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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] |
Text
. _ _ . _ _.. _ _ _ _ . .___, . - . _ _ _ . _ _
e e I l
North l Atlantic I 1
Facility Operating License NPF-86 Docket No. 50-443 i License Amendment Request No. 96-05 !
IMPLEMENTATION OF 10CFR50 APPENDIX J, OPTION B '
CONTAINMENT LEAKAGE RATE TESTING (TACM95312)
SEABROOK STA TION i
s This License Amendment Request is submitted by North Atlantic Energy Service Corporation l pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
Section 1 -
Introduction and Safety Assessment for the Proposed Changes Section 11 -
Markup of Proposed Changes Section 111 -
Retype of Proposed ChangesSection IV -
Determination of Significant Hazards for Proposed ChangesSection V - Proposed Schedule for License Amendment issuance and EffectivenessSection VI - Environmentallmpact Assessment Sworn and Subscribed to before 6# day meof U/ thiq,MfL- ,1996 N
M gj b Mp/@n Ted C. Folgenbaum
~
Not.ny5ublic
( Executive Vice P ident and Chief Nuclear Officer 9606110085 960604 PDR ADOCK 05000443 p PDR
I. Introduction and Safety Assessment for the Proposed Changes A. Introduction ,
Containment leakage rate testing includes the performance of an Integrated Leak Rate Test (ILRT), or Type A test, and Local Leakage Rate Tests (LLRTs), or Type B and Type C tests. Type A tests assess the overall leakage rate of the primary reactor containment while Type B tests detect leakage paths and assess leakage for certain primary containment penetrations. Type C tests assess containment isolation valve leakage rates. The requirements for the aforementioned types of leakage rate testing are delineated in 10CFR50, Appendix J (hereafter, Appendix J).
The Appendix J testing requirements ensure that leakage through the primary containment and systems penetrating primary containment does not exceed allowable leakage rate values as specified in the Technical Specifications ot associated Bases. These requirements ensure that an adequate primary containment boundary is maintained during and after an accident by minimizing potential leakage paths to the environment and that the primary containment function as assumed in the safety analysis will be maintained.
On February 4, 1992, the NRC published in the Federal Register the agency's planned actions and initiatives to eliminate requirements that are marginal to safety and yet impese significant regulatory burdens on licensees. The NRC concluded that decreasing the prescriptiveness of some regulations may improve their effectiveness by providing flexibility to licensees to implement cost effective safety measures. It was determined that the detailed and prescriptive technical requirements contained in some regulations could be improved and replaced with performance based requirements and supporting regulatory guides.
In accordance with the above conclusions, the NRC indicated that modifications to Appendix J could be considered. The performance-based containment leakage testing option, Option B of 10CFR50, Appendix J, became effective on October 26, 1995. This option allows the use of a reduced testing frequency for primary containment systems and components, based on performance history. The implementation of this option requires the development of a program based on Regulatory Guide 1.163, and modification of the technical specifications to reference this program.
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4 I
Description of Proposed Changes North Atlantic proposes to modify the Seabrook Station Technical Specifications to implement Option B to 10CFR50 Appendix J in accordance with Regulatory Guide 1.163. The Regulatory Guide endorses
, the performance based methods contained within NEI 94-01, Revision 0, l
- Industry Guideline for Implementing Performance Based Option of j 10CFR50 Appendix J", dated July 26, 1995. As required by Appendix J,
- Regulatory Guide 1.163 is included by general reference in the l proposed changes to the Technical Specifications. j The Technical Specifications for Seabrook Station are proposed to be j l modified as follows
- i
- 1. Definitions: Definition 1.7; Containment Integrity (Item d.)
is revised to reflect that leakage rates are in accordance j with the Containment Leakage Rate Testing Program.
- 2. Limiting Condition for Operation and Surveillance Requirements:
l a. Containment Integrity: Surveillance Requirement 4.6.1.1.c is deleted because the specific guidance is
! contained in the Containment Leakage Rate Testing Program.
- b. Containment Leakage: Limiting Condition for Operation 3.6.1.2.a-c and Surveillance Requirements 4.6.1.2.a-h are revised to replace specific guidance with a reference to the Containment Leakage Rate Testing
, Program.
