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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARBSEP-99-0126, Application for Amend to License DPR-71,revising TS 2.1.1.2 to Remove Note That Limits Use of MCPR Safety Limit Values to Cycle 12 Operation1999-09-28028 September 1999 Application for Amend to License DPR-71,revising TS 2.1.1.2 to Remove Note That Limits Use of MCPR Safety Limit Values to Cycle 12 Operation BSEP-98-0190, Application for Amends to Licenses DPR-62 & DPR-71,deleting Various License Conditions,Making Editorial Changes & Providing Clarifying Info1998-10-27027 October 1998 Application for Amends to Licenses DPR-62 & DPR-71,deleting Various License Conditions,Making Editorial Changes & Providing Clarifying Info BSEP-98-0165, Application for Amends to Licenses DPR-62 & DPR-71,revising TS 5.2.2.f to Require Operations Manager or Assistant Operations Manager to Hold SRO License1998-08-17017 August 1998 Application for Amends to Licenses DPR-62 & DPR-71,revising TS 5.2.2.f to Require Operations Manager or Assistant Operations Manager to Hold SRO License BSEP-98-0095, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-14331998-04-24024 April 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433 BSEP-98-0037, Application for Amends to Licenses DPR-62 & DPR-72,revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements1998-04-0909 April 1998 Application for Amends to Licenses DPR-62 & DPR-72,revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements BSEP-98-0049, Application for Amends to Licenses DPR-71 & DPR-82 to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,revising Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons1998-04-0303 April 1998 Application for Amends to Licenses DPR-71 & DPR-82 to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,revising Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons BSEP-98-0062, Suppl to Application for Amend to DPR-71,revising Safety Limit Min Critical Power Ratio Ref in TS 2.1.2 from 1.10 to 1.09 for Two Recirculation Loop Operation & to 1.10 for Single Recirculation Loop Operation for Fuel Cycle 121998-03-27027 March 1998 Suppl to Application for Amend to DPR-71,revising Safety Limit Min Critical Power Ratio Ref in TS 2.1.2 from 1.10 to 1.09 for Two Recirculation Loop Operation & to 1.10 for Single Recirculation Loop Operation for Fuel Cycle 12 BSEP-98-0056, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved TS as Contained in Rev 1 of NUREG-14331998-03-13013 March 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved TS as Contained in Rev 1 of NUREG-1433 BSEP-98-0036, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-14331998-02-26026 February 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433 BSEP-98-0034, Application for Amend to License DPR-71,revising SLMCPR Referenced in TS 2.1.2 from 1.10 to 1.09 & Deleting Document Referencd in TS 6.9.3.2.c.Proprietary & non-proprietary GE Info,Encl.Proprietary Info Withheld1998-02-23023 February 1998 Application for Amend to License DPR-71,revising SLMCPR Referenced in TS 2.1.2 from 1.10 to 1.09 & Deleting Document Referencd in TS 6.9.3.2.c.Proprietary & non-proprietary GE Info,Encl.Proprietary Info Withheld BSEP-97-0506, Suppls to 961101 Application for Amend to TS to Allow Full Implementation of BWROG Enhanced Option I-A Reactor Stability long-term Solution.Suppl Expands Note in LCO 3.3.1.1,Table 3.3.1-11997-12-18018 December 1997 Suppls to 961101 Application for Amend to TS to Allow Full Implementation of BWROG Enhanced Option I-A Reactor Stability long-term Solution.Suppl Expands Note in LCO 3.3.1.1,Table 3.3.1-1 BSEP-97-0475, Application for Amends to Licenses DPR-71 & DPR-62,adding Footnote to Surveillance Requirement (SR) 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 51997-11-0606 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,adding Footnote to Surveillance Requirement (SR) 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 