive than 0 Ak/krF. The maximum upper limit is changed to +0.5 x 10d Ak/kFF for all rods out (ARO), BOC for power levels up to 70%
Rated Themial Power with a linear ramp to 0 Ak/kfF at 100% Rated Thermal Power. This follows the example of other Westinghouse PWR.s which are currently licensed with a PMTC and the change is supported by the safety analysis documented in YAEC-1871m approved in License Amendment No. 33"*.
- 2. Basis to Technical Specification 3.1.1.3 A paragraph is added to the Basis to Technical Specification 3.1.1.3 which states a commitment ,
I to compliance with the ATWS Rule and the basis for the Rule by assuring ATWS core damage frequency will remain below the target of 1.0 x 104per recctor year established in SECY-83-293m. This is achieved by determining a more restrictive cycle specific upper MTC limit which assures compliance with the ATWS Rule and placing it in the COLR.
- 3. Technical Specification 6.8.1.6.b. Administrative Controls Technical Specification 6.8.1.6.b lists the analytical methods used to determine the core operating l limits. The analytical method used to determine the cycle specific upper MTC limit placed in the j COLR which assures compliance with the ATWS Rule is discussed in this LAR. A reference is 1 added to Technical Specification 6.8.1.6.b.
2 l
l 1
- 4. Core Operatine Limits Report He COLR currently identifies the following cycle specific upper MTC limit:
The Afoderator Temperature Coefficient (AfTC) shall be less positive than 0 AWWFfor Beginning of Cycle Life (BOL), All Rods Out (ARO), Hot Zero Thermal Power Conditions.
Upon approval of this LAR, the cycle specific upper MTC limit will be changed to the value determined using the analytical method described herein. Typical MTC values with ARO, BOC are shown in Figure 1. Using the example of the typical core illustrated in Figure 2, the above COLR limit would be changed to:
The Afoderator Temperature Coefficient (AfTC) shall be less positive than
+ 0.23 x W AWWFfor Beginning of Cycle Life (BOL), All Rods Out (ARO),
Hot Zero ThermalPower Conditions.
This assures that operation with a PMTC will proceed in compliance with the risk goal of the ATWS Rule by limiting the MTC to the value assumed in supporting generic analysis"M.
B. Safety Evaluation of Proposed Chances Technical Specification 3.1.1.3 is modified to specify a maximum upper MTC limit of +0.5 x 10 d Ak/k/ F for all rods withdrawn, beginning of cycle (BOC), for power levels up to 70% rated thermal power with a linear ramp to 0 Ak/k/F at 100% rated thermal power. The safety analysis in YAEC-1871m w th its approval in License Amendment No. 33" provides assurance that Seabrook Station can be safely operated up to this proposed limit.
Changes to the Basis for Technical Specification 3.1.1.3 identify a commitment to compliance with the ATWS Rule and the basis for the Rule by assuring ATWS core damage frequency remains below the target of 1.0 x 104 per reactor year established in SECY-83-293m. This is achieved by determining a more restrictive cycle specific upper MTC limit which assures compliance with the ATWS Rule and placing it in the COLR. A cycle specific upper MTC limit will be determined using a proposed analytical method identified by reference in Technical Specification 6.8.1.6.b., Administrative Controls. The proposed analytical method is described in Section I.A of this LAR.
The least negative MTC values for a typical cycle occur with all control rods out (ARO) near beginning of cycle (BOC) conditions as illustrated in Figure 1. Figure 2 illustrates the least negative MTC near BOC as a function of thermal power level for a typical cycle. Figure 2 also illustrates the effect of designing a cycle with the least negative MTC limited to -8 pcmfF at hot full power (liFP), ARO. This is accomplished by adjusting the amount of burnable neutron absorber and, therefore, the critical boron concentration. The behavior of MTC with cycle exposure and power level is such that for cycles designed with a limit of-8 pcmfF at HFP, ARO, there will be times when the MTC is less negative. The power history of previous cycles at Seabrook Station was reviewed. The review involved determining the duration of periods when the reactor was critical but at less than full power. Assuming cycles were designed with a limit of -8 pcmfF at ilFP, ARO, the total fraction of time when the MTC would have been less negative was determined. The conclusion is that the MTC of previous cycles designed with a 3
limit of-8 pcmrF ARO,liFP would be less negative for less than 5% of the time. Future cycles are expected to have more efficient startups and fewer trips so that this conclusion applies to future cycles as well.