- c. Containment Leakage: The Action for Limiting Condition for Operation 3.6.1.2 is revised to include the I equivalent Action as required for Limiting Condition for Operation 3.6.1.1 when the overall integrated containment leak rate exceeds 1.0 L.,
- d. Containment Air Locks: Limiting Condition for Operation 3.6.1.3.a-b is deleted and Surveillance Requirements 4.6.1.3.a-b are revised to replace specific guidance with a reference to the Containment Leakage Rate Testing Program. The footnote dddressing
- the exemption to Appendix J regarding testing the air j locks prior to establishing containment integrity will l be maintained in the Containment Leakage Rate Testing l
Program.
( e. Containment Vessel Structural' Integrity: Surveillance Requirement 4.6.1.6 is revised to replace specific i
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l
guidance with a reference to the Containment Leakage Rate Testing Program.
- f. Containment Ventilation System: Limiting Condition for Operation 3.6.1.7, Action b. is revised to replace specific guidance with a reference to the Containment Leakage Rate Testing Program. Surveillance Requirement 4.6.1.7.1 is revised to replace specific guidance with l a reference to the Containment Leakage Rate Testing l Program.
- g. Containment Enclosure Building: Limiting Condition for Operation 3.6.5.3 and Surveillance Requirement 4.6.5.3 are revised to include a reference to the requirements in the Containment Leakage Rate Testing Program.
- 3. Bases: Sections 3/4.6.1.2 (Containment Leakage), 3/4.6.1.7 (Containment Ventilation System) and 3/4.6.5.3 (Containment Enclosure Building Structural Integrity) are revised to l reflect the above changes including a reference to the Containment Leakage Rate Testing Program. In addition, a statement has been added to Section 3/4.6.1.2 to clarify the operability of containment regarding allowable leakage rates.
- 4. Administrative Controls: Section 6.15 is added to establish a Containment Leakage Rate Testing Program, as specified in Regulatory Guide 1.163, dated September 1995.
Summary of Changes to Seabrook Station Containment Leakage Testing l The proposed changes to the Technical Specifications will result in ,
the following changes to containment leakage testing at Seabrook j Station: 1 The current Type A test schedule la three tests in a 10 year period. l Based on demonstrating compliance with the performance criteria of Option B to Appendix J and references therein, the Type A test schedule could be extended to one test in a 10 year period.
If a Type A test is failed and the failure is not due to a Type B or C component, acceptable performance shall be reestablished by performing a Type A test within 48 months of the unsuccessful Type A test.
Following a successful Type A test, the surveillance frequency may be returned to once per 10 years. If a Type A test failure is caused by j
failure (s) of a Type B or C component, the corrective action for Type B and C failures would apply as stated below. In addition, the primary containment leakage rate acceptance criteria for operability remains at an overall leakage limit of 5; 1.0L..
I 3
General inspections of the accessible interior and exterior surfaces of the containment structures will be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test if the interval for the Type A test has been extended to 10 years, in order to allow for early detection of evidence of structural deterioration.
Extensions in Type B and C test intervals are allowed based upon completion of two consecutive successful periodic as-found tests.
Type B tests (with the exception of airlocks) may be extended to a maximum interval of 10 years. Type C tests (with the exceptions of containment purge and vent valves) may be extended to a maximum interval of 5 years. If a Type B or C test is not successful, the test frequency will be set at the initial test intervals.
Performance factors that will be considered prior to extending intervals are as follows:
a) Past component Performance -
Leakage rate testing intervals should not be extended until plant-specific component performance of two successful consecutive As-found tests are performed.
b) Service - Environment and use of components, c) Design - Valve type and penetration design.
d) Safety Impact -
Potential impact of penetration failure in limiting releases from the containment under accident conditions.
e) cause Determination - Common-mode failure mechanisms.
Test intervals will be established by reviewing Type B and C test data and determining if the Type B or C tests for each component had passed l or failed. The test interval assignments and all supporting l evaluations will be documented. If it is determined that a component l will remain on a two-year interval regardlesc of its historical l performance, interval establishment is not required. The allowable leakage rates are assigned to each Type B and C component. The allowable leakage rate assigned to each component is the administrative leakage rate limit and is specified to be indicative of the potential onset of component degradation. The leakage rate acceptance criteria are established in a conservative manner. In ;
setting these limits, credit is not taken for the effects of multiple penetration barriers in further reducing overall leakage through the penetration. Therefore, the acceptance criteria for the Type B and C tests remain at very low values.
Airlock testing has been increased to an interval of once per 30 months. When containment is required, airlock door seals will be tested within 7 days after each containment access. For periods of multiple containment entries where the airlock doors are routinely used for access more frequently than once every 7 days, door seals may be tested once per 30 days.