5 BSEP-97-0454, Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time1997-11-0606 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time BSEP-97-0397, Application for Amends to Licenses DPR-71 & DPR-62,revising Proposed Terms in TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology,Per GL 87-091997-11-0404 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Proposed Terms in TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology,Per GL 87-09 BSEP-97-0458, Application for Amends to Licenses DPR-71 & DPR-62,revising Description of Control Rod Assemblies,Per Description Contained in NUREG-1433,Rev 11997-10-29029 October 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Description of Control Rod Assemblies,Per Description Contained in NUREG-1433,Rev 1 BSEP-97-0419, Application for Amends to Licenses DPR-71 & DPR-62,revising Certain Instrumentation Allowable Values,Per NUREG-1433,Rev 11997-10-28028 October 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Certain Instrumentation Allowable Values,Per NUREG-1433,Rev 1 BSEP-97-0445, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber1997-10-28028 October 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl1997-10-13013 October 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl BSEP-97-0359, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Labels for Coordinates of TS Figures 3.4.6.1-1, 3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F)1997-08-27027 August 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Labels for Coordinates of TS Figures 3.4.6.1-1, 3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F) BSEP-97-0319, Application for Amends to Licenses DPR-62 & DPR-71,approving Method of Transferring Spent Fuel Shipping Cask1997-08-0606 August 1997 Application for Amends to Licenses DPR-62 & DPR-71,approving Method of Transferring Spent Fuel Shipping Cask BSEP-97-0277, Application for Amends to Licenses DPR-62 & DPR-71, Clarifying TS 4.0.5.f Re Use of NRC Staff Approved Alternatives to Recommendations of GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping1997-07-25025 July 1997 Application for Amends to Licenses DPR-62 & DPR-71, Clarifying TS 4.0.5.f Re Use of NRC Staff Approved Alternatives to Recommendations of GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping BSEP-97-0315, Application for Amends to Licenses DPR-62 & DPR-71,revising Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features1997-07-18018 July 1997 Application for Amends to Licenses DPR-62 & DPR-71,revising Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features BSEP-96-0337, Application for Amends to Licenses DPR-62 & DPR-71,updating TS 3.6.1.6 to Support Upgrade to Containment Average Air Temp Limit Associated W/Conversion to Improved Tss.Encl Proprietary Rept & TSs Withheld1997-06-12012 June 1997 Application for Amends to Licenses DPR-62 & DPR-71,updating TS 3.6.1.6 to Support Upgrade to Containment Average Air Temp Limit Associated W/Conversion to Improved Tss.Encl Proprietary Rept & TSs Withheld BSEP-97-0222, Application for Amends to Licenses DPR-71 & DPR-62,revising Action Statements a.1 & a.2 of TS 3/4.4.5 by Reducing Max Allowed Reactor Coolant Specific to Activity1997-05-23023 May 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Action Statements a.1 & a.2 of TS 3/4.4.5 by Reducing Max Allowed Reactor Coolant Specific to Activity BSEP-97-0168, Application for Amends to Licenses DPR-71 & DPR-62,revising Surveillance Requirements to Require Testing of Control Room Emergency Ventilation Sys Charcoal & Revising Acceptance Criteria for Subject Charcoal Testing1997-04-30030 April 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Surveillance Requirements to Require Testing of Control Room Emergency Ventilation Sys Charcoal & Revising Acceptance Criteria for Subject Charcoal Testing BSEP-97-0144, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-091997-04-14014 April 