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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
. .
SEABROOK STATION UNIT 1 New Hampshire Yankee Facility Operating License'NPF-86 l Docket No.- 50-443 !
License Amendment Request No. 9105-Core Operating Limits Report This License Amendment Request is submitted by New Hampshire Yankee pursuant to 10 CFR50.90. The following information is enclosed in support of this License Amendment Request:
. Section 1 - Introduction and Description of Proposed Changes
. Section il - Markup of Proposed Ct anges
. Section lli - 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 Vil -
Other Supporting Dccumentation Sworn and Subscribed to before me this
, @ day of LLdw .1991. , /
// 8u 4W lumb Es #$O2rww Ted C. Felpdnbaum Notary 4ublic d President and Chipf Executive Officer Commission Expires: 2-28-95 9109100373 910904 PDR ADOCK 05000443 P PDR
71.- Introduction and Description of Proposed Chang _es i
A. Introduction
_ _ This License Amendment Request (91-05) proposes changes to the Seabrook Station-Technical Specifications implementing the guidence of NRC Generic Letter (GL) 88-16 " Removal of Cycle-Specific Parameter Limits from Technical Specifications".
Generic Letter 88-16, issued in October ~1988, provided-guidance f_or,_and " encouraged" licensees to pursue an alternative method to'the practice of specifying cycle-specific parameter limits-in Technical Specifications. The GL 88-16 alternative eliminates the necessity for the preparation and review of license amendments each refueling for the sole purpose of updating cycle-specific parameter limits. The NRC stated-in GL 88-16 that "If these limits are developed using an '
NRC-approved methodology, the license amendment process is an unnecessary burden on the licensee and the NRC". Generic Letter 88-16 specified threel actions to modify Technical Specifications:
"(1) the addition of the definition of a named formal report that includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safety analysis (2) Lthe addition of an administrative reporting requirement to submit the formal-report on cycle-specific parameter limits to the Commission
.for information, and (3) the modification of individual TS to note that cycle-specific parameters shall be maintained within the limits provided in the defined formal report."-
The above three actions specified in GL 88-16 are complied with by NHY in the proposed Technical Specification changes. A description of the proposed Technical Specification changes is provided below:
- 8. Description of Proposed Changes The proposed Technical Specification changes involve the relocation of several cycle-specific parameter limits from Technical Specifications to a new NHY report entitled the Core Operating Limits Report (COLR). A definition-for the COLR has been added to the Technical Specifications as definition 1.10. A-COLR paragraph has been added to the Administrative Controls Section 6.8.1.6 of the Technical-
, Specification replacing the Radial Peaking Factor Limits Report. The radial peaking factnr limits will be contained within the COLR.
Additionally, certain individual Technical' Specifications have been modified to state that the cycle-specific parameter limits are specified in the COLR. The initial-COLR and COLR revisions, will be provided to the NRC upon issuance, to allow continued trending.of the 1
cycle-specific parameters by the NRC. A draft COLR for Cycle 2 has been provided with this License Amendment Request, Section Vll.
Tte proposed Technical Specification changes will reference the COLR for certain cycle-specific parameter limits and will require that the cycle-specific parameters be maintained within the limits specified in the'COLR. The cycle-specific parameter limits relocated to the COLR
- in the proposed Technical Specification changes are:
-(a) 3.1.1.1 SHUTDOWN MARGIN for MODES 1, 2, 3 and 4
-(b) 3.1.1. 2_ SHUTDOWN MARGIN for MODE 5-(c) 3.1.1.3 Moderator Temperature Coefficient (d) 3.1.3.5 Shutdown Rod insertion Limits (e) 3.1.3.6 Control Rod Insertion Limits (f) 3.2.1 AXIAL FLUX DIFFERENCE (g) 3.2.2 Heat-Flux Hot Channel Factor (h) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor l The proposed changes are consistent with the requirements of 10 CFR 50.36 and the NRC Staff's proposed policy for improving Technical Specifications, delineated in SECY-86 10. " Recommendations for Improving TS." This policy allows process variables such as core operational limits to be-controlled _ by specifying them numerically in the Technical Specifications or by specifying the method for calculating their numerical values, if the Staff finds that theicorrect limits will be
.followed in _ operating the. plant. The proposed Technical Specification L Section 6.8.1.6 references- the NRC-approved calculation methodologies.
1 The development of cycle-specific parameter limits will continue to be performed by the referenced methodologies which have been accepted by the NRC. Prior NRC approval will be sought for the use of methodologies not _specified in proposed Technical Specification Section 6.8.1=.6.
The proposed changes to the Technical-Specifications are considered to be improvements and are consistent with the NRC stated policy for improving Technical Specifications (52 FR 3788, February 6,1987).
! C. Listing of Affected Technical' Specification Pages The Technical Specification pages that are revised by this License
' Amendment Request are provided in Section II as a-marked-up copy.
L Retyped pages incorporattng all of the proposed changes are provided in L Section Ill. Following is a listing of the revised pages and the l
changes made-on each page.
Paae Chanae i 'New definition 1.10 added for the COLR iii figures 3.1-1, 3.2-1 and 3.2-2 deleted xiv Radial Peaking Factor-Limits Report replaced by the CORE.
