|
---|
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
-. - . - - - . . .
SEABROOK STATION UNIT 1 New Hampshire Yankee Facility Operating License NPF 86 Docket No. 50 443 License Amendment Request No. 91-10 Supplement 1 Revision to the Diesel Generator Surveillance Requirements This License Amendment Request is submitted by New Hainpshire Yankee pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
. Section 1 -
Introduction and Description of Proposed Changes Section ll -
Markup of Proposed Changes i
. Section ill -
Retype of Proposed Changes
.Section IV -
Safety Evaluation of Proposed Changes
)
Section V -
Determination of Significant Hazards for Proposed Changes
.Section VI -
Proposed Schedule for License Amendment issuance and Effectiveness
. Section Vll -
Enviro.1 mental Impact Assessment w
Sworn and Subscribed 'f 7- /
/ day ofme to/r/oefore d?this.
.n ,1992 -
, 74 4 / M bdO, c/, e o W h e h % db h BrucIIL Drawbridge /
-dNotary Public Executive oirector Nuclear. Pr6, duction mACY A D:Cnit;CO. May rurc y cmme, tpa xg 7 3, 7393 9206240289 pDit 920619 0 ADOCK 05000443 PDR
I. Jntroductiori and llescription of Proposed Channes A. Introduction The purpose of the proposed Technical Specification change is to revise Technical i Specification 3/4.8.1 ' A.C. Sourcer." to:
- 1. Revise the method of verifying diesel generator hot restart capability. Presently Technical Specification Surveillance Requirement 4.8.1.1.2f.7) verifies diesel generator hot restart capability by initiating a Loss of Offsite Power / Safety injection (LOP /SI) test within 5 minutes of completing the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> diesel generator run. The curient Technical Specification creates significant scheduling demands during an outage by reducing schedule flexib!!ity and imposing unnecessary operational burdens. The ,
revised Surveillance requirement will verify dicsci generator hot restart capability by either manually or automatically starting the diesel generator and verifying that it attains rated voltage and frequency within the required time. i i.o requirement to sequence on the LOP /S1 loads does not contribute to verifying the abihty of the diesel generator to start from normal operating temperatures. ;
Regulatory Guide 1.108, Periodle Testine of Diesel Generator linits th rd n Onsig i filectric Power %tems at Nuclear Power Plants Position C.2.a($), which is the basis for the requirement to verify hot restart capability by performing a LOP /SI test immediately following the 24 hout test states the pur!mse of the requirement is tm
" demonstrate functional capability at full load temperature conditions #. The capability of the diesel generator to start from a normal operating temperature condition will continue to be verified. Demonstrating diesel generator hot restart capability without loading the engine with LOP /SI loads does not invaHdate or reduce the effectiveness of either test, provided normal operating temperatures are achieved prior to demonstrating hot restart capability.
Normal operating temperature conditions will be assured by perf irming the test within ;
5 minutes of completing the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> diesel generator run. If fer some reason the surveillunce cannot be conducted within the 5. minute time period, or if the surveillance is unsuccessful, the engine may be brought to normal operating temperature by operating at a load of greater than or equal to 5600 kW and less than or equal to 6100 kW for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperature has stabilized.
- 2. - Surveillance Requirement 4.8.1.1.2a.6) specifies l' tt that at least once per 184 days, that the diesel generator be rapidly loaded to g.; 4er than or equal to 6083 kW in less than or equal to 120 seconds. Rapidly loading the diesel generator in this ,
manner introduces mechanical stresses and engine wear. The purpose of this test is l to demonstrate that the dicscl generator is capable of accepting load by simulating the loading rate of the emergency power sequencer. This test does not validate any operational rcquirement which is not demonstrated by performance of Surveillance Requirements 4.8.1.1.2.f.4) and 6). These tests are the Loss of Offsite Power and Loss of Offsite Power / Safety injection f :sts. Performance of these tests demonstrate that the dicsci generators- are capable of ac cepting lead as it is sequenced by the emergency power sequencer.
I 1 l
l l
t
.. -. . _ . _ , , _ _ - , , _ a,_._., .. . , . _ . _ . . . . , _ . _ , , . _ , _ . , _ , _ _ _ ,.,.,,.,.m , , - , , , . . _ _ _ . _ , , - , _ _ , . .
The:cfore, the part o' Suncillance itequitement 4.8.1.1.2f.0) to rapidly load the dicsci generator in less than or equal to 120 seconds % deleted.
- 3. A load range is being provided where applicable to preclude routine overload of the diesel generator. As presently written, during surveillance test:ng which requires loading of the die:,el generator, the operator must maintain load greater than the continuous diesel gcnerater load rating of 6083 kW This is to prevent grid induced transientr,, specifically changes in Volt Amps Reactive (VARS), from lowering the ;
output of the diesel generator to less than the surveillance required load of 6083 kW. !
Operation significantly above this load has manufacturer imposed limits on the time that this rating can be exceeded. Thus, providing a load range of greater than or equal to 5600 kW and less than or equal to 6100 kW will preclude significant routine exceedance of the diesel generator coritinuous load rating.
Similarly, the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of the diesel generator is tested by operating ut a load of preater than or equal to 6697 kW. ~1 his requirement is revised to greater than or equal to 6300 kW and less than or equal to 67JO kW. ;
Loading the diesel generators to these ranges will preclude routine overload of the diesel generators but will still demonstrate that the diest i generators are capable of i supporting operation of the emergency busses.