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-09 BSEP-97-0135, Application for Amends to Licenses DPR-71 & DPR-62,revising Requirements for Instrumentation Response Time Testing Associated W/Rps,Isolation Actuation Sys & ECCS1997-04-11011 April 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Requirements for Instrumentation Response Time Testing Associated W/Rps,Isolation Actuation Sys & ECCS BSEP-97-0125, Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time1997-03-27027 March 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time BSEP-97-0120, Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time1997-03-24024 March 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time BSEP-97-0012, Application for Amends to Licenses DPR-71 & DPR-62 to Incorporate New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation1997-03-0505 March 1997 Application for Amends to Licenses DPR-71 & DPR-62 to Incorporate New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation BSEP-96-0447, Application for Amends to Licenses DPR-71 & DPR-62,revising Minimum & Maximum Values of Pressure Suppression Pool Water Vols Contained in TS 3.6.2.1.a.1 & Corresponding Bases1997-01-15015 January 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Minimum & Maximum Values of Pressure Suppression Pool Water Vols Contained in TS 3.6.2.1.a.1 & Corresponding Bases BSEP-96-0344, Application for Amends to Licenses DPR-62 & DPR-71,revising P-T Limits Curves Currently Located in Units 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test pressure-temp Limit Curves to Add New Ones1997-01-0707 January 1997 Application for Amends to Licenses DPR-62 & DPR-71,revising P-T Limits Curves Currently Located in Units 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test pressure-temp Limit Curves to Add New Ones BSEP-96-0343, Application for Amends to Licenses DPR-71 & DPR-62,changing Method of Detecting Reactivity Anomalies as Well as Editorial Changes to Bases for TS 3/4.1.21996-12-0404 December 1996 Application for Amends to Licenses DPR-71 & DPR-62,changing Method of Detecting Reactivity Anomalies as Well as Editorial Changes to Bases for TS 3/4.1.2 BSEP-96-0414, Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl1996-11-0101 November 1996 Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl BSEP-96-0406, Application for Amends to Licenses DPR-62 & DPR-71,allowing Full Implementation of BWROG Enhanced Option 1-A Reactor Stability Long Term Solution,Per GL 94-021996-11-0101 November 1996 Application for Amends to Licenses DPR-62 & DPR-71,allowing Full Implementation of BWROG Enhanced Option 1-A Reactor Stability Long Term Solution,Per GL 94-02 BSEP-96-0390, Application for Amend to License DPR-71,revising Minimum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core1996-10-16016 October 1996 Application for Amend to License DPR-71,revising Minimum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core BSEP-96-0271, Suppl to Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in TS 2.1.2 from 1.07 to 1.09 for Unit 1 Cycle 11 Operation & TS 5.3.1 to Reflect New Fuel Type GE131996-07-30030 July 1996 Suppl to Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in TS 2.1.2 from 1.07 to 1.09 for Unit 1 Cycle 11 Operation & TS 5.3.1 to Reflect New Fuel Type GE13 BSEP-96-0061, Application for Amend to License DPR-71,revising MCPR Safety Limits in TS 2.1.2 from 1.07 to 1.09 for Cycle 11 Operation & Revising TS 5.3.1 to Reflect New Fuel Type GE13 That Will Be Used During Refueling Outage 101996-04-0808 April 1996 Application for Amend to License DPR-71,revising MCPR Safety Limits in TS 2.1.2 from 1.07 to 1.09 for Cycle 11 Operation & Revising TS 5.3.1 to Reflect New Fuel Type GE13 That Will Be Used During Refueling Outage 10 BSEP-96-0126, Application for Amends to Licenses DPR-62 & DPR-71, Respectively,Revising TS 3.0 & 4.0 & Bases Re Applicability & Srs,Per Guidance in GL 87-09 & NUREG-14331996-04-0404 