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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] |
Text
.- -. . _ _ - - . .
~- g- SEABROOK STATION UNIT 1 Now Hampshiro Yankee
_m___ a Facility Operating Licenso NPF 86 Docket No. 50 443 Liconso Amendment Roquest No. 9110 Decoupling_ of the Loss of Ottalte PoWor/Safot'r injection Test From the 24 Hour Diesel Generator Survoillance Run t
This License Amendment Roquest is submitted by New Hampshiro Yankee pursuant to 10 CFR50.90. The following information is enclosed in support of this License Amendment Roquest:
. Section 1 -
Introduction and Description of Proposed Changos
. Section 11 - Markup of Proposed ChanDos
. Section lli - Rotype of Proposed Changes
.Section IV - Sefoty Evaluation of Proposed Changos
.Section V - Determination of Significant Hazards for Proposed Changes
.Section VI -
Proposed Schedulo for Licenso Amendment issuanco and Effectivonoss
. Section Vil -
Environmental Impact Assessment Sworn and Subscribed to before me this
,Rof/ day of //fhM ,1992 , ,
A-f6M C4^ ~
Gkgfi/M ,b/ W3I4 Ted'C/elgenbaum
[ffotary Public ,
Prealdent and Chief Executive Officer ta w .
.a L,g v ., i tja 92o3310280 920320 PDR ADOCK 05000443 F PDR
i I
e
. l 1, hiami,jnJ.jas,Lynd liesLthjhp of Prooo>eil Cbynn3. [
J A. Introduction -
J l The purpose of the proposed Tnhnical Specification change is to sevise Technit al Specification 3/4.8.1 'A.C. Sou ces" to separate the Loss of Olisite Pow e r /S alct y (
- injection (l.OP/SI) test frora the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> diesel generator surseillance run. The
- purpose of the LOP /S! surteillance is to demonstante that the diesel generator oill ,
start, energi/c the einergency. busses, and sequence on safety injection required loads following a loss of offsite power coincident with a salcty injection actuation. The hot nestart capability of the diesel generator is demonst ated by acquiring the diesel :
generator to be at normal operating temperature prior so the start of the sutveillance. l The NitC has previously seviewed and approved similar testing changes at other plants t (e.g., Grand Gulf Nucleus Station, Unit 1 Amendment No. 52 to License No. NPP49;
- itiver llend Station, Unit 1, Amendment No. 43 to 1.icense No. NPF.47; and Virgil C '
Summer Nuclear Station Und 1, Amendment No. 94 to 1.icense No. NPP 12).
As presently _ waitten Technical Specification Su r s eillanc e lleq uir eme nt 4 A 1.1 2f.7 requires the LOP /Si test to be perfortued within $ minutes of completing the 24 hout diesel generator surveillance sun. This requirement is derived from llegulatory Guide r 1.108, Pc_rlodle Testine _ of 111esel Generator LinittL,J),syd n> Onsite-_ Ilul.rle Pou er
)fpgm_s; nt _ Ngghpr Power Plants. The current Technical Spe(ification requiremeur creates significant schedu!ing demands during an ouhge by reducing schedule flexibility and unnecessarily canktraining outage activities. Due to the current requirements of Surveillance ~1tequirement 4 A1.1.2f.7. it would not be prudent during an outage to ,
uttempt the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tun of the diesel generator until all of the diesel generator design loads are operable and capable of satisfying the requirements of the I.OP/S! lest.
Since all of these loads are not typically operable until near tne end of the outage. the perfo mance of Surveillance Requirement 4AL1.2f.7 is forced to occur as a critical path item. If these tests are separated, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> diesel generator run may be performed earlier in the outage in parallel with critical path activities. New llampshire ,
Yankee (NilY) believes that the proposed Technical Specification change satisfies the intent of Ilegulutory Guide LIOS as discussed below.
Regulatory Guide 1.108 Position C.2.a(5), which is the basis for the requirement to perform the LOP /SI test immediately after the diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test states that the purpose of the requirement is im " demonstrate functional capability at full load temperature conditions' Decoupling the two tests does not invalidate or reduce the effectiveness of either test, provided full load temperature conditions are achieved prior to perforrning the LOP /S! test.
- To. ensure that the intent of Regulatory Guide 1.108 Porition C.2.a($) is met, a requirement to operate the diesel generator loaded to greater than or equal to 6083
- kW for at least 60 minutes has been included in the proposed Technical Specification change. This requirement will be satisfied prior to performance of the LOl/SI test The concept of separating the LOP /SI test from the diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run is acknowledged in the existing Seabrook Station Technical Specifications. The note at the bottom of page 3/4 8 7 states: *1f Specification 4X Lt.2f.6)b) is not sutisfactorily I
completed, it is-not necessary to repeat the preceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, instead the diesel i
l 1 I
--~,cy-~w-,,,,-.emw y-,m, n p .m,,%,.w,wm#w.,%,.,..e.,,c,,,3--..c,-n.,-__m,,,m-r_,m,.,.,.n..mpw--.rweg.,e-,-,,,wms,y_,,.,.,+,,,.,r.,,,e,,.-ym._,_.i.--,.,,_.y--,_,,-,%,--,.1
- - -_ _ . . ~ . . - . - _ - - . - - - . . . - - - . _ _ . - . - . _ _
i l
generator rnay be operated at 6083 kW for I hour or until operuting, temperature has stabillied' Specification 4,8.1.L2f 6)b) is the LOP /SI test 4 11 is citar f rom the current I Technical Specificalmus that the actual required prerequisite for the Lor /SI test ir. that i the diesel generator be at its normal operating temperature.
New ilampshire Ynnkee has substantial experience operating the diesel generators and ;
the operating history confirms that normal operating temperatures will be reached following a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> run when the diesel generator is loaded to at least 0083 kW. This ,
has been verified by NilY through a review of diesel generator monthly Technical i Specification r.urveillance data. The manufacturer of the Seabrook Station diesel 4 generuur, Colt industries, has also documented by letter to NilY that operation af the diesel generator for at least one hour at a load of 6083 kW should establish stable operating temperatures. .
1 (L Description of Changes The following changes are proposed to Trehnical Specification 3/411: -
3
- 1. S U R Vlill.LA NCli iti!OUliti!Ml!NT 4 A 1.1.2f.6)b). This Surveillance llequirement is resised to require that the I.Ol'/S! lest be conducted within 5 minutes of operating the diesel generator at greater .than or equal to 6083 kW ,
for at least_60 rninutes. This proposed surveillance requirement ensures that the intent of Regulatory Guide L108 is met by serifying the diesel generator is at normal operating temperature prior to the initiation of the LOP /S! test.
- 2. SURVlilLLANCII RIIOUIRIIM1!NT 41Lt.2f.7). The last sentence is deleted since the requirement to perform the LOP /SI test within 5 minutes of completinh the diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run has been revised. The new requirement is to ,
run the dietel generator at greater than or equal to 6083' kW for at least 60 3 minutes prior to starting the LOP /SI test and is contained in Surveillance Requirement 4A LL2f.6)b). In addition, the footnote at the bottom of page 3/4 8-7 is applicable to the sentence on this page which is deleted, therefore it is deleted. The requirements contained in the footnote are incorporated into the proposed change to Surveillance Requirement 41LL2f,6)h). Since the operating historf of the diesel generators indicate that normal operating temperatures will be reached following a 60 minute run at greater that, or equal to 6083 kW, the statement *or until operating temperature has stabiliicd* is deleted. Removing "
this statement _will enhance the clarity of the Surveillance Requirement.
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