OPERATING LIMITS REPORT IJ2 Definition 1.10, CORE OPERATING LIMITS REPORT added. DOSE EQUIVALENT l-131 definition renumbered 1-3 All definitions renumbered 2
- t_
1 All definitions renumbered 1 All definitions renumbered 1-6 All definitions renumbered 17 All definitions renumbered 3/411 Specification 3.1.1.1 - The specific SHUTDOWN MARGIN was replaced by_the-reference to the COLR 3/4 1-3 Specification 3.1.1.2 - The specific SHUT 00WN MARGIN was replaced'by the reference to the COLR Specification 4.1.1.2 - The specific SHUTDOWN MARGIN was replaced by the reference to the COLR, and the sentence was reworded to accept the reference 3/4 1-4 Specification.3.1.1.3 - The specific MTC values were replaced by the reference to the COLR ACTION a. - The specific MTC value was replaced by a reference to the COLR ACTION a.1 - The specification 3.1.1.3a values were replaced by the reference to.the COLR ACTION ,b The Specification 3.1.1.3b reference was replaced:by a reference to the COLR 3/4.1-5 Specification 4.1.1.3a~-~The Specification 3.1.1.3a reference was replaced by a reference to the COLR, Specification 4.1.1.3b - The Specification 3.1.1.3b reference was replaced by a reference to the COLR, The specific MTC-values were replaced by reference to the COLR 3/4 1-8' ACTION - The specific SHUTDOWN MARGIN value was replaced-by a reference to the COLR o
i- 3/4'l-10 ACTION - Same as above b 3/41-12 ACTION a .Same as above 3/4 1-15 ACTION b.2, - The reference to Figure 3,1-1 was replaced by
- l. a reference to Specification 3.1.3.b i
L- 3/4_1-16 ACTION c.l. - Same as above 3/4--l-21 Specification 3.1.3.5 - The words "or specified in the CORE OPERATING LIMITS REPORT (COLR)" were added Spec'ification 4.1.3.5 - The words "as specified in the COLR" were added 3
- 3/4 1-22 Specification 3.1.3.6 - The reference to' Figure 3.1-1 was replaced by a reference to tne COLR ACTION Same as above ACTION b - Same as above 3/4:1-23 Figure 3.1-1 deleted and this page intentionally left blank 3/4 2-1 Specification 3.2.1 - The specific values for Axial Flux Difference (AFD) were replaced by a reference to the COLR.
The references to the specific AFD, values and to Figure 3.2-1 were replaced by references to the COLR ACTION -'The references to the specific AFD values and to Figure 3.2-1 were replaced by a reference to the COLR 3/4 2-1 ** - The reference to Figure 3.2-1 were replaced by a reference to:the COLR 3/4 2-2 '
Specification 3.2.lc - The reference to the specific AFD values was replaced with a reference to the COLR
- - Sarc.e as above 3/4 2-3 - Figure 3.2-1 was deleted and this page is intentionally left blank 3/4 2-4 Specification 3.2.2 - In the first equation, 2.32 was replaced with the term Fo*". In the second equation, 4.64 was replaced with the term Fg *"/.5. A definition for F"" a was added and the definition of K(Z) was revised to
, reference the COLR 3/4 2 Figure 3.2-2 was deleted and this page is intentionally left blank 3/4'2-6 Specification 4.2.2;2.c.2 - In the equation, 0.2 was .
replaced with PF,y, PF,y -was defined as_the power factor
. multiplier _ of F,7 specified in the COLR.
3/4 2-7 Specification 4.2.2.2.e - The reference to the Radial Peaking Factor limit Report was replaced by a reference to the COLR 3/4 2-8 and 0.2 was.
In the equation,1.49 replaced was replaced with Pfa. Defirittions with an of F""a F""bn PF, were also added.-
B 3/4 1-1 3/4.1.1 - The references to specific SHUTDOWN MARGIN were replaced by references to the COLR 4
t s
w . , '
3/4,1,1,3 - The references to specific MTC values viere !
replaced byl references to the COLR
~
1 B 3/4.1-2 3/4,1.2 - The reference to a specific SHUTDOWN MARGIN was-replaced by a reference to the COLR
' B.3/4 1-3 3/4.1 2 - Same as above B 3/4 2-1 3/4,2.1 - The value 2.32 was replaced by a reference to the Fn limit as specified in the COLR
- B 3/4 2-3 3/4.2.2 and 3/4.2.3 - The reference to the Radial Peaking Factor Limits Report was replaced with a reference to the COLR 6-18 6,8,1,6 - The . Radial Peaking Factor l'imits Report was replaced with the description of the COLR and the listing of NRC approved methodologies
- 6-18A Continuation of the COLR description 6-18B- Continuation of the COLR description 6-18C- Continuation of the COLRl description XXXX. These pages are overleaf pages that were not revised and are included to facilitate duplex duplication t
f 4
5
. .- . . - - - . . . . . - - - - . _ - - . . . . - . . - - - = . . . - . . ..-. .- ..-
~ II . . Markuo of Proposed Chanaes-
.See attached markup of proposed changes to Technical Specifications.
6 i-1
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