April 1996 Application for Amends to Licenses DPR-62 & DPR-71, Respectively,Revising TS 3.0 & 4.0 & Bases Re Applicability & Srs,Per Guidance in GL 87-09 & NUREG-1433 BSEP-96-0123, Application for Amends to Licenses DPR-62 & DPR-71,revising TS to Allow Uprate of Facilities to 105% of Rated Thermal Power.Proprietary & Nonproprietary Versions of GE Power Uprate SAR for Bsep... Encl.Proprietary GE Rept Withheld1996-04-0202 April 1996 Application for Amends to Licenses DPR-62 & DPR-71,revising TS to Allow Uprate of Facilities to 105% of Rated Thermal Power.Proprietary & Nonproprietary Versions of GE Power Uprate SAR for Bsep... Encl.Proprietary GE Rept Withheld BSEP-95-0561, Application for Amends to Licenses DPR-62 & DPR-71,modifying RPS Electrical Protective Assemblies Channel Functional Test Surveillance Interval in TS SR 4.8.2.5.a,per GL 91-091995-11-15015 November 1995 Application for Amends to Licenses DPR-62 & DPR-71,modifying RPS Electrical Protective Assemblies Channel Functional Test Surveillance Interval in TS SR 4.8.2.5.a,per GL 91-09 BSEP-95-0383, Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages1995-10-23023 October 1995 Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages BSEP-95-0316, Application for Amends to Licenses DPR-62 & DPR-71,proposing Changes to TS 3/4.6.1.2 & 3/4.6.1.3,by Removing Detailed Requirements Describing Type B & C Testing for PCIV & Penetrations1995-09-13013 September 1995 Application for Amends to Licenses DPR-62 & DPR-71,proposing Changes to TS 3/4.6.1.2 & 3/4.6.1.3,by Removing Detailed Requirements Describing Type B & C Testing for PCIV & Penetrations BSEP-95-0299, Requests Rev to Ts,Revising MCPR Limit,Ts 5.3.1 to Reflect New Fuel Type & Acceptable Range of Na Pentaborate Concentration for Standby Liquid Control Sys Shown in TS Figure 3.1.5-1 That Reflects Changes to Poison Matl1995-08-0404 August 1995 Requests Rev to Ts,Revising MCPR Limit,Ts 5.3.1 to Reflect New Fuel Type & Acceptable Range of Na Pentaborate Concentration for Standby Liquid Control Sys Shown in TS Figure 3.1.5-1 That Reflects Changes to Poison Matl BSEP-95-0153, Application for Amends to Licenses DPR-71 & DPR-62,adding Exemption from Requirements of TS 3.0.4 to Spec 3/4.8.1.11995-03-31031 March 1995 Application for Amends to Licenses DPR-71 & DPR-62,adding Exemption from Requirements of TS 3.0.4 to Spec 3/4.8.1.1 BSEP-95-0539, Application for Amend to Licenses DPR-71 & DPR-62,providing Clarification to Basis for Deletion of Instrumentation Surveillances from TS 3/4.6.2 on Suppression Chamber1995-02-14014 February 1995 Application for Amend to Licenses DPR-71 & DPR-62,providing Clarification to Basis for Deletion of Instrumentation Surveillances from TS 3/4.6.2 on Suppression Chamber BSEP-94-0469, Application for Amends to Licenses DPR-62 & DPR-71,removing Specific Instrumentation Requirements for Suppression Chamber Water Temp Monitoring from TS 3/4.6.2,on Suppression Chamber1994-11-16016 November 1994 Application for Amends to Licenses DPR-62 & DPR-71,removing Specific Instrumentation Requirements for Suppression Chamber Water Temp Monitoring from TS 3/4.6.2,on Suppression Chamber BSEP-94-0401, Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.6.1.2 by Adopting Wording for Primary Containment Integrated Leak Rate Testing Consistent W/Requirements of BWR-4 Improved STS (NUREG-1433)1994-11-16016 November 1994 Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.6.1.2 by Adopting Wording for Primary Containment Integrated Leak Rate Testing Consistent W/Requirements of BWR-4 Improved STS (NUREG-1433) BSEP-94-0413, Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times1994-10-28028 October 1994 Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times BSEP-94-0386, Application for Amends to Licenses DPR-71 & DPR-62,deleting Remaining Ets,Including Section 2/3.3.1,water Level in Discharge Canal & Section 2/3.4,meteorology1994-10-25025 October 1994 Application for