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O The North Atlantic allowable leakage rates or administrative limits for each component will be specified such that they are an indicator of potential valve or penetration degradation. A failure of the allowable leakage rate or administrative limit is not a failure of the Technical Specification requirement.
No change in the method of testing is being proposed. The tests will continue to be done at P., The test pressure for primary containment isolation valves will continue to be applied in the same direction as would be required for the valve to perform its safety function (unless a different direction can be shown to be equivalent or more conservative. Other programs are in place to ensure that proper maintenance and repairs are performed during the service life of the primary containment and systems and components penetrating the primary containment.
i B. Safety Assessment of the Proposed Changes The changes proposed by License Amendment Request 96-05 revise the l existing specific guidance in the Seabrook Station Technical j Specifications with a reference to a Containment Leakage Rate Testing l Program. The Containment Leakage Rate Testing Program will be l established in accordance with the recommendations of Regulatory Guide '
1.163, " Performance Based Containment Leak Test Program." This program will provide the acceptance criteria and testing schedule for containment penetrations in accordance with 10CFR50, Appendix J, Option B. ,
l The proposed implementation of 10CFR50, Appendix J, Option B has been determined to have a minimal impact on public health and safety, 1 Option B allows for reduced testing of those containment penetrations which have acceptable performance histories.
The k Staff has reviewed the potential impac'ts on safety associated with tLe implementation of 10CFR50, Appendix J, Option B and documented the impact in NUREG-1493, " Performance-Based Containment Leakage-Test Program." The document summarizes the impact of reducing the frequency of Type A tests from the current three tests in ten years to one test in ten years as an imperceptible increase in risk.
The Type B and C testing frequency changes are expected to contribute less than 0.1 percent (0.001) of the overall accident risk. *The overall impact of the combined rule changes were very small. EPRI Research Project Report TR-104285, " Risk Impact Assessment of Revised Containment Leak Rate Testing Intervals," also concluded that a relaxation of the test intervals for Type B and C penetrations results in a negligible increase in total plant risk. The implementation of Option B will allow the test intervals to be extended without challenging the radiological release limits from the site since all of the penetrations are periodically tested with leakage rates well below the specified limits.
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The testing history of containment penetrations at Seabrook Station has shown that the implementation of Option B will provide an appropriate level of assurance that the containment will perform the intended function and the radiological release limits will be maintained well below the limits set in 10CFR100.
The implementation of Option B will also reduce the exposure to personnel during performance of the required testing in accordance with the Containment Leakage Rate Testing Program. NUREG-1493 concluded that for Type B and C testing, although reducing the testing frequency led to minor increases in potential off-site dose
. consequences, the actual decrease in on-site (worker) doses exceeded (by at least an order of magnitude) the potential off-site dose increases.
In summary, the proposed performance based containment leakage rate testing program will have a minimal impact on public health and safety for the following reasons;
- The overall performance goal of ensuring containment isolation
- with a high degree of reliability can be demonstrated based upon continued excellent performance of the containment penetrations.
l Qualitative performance factors are considered in establishing performance criteria. These factors consider past - performance, component design, component service, safety impact and cause determination. =
- Quantitative acceptance criteria for testing will continue to be i established in a conservative manner.
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- Quantitative criteria for testing intervals are based on
- demonstrated component performance and the achievement of the l overall performance goal.
- The performance based testing program will continue to provide l
assurance that the accident analysis assumptions remain bounding.
l Conclusion Based on the above, the implementation of 10CFR50, Appendix J, Option B in accordance with Regulatory Guide 1.163 will provide adequate assurance that the containment will perform the design function, and have minimal impact on public health and safety or radiological releases.
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II. Markup of Proposed Changgg See attached markup of proposed changes to Technical Specifications.
The attached markup reflects the currently issued . revision of Technical Specifications. Pending Technical Specifications or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed markup.
l The page numbers of the affected pages are listed below.
, 1-2 Definitions I 3/4 6-1 Containment Integrity 3/4 6-2 Containment Leakage 3/4 6-3 Containment Leakage 3/4 6-4 Containment Leakage 3/4 6-7 Containment Air Locks 3/4 6-8 Containment Air Locks 3/4 6-11 Containment. Vessel Structural Integrity l 3/4 6-12 Containment Ventilation System 3/4 6-13 Containment Ventilation System 3/4 6-25 Containment Enclosure Building Structural Integrity Item 6.15 Administrative Controls B 3/4 6-1 Containment Systems B 3/4,6-2 Containment Systems B 3/4 6-4 Containment Systems l
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