Technical Specification Surveillance Requirement 4.1.1.3.a states that the MTC shall be measured and compared to the BOC limit specified in the COLR, prior to initial operation above 5% of rated thermal power, after each fuel loading. Figure 2 illustrates the hot zero power (liZP), ARO, MTC limit which should be placed in the COLR for a typical cycle to assure thtt the limiting 11FP, ARO MTC is not less negative than 3 pcmrF. From Figure 2, the upper MTC limit for a typical cycle would be 2.3 pcmfF.
In the future, cycles will be designed so that the maximum upper MTC limit of Technical Specification 3.1.1.3 and the hot zero power (IlZP), all rods out (ARO) MTC limit in COLR is met. The cycle specific IIZP, ARO MTC limit in COLR will be adjusted, if necess,uy, to assure that the predicted MTC at BOC, ARO, hot full power (liFP) is equal to or more negative than the value used (-8 pcmrF) in the generic ATWS analysis. This assures that operation with a PMTC will proceed in compliance with the risk goal of the ATWS Rule by limiting the MTC to the value assumed in supporting generic analysisM The combination of proposed changes to Technical Specifications, Bases, and the COLR will allow core operation with a PMTC while assuring plant safety through:
- 1) compliance with the upper MTC limit assumed in the YAEC-1871 safety analysis approved in License Amendment No. 33; and
- 2) compliance with the risk goal of the ATWS Rule by limiting the MTC to the value assumed in supporting generic analysis.
4
References
- 1. NYN-93160, Letter from T.C. Feigenbaum (NAESCO) to USNRC," License Amendment Request 93-18: Wide Band Operation and Core Design Enhancements (TAC No. M87849)", November 23, 1993.
- 2. YAEC-1871, A.E. Ladieu, et.al., " Safety Analysis in Support of Wide-Band Operation and Core Design Enhancements for Seabrook Station", September,1993.
- 3. WCAP-11993, B.D. Sloane et. al., " Joint Westinghouse Owners Group / Westinghouse Program:
Assessment of Compliance With ATWS Rule Basis for Westinghouse PWRs", December,1988.
- 4. ATWS Final Rule - Code of Federal Regulations 10CFR50.62 and Supplementary Information Package, " Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light . Water-Cooled Nuclear Power Plants".
- 5. Letter from A.W. De Agazio (USNRC) to T.C. Feigenbaum (NAESCO), " Amendment No. 33 to Facility Operating License NPF-86: Wide-Band Operation and Core Enhancements - License Amendment Request 93-18 (TAC M87849)", November 23,1994.
- 6. Letter from A.W. De Agazio (USNRC) to T.C. Feigenbaum (NAESCO), " Correction to Amendment 33 to Facility Operating License NPF-86 (TAC M87849)", December 6,1994.
- 7. SECY-83-293, USNRC, W.J. Dirks, " Amendments to 10CFR50 Related to Anticipated Transients Without Scram (ATWS) Events", July 19,1983.
- 8. NS-TMA-2096, Letter from T. M. Anderson (W) to R. J. Mattson (USNRC), "ATWS Submittal",
June 8,1979.
- 9. NS-TMA-2182, Letter from T. M. Anderson (W) to S.11. Ilanauer (USNRC), "ATWS Submittal".
December 30,1979.
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' i FIGURE 1 SEABROOK STATION CYCLE 4 MODERATOR TEMPERATURE COEFFICIENT (ARO: Eauilibrium Xenon) 0.00 . .. . . . . .. ,
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-5.00 . !
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-20.00 o *
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- 30.00 i
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-35.00 g
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-- HZP No Xenon - HFP Eq Xenon
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FIGURE 2 i SEABROOK STATION CYCLE 4 MODERATOR TEMPERATURE COEFFICIENT (BOC: ARO: Eauilibrium Xenon) 3.00 2M
( '
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-1.00 N
-2.00 N s
-3.00 N \ \ .
k
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-4.00 Nx
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-6.00
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-7.00
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-9.00 l
-10.00
~
O 10 20 30 40 50 60 70 80 90 100 Power Level (%RTP)
-*- BOC Cycle 4 -*- ATWS L*mit !
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II. MARKUP OF LAR 95-05 PROPOSED CHANGES !
The enclosed markup pages reflect the currently issued version of Technical Specifications and Bases and include the changes approved in License Amendment No. 33, Wide-Band Operation and Core Enhancements"'). Revision bars are provided in the right margin to designate a change in the text.
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