Amends to Licenses DPR-71 & DPR-62,deleting Remaining Ets,Including Section 2/3.3.1,water Level in Discharge Canal & Section 2/3.4,meteorology 1999-09-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARBSEP-99-0126, Application for Amend to License DPR-71,revising TS 2.1.1.2 to Remove Note That Limits Use of MCPR Safety Limit Values to Cycle 12 Operation1999-09-28028 September 1999 Application for Amend to License DPR-71,revising TS 2.1.1.2 to Remove Note That Limits Use of MCPR Safety Limit Values to Cycle 12 Operation BSEP-98-0190, Application for Amends to Licenses DPR-62 & DPR-71,deleting Various License Conditions,Making Editorial Changes & Providing Clarifying Info1998-10-27027 October 1998 Application for Amends to Licenses DPR-62 & DPR-71,deleting Various License Conditions,Making Editorial Changes & Providing Clarifying Info BSEP-98-0165, Application for Amends to Licenses DPR-62 & DPR-71,revising TS 5.2.2.f to Require Operations Manager or Assistant Operations Manager to Hold SRO License1998-08-17017 August 1998 Application for Amends to Licenses DPR-62 & DPR-71,revising TS 5.2.2.f to Require Operations Manager or Assistant Operations Manager to Hold SRO License BSEP-98-0095, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-14331998-04-24024 April 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433 BSEP-98-0037, Application for Amends to Licenses DPR-62 & DPR-72,revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements1998-04-0909 April 1998 Application for Amends to Licenses DPR-62 & DPR-72,revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements BSEP-98-0049, Application for Amends to Licenses DPR-71 & DPR-82 to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,revising Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons1998-04-0303 April 1998 Application for Amends to Licenses DPR-71 & DPR-82 to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,revising Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons BSEP-98-0062, Suppl to Application for Amend to DPR-71,revising Safety Limit Min Critical Power Ratio Ref in TS 2.1.2 from 1.10 to 1.09 for Two Recirculation Loop Operation & to 1.10 for Single Recirculation Loop Operation for Fuel Cycle 121998-03-27027 March 1998 Suppl to Application for Amend to DPR-71,revising Safety Limit Min Critical Power Ratio Ref in TS 2.1.2 from 1.10 to 1.09 for Two Recirculation Loop Operation & to 1.10 for Single Recirculation Loop Operation for Fuel Cycle 12 BSEP-98-0056, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved TS as Contained in Rev 1 of NUREG-14331998-03-13013 March 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved TS as Contained in Rev 1 of NUREG-1433 BSEP-98-0036, Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-14331998-02-26026 February 1998 Suppl Application for Amends to Licenses DPR-62 & DPR-71, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433 BSEP-98-0034, Application for Amend to License DPR-71,revising SLMCPR Referenced in TS 2.1.2 from 1.10 to 1.09 & Deleting Document Referencd in TS 6.9.3.2.c.Proprietary & non-proprietary GE Info,Encl.Proprietary Info Withheld1998-02-23023 February 1998 Application for Amend to License DPR-71,revising SLMCPR Referenced in TS 2.1.2 from 1.10 to 1.09 & Deleting Document Referencd in TS 6.9.3.2.c.Proprietary & non-proprietary GE Info,Encl.Proprietary Info Withheld BSEP-97-0506, Suppls to 961101 Application for Amend to TS to Allow Full Implementation of BWROG Enhanced Option I-A Reactor Stability long-term Solution.Suppl Expands Note in LCO 3.3.1.1,Table 3.3.1-11997-12-18018 December 1997 Suppls to 961101 Application for Amend to TS to Allow Full Implementation of BWROG Enhanced Option I-A Reactor Stability long-term Solution.Suppl Expands Note in LCO 3.3.1.1,Table 3.3.1-1 BSEP-97-0454, Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time1997-11-0606 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation,For Limited