- 4. The term " ambient condition" is used in Surveillance Requirement 4.8.1.1.2a.5) t o describe the conodion from which the diesel generator is to be started. This term does not -ccount for the jacket water and lube oil warming systems which are continuously in operatmn. A more accurate term to describe the condition which the -
diesels are mainteined is
- standby" Therefore, to improve the clarity of the Technical Specification and to more accurately describe the condition in which the diesel generators are maintained, the term " ambient condition" is being replaced with
" standby conditions" in Surveillance requirement 4.8.1.1.2a.5), and the term standby conditions" is added to Surveillance Requirements 4.8.1,1.2f.4)h) and 4.8.1.1.2f.6)b). l S. -Several notes are being revised and or added as necessary. The purnose of the changes is to provide amplifying information for the applicable Technical Specification to enhance and improve its clarity. The details of these changes arc discussed in Section B below.
l
-H. Description of Changes The following changes are proposed to Technical Specification 3/4.8.1:
- 1. The second ' sentence of the note at the bottom of page 3/4 8.3 is deleted. The note will now state: "All-starts for the purpose of these suncillances may be preceded by an engine prelube period" The second sentence is being deleted since the Seabrook Station emergency diesel generators are not gradually accelerated to operating speed.
The SURVEILLANCE REQUIREMENT to which this note is applicable is changed i
2
1 l
e F from substep 5) to apply to the entire SUltVElLLANCE RiiOUIREMENT of 4.N.1.1.2 because the cugine prelube option is applicable to all test starts.
- 2. The term "a mbie nt condition" is replaced with the term " standby conditions" in SU RVElLLANCE R EQUIREM ENT 4.8.1.1.2a.5). The term " standby conditions" is inserted in SURVEILLANCE REQUIREMENTS 4. 8.1.1. 2 f. 4 ) b), 4.8.1. L 2 f. 5 ), and 4.8.1.1.2. f.6) . This term (standby conditions) more accurately describes the candition in which the diesel generators are maintained and accounts for the jackei water and lube oil warning r.ystems which are continually in operation.
A
- 3. A land of " greater than or equal to 6083 kW" is replaced by a load range of *picater than or equal to 5600 LW and less than or equal to 6100 LW" in the f ollowing SURVEILLANCE REQUIREMENTS 4.8.1.1.2a 6) and 4.S.1.1.2L7) and to the note at the bottom of page 3/4 8 7. The lond range is provided to preclude routinely
, exceeding the continuous load rating of the diesel generator. Similarly, the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> load rating specified in SURVEILLANCE REQUIREMENT 4.8.L12f.7) is changed to a load range of " greater than or equal to 6300 kW and less than or equal to 6700 kW"
- 4. The- requirement of SURVEILLANCE R EQ U I R E M ENT 4.8.1.1.2a.6), to load the diesel generators "in less than or equal to 120 seconds
- is deleted. This test introduces mechanical stress and wear on the diesel engine and does not validate any operational requirement which is not already validated by performing other surveillances. l
- 5. The existing notes at the bottom of page 3/4 8 4 and 3/4 8-7 are being deleted for the following reasons;.1) the requirement to rapidly load the diesel generators has been deleted, 2} the note concerning diesel generator prelube has been relocated so that it applies to the entire SURVE!LLANCE REQUIREMENT and. 3) the diesel ;
j generators at Seabrook Station are not gradually accelerated to operating speed. A new note stating: " Diesel generator louding may be in accordance with manufacturers recommendations, including a warmup period. The load range is provided to preclude routine overloading of the diesel generator. Momentary transients outside the load
- range due changing bus conditions, do not invalidate the test." is being added, The information contained in the new note will provide the operator with additional information- concerning performance of the surveillance. These notes are applicable to SURVEILLANCE REQUIREM ENTS 4.8.1.1.2a.6) and 4.8.L t.2f.7),
The information in this note is also being added at the bottom of page 3/4 8 7. This will be in the form of a new note and revision to the existing note.
- 6. 'The requirement to verify diesel generator hot restart capability by performing a LOP /S1 test is replaced by a requirement to demonstrate hot restart capability by manually or automatically starting the diesel generator and verifying that rated voltage and . frequency are attained wit hin the required time. Specifically, " perform Specification 4.8.1.1.2f.6)b)" (the LOP /SI test) is replaced with " Verify that the diesel generator' starts on a manual or auto start signal,- attains generator voltage and frequency of 4160 + / 420 volts and 60 + /- 1.2 117 within 10 seconds and operates for at least 5 minutes"** The requirement to sequence on the LOP /SI loads does not contribute to verifying the ability of the diesel generator to start from normal 3
f
_ _ . _ a . _a _ ._______.-.._._.____.__.,.._._a__._
_.____._..m__.._.._. _ _ . . _ - - - -
operating temperatures. Demonstrating diesel generator hot restart capaleility without loading the engine with LOP /SI loads does not invalidate or reduce the ef fectiu ness of either t e r,t, provided normal operating temperatures are achiesed prior to demonstrating hot restart capability.
7, Since the LOP /S1 test will no longer be used to demonstra'e diesci gerirrator hot restatt capability, the note at the bottom of page 3!4 M is reworded to delete the reference to this test. Additionally, the sequirement to run the dicscl generator for i hout to achieve normal operating temperature is increased to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The latter requirement is more cona.tvative than the current 1 hout requirement and will continue to establish the required conditions to demonstrate diesel generator hot i restart capability. l i
j i
a f
t I
i l
i 4
. . _ - __ . . _ ._ _ _ _ - . . _ . _ _ _ _ _ _ . - . _ - _ _ _ _ _ _ . _ _ _ . . . . _ __u, . , _ , . . _ . _ - . _ -__,___-,...e__, . _ . ~