Period of Time BSEP-97-0475, Application for Amends to Licenses DPR-71 & DPR-62,adding Footnote to Surveillance Requirement (SR) 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 51997-11-0606 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,adding Footnote to Surveillance Requirement (SR) 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 5 BSEP-97-0397, Application for Amends to Licenses DPR-71 & DPR-62,revising Proposed Terms in TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology,Per GL 87-091997-11-0404 November 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Proposed Terms in TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology,Per GL 87-09 BSEP-97-0458, Application for Amends to Licenses DPR-71 & DPR-62,revising Description of Control Rod Assemblies,Per Description Contained in NUREG-1433,Rev 11997-10-29029 October 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Description of Control Rod Assemblies,Per Description Contained in NUREG-1433,Rev 1 BSEP-97-0445, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber1997-10-28028 October 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber BSEP-97-0419, Application for Amends to Licenses DPR-71 & DPR-62,revising Certain Instrumentation Allowable Values,Per NUREG-1433,Rev 11997-10-28028 October 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Certain Instrumentation Allowable Values,Per NUREG-1433,Rev 1 BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl1997-10-13013 October 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl BSEP-97-0359, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Labels for Coordinates of TS Figures 3.4.6.1-1, 3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F)1997-08-27027 August 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Labels for Coordinates of TS Figures 3.4.6.1-1, 3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F) BSEP-97-0319, Application for Amends to Licenses DPR-62 & DPR-71,approving Method of Transferring Spent Fuel Shipping Cask1997-08-0606 August 1997 Application for Amends to Licenses DPR-62 & DPR-71,approving Method of Transferring Spent Fuel Shipping Cask BSEP-97-0277, Application for Amends to Licenses DPR-62 & DPR-71, Clarifying TS 4.0.5.f Re Use of NRC Staff Approved Alternatives to Recommendations of GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping1997-07-25025 July 1997 Application for Amends to Licenses DPR-62 & DPR-71, Clarifying TS 4.0.5.f Re Use of NRC Staff Approved Alternatives to Recommendations of GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping BSEP-97-0315, Application for Amends to Licenses DPR-62 & DPR-71,revising Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features1997-07-18018 July 1997 Application for Amends to Licenses DPR-62 & DPR-71,revising Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features BSEP-96-0337, Application for Amends to Licenses DPR-62 & DPR-71,updating TS 3.6.1.6 to Support Upgrade to Containment Average Air Temp Limit Associated W/Conversion to Improved Tss.Encl Proprietary Rept & TSs Withheld1997-06-12012 June 1997 Application for Amends to Licenses DPR-62 & DPR-71,updating TS 3.6.1.6 to Support Upgrade to Containment Average Air Temp Limit Associated W/Conversion to Improved Tss.Encl Proprietary Rept & TSs Withheld BSEP-97-0222, Application for Amends to Licenses DPR-71 & DPR-62,revising Action Statements a.1 & a.2 of TS 3/4.4.5 by Reducing Max Allowed Reactor Coolant Specific to Activity1997-05-23023 May 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Action Statements a.1 & a.2 of TS 3/4.4.5 by Reducing Max Allowed Reactor Coolant Specific to Activity BSEP-97-0168, Application for Amends to Licenses DPR-71 & DPR-62,revising Surveillance Requirements to Require Testing of Control Room Emergency Ventilation Sys Charcoal & Revising Acceptance Criteria for Subject Charcoal Testing1997-04-30030 April 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Surveillance Requirements to Require Testing of Control Room Emergency Ventilation Sys Charcoal & Revising Acceptance Criteria for Subject Charcoal Testing BSEP-97-0144, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-091997-04-14014 April 1997 Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Revising Tech Specs 3.0 & 4.0 & Respective Bases for Sections to Incorporate Guidance Contained in NRC GL 87-09 BSEP-97-0135, Application for Amends to Licenses DPR-71 & DPR-62,revising Requirements for Instrumentation Response Time Testing Associated W/Rps,Isolation Actuation Sys & ECCS1997-04-11011 April 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Requirements for Instrumentation Response Time Testing Associated W/Rps,Isolation Actuation Sys & ECCS BSEP-97-0125, Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time1997-03-27027 March 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time BSEP-97-0120, Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time1997-03-24024 March 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Definitions for ECCS Response Time,Isolation Sys Response Time & Reactor Protection Sys Response Time BSEP-97-0012, Application for Amends to Licenses DPR-71 & DPR-62 to Incorporate New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation1997-03-0505 March 1997 Application for Amends to Licenses DPR-71 & DPR-62 to Incorporate New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation BSEP-96-0447, Application for Amends to Licenses DPR-71 & DPR-62,revising Minimum & Maximum Values of Pressure Suppression Pool Water Vols Contained in TS 3.6.2.1.a.1 & Corresponding Bases1997-01-15015 January 1997 Application for Amends to Licenses DPR-71 & DPR-62,revising Minimum & Maximum Values of Pressure Suppression Pool Water Vols Contained in TS 3.6.2.1.a.1 & Corresponding Bases BSEP-96-0344, Application for Amends to Licenses DPR-62 & DPR-71,revising P-T Limits Curves Currently Located in Units 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test pressure-temp Limit Curves to Add New Ones1997-01-0707 January 1997 Application for Amends to Licenses DPR-62 & DPR-71,revising P-T Limits Curves Currently Located in Units 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test pressure-temp Limit Curves to Add New Ones BSEP-96-0343, Application for Amends to Licenses DPR-71 & DPR-62,changing Method of Detecting Reactivity Anomalies as Well as Editorial Changes to Bases for TS 3/4.1.21996-12-0404 December 1996 Application for Amends to Licenses DPR-71 & DPR-62,changing Method of Detecting Reactivity Anomalies as Well as Editorial Changes to Bases for TS 3/4.1.2 BSEP-96-0414, Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl1996-11-0101 November 1996 Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl BSEP-96-0406, Application for Amends to Licenses DPR-62 & DPR-71,allowing Full Implementation of BWROG Enhanced Option 1-A Reactor Stability Long Term Solution,Per GL 94-021996-11-0101 November 1996 Application for Amends to Licenses DPR-62 & DPR-71,allowing Full Implementation of BWROG Enhanced Option 1-A Reactor Stability Long Term Solution,Per GL 94-02 BSEP-96-0390, Application for Amend to License DPR-71,revising Minimum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core1996-10-16016 October 1996 Application for Amend to License DPR-71,revising Minimum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core BSEP-96-0271, Suppl to Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in TS 2.1.2 from 1.07 to 1.09 for Unit 1 Cycle 11 Operation & TS 5.3.1 to Reflect New Fuel Type GE131996-07-30030 July 1996 Suppl to Application for Amend to License DPR-71,revising MCPR Safety Limit Specified in TS 2.1.2 from 1.07 to 1.09 for Unit 1 Cycle 11 Operation & TS 5.3.1 to Reflect New Fuel Type GE13 BSEP-96-0061, Application for Amend to License DPR-71,revising MCPR Safety Limits in TS 2.1.2 from 1.07 to 1.09 for Cycle 11 Operation & Revising TS 5.3.1 to Reflect New Fuel Type GE13 That Will Be Used During Refueling Outage 101996-04-0808 April 1996 Application for Amend to License DPR-71,revising MCPR Safety Limits in TS 2.1.2 from 1.07 to 1.09 for Cycle 11 Operation & Revising TS 5.3.1 to Reflect New Fuel Type GE13 That Will Be Used During Refueling Outage 10 BSEP-96-0126, Application for Amends to Licenses DPR-62 & DPR-71, Respectively,Revising TS 3.0 & 4.0 & Bases Re Applicability & Srs,Per Guidance in GL 87-09 & NUREG-14331996-04-0404 April 1996 Application for Amends to Licenses DPR-62 & DPR-71, Respectively,Revising TS 3.0 & 4.0 & Bases Re Applicability & Srs,Per Guidance in GL 87-09 & NUREG-1433 BSEP-96-0123, Application for Amends to Licenses DPR-62 & DPR-71,revising TS to Allow Uprate of Facilities to 105% of Rated Thermal Power.Proprietary & Nonproprietary Versions of GE Power Uprate SAR for Bsep... Encl.Proprietary GE Rept Withheld1996-04-0202 April 1996 Application for Amends to Licenses DPR-62 & DPR-71,revising TS to Allow Uprate of Facilities to 105% of Rated Thermal Power.Proprietary & Nonproprietary Versions of GE Power Uprate SAR for Bsep... Encl.Proprietary GE Rept Withheld BSEP-95-0561, Application for Amends to Licenses DPR-62 & DPR-71,modifying RPS Electrical Protective Assemblies Channel Functional Test Surveillance Interval in TS SR 4.8.2.5.a,per GL 91-091995-11-15015 November 1995 Application for Amends to Licenses DPR-62 & DPR-71,modifying RPS Electrical Protective Assemblies Channel Functional Test Surveillance Interval in TS SR 4.8.2.5.a,per GL 91-09 BSEP-95-0383, Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages1995-10-23023 October 1995 Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages BSEP-95-0316, Application for Amends to Licenses DPR-62 & DPR-71,proposing Changes to TS 3/4.6.1.2 & 3/4.6.1.3,by Removing Detailed Requirements Describing Type B & C Testing for PCIV & Penetrations1995-09-13013 September 1995 Application for Amends to Licenses DPR-62 & DPR-71,proposing Changes to TS 3/4.6.1.2 & 3/4.6.1.3,by Removing Detailed Requirements Describing Type B & C Testing for PCIV & Penetrations BSEP-95-0299, Requests Rev to Ts,Revising MCPR Limit,Ts 5.3.1 to Reflect New Fuel Type & Acceptable Range of Na Pentaborate Concentration for Standby Liquid Control Sys Shown in TS Figure 3.1.5-1 That Reflects Changes to Poison Matl1995-08-0404 August 1995 Requests Rev to Ts,Revising MCPR Limit,Ts 5.3.1 to Reflect New Fuel Type & Acceptable Range of Na Pentaborate Concentration for Standby Liquid Control Sys Shown in TS Figure 3.1.5-1 That Reflects Changes to Poison Matl BSEP-95-0153, Application for Amends to Licenses DPR-71 & DPR-62,adding Exemption from Requirements of TS 3.0.4 to Spec 3/4.8.1.11995-03-31031 March 1995 Application for Amends to Licenses DPR-71 & DPR-62,adding Exemption from Requirements of TS 3.0.4 to Spec 3/4.8.1.1 BSEP-95-0539, Application for Amend to Licenses DPR-71 & DPR-62,providing Clarification to Basis for Deletion of Instrumentation Surveillances from TS 3/4.6.2 on Suppression Chamber1995-02-14014 February 1995 Application for Amend to Licenses DPR-71 & DPR-62,providing Clarification to Basis for Deletion of Instrumentation Surveillances from TS 3/4.6.2 on Suppression Chamber BSEP-94-0401, Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.6.1.2 by Adopting Wording for Primary Containment Integrated Leak Rate Testing Consistent W/Requirements of BWR-4 Improved STS (NUREG-1433)1994-11-16016 November 1994 Application for Amends to Licenses DPR-62 & DPR-71,revising TS 3/4.6.1.2 by Adopting Wording for Primary Containment Integrated Leak Rate Testing Consistent W/Requirements of BWR-4 Improved STS (NUREG-1433) BSEP-94-0469, Application for Amends to Licenses DPR-62 & DPR-71,removing Specific Instrumentation Requirements for Suppression Chamber Water Temp Monitoring from TS 3/4.6.2,on Suppression Chamber1994-11-16016 November 1994 Application for Amends to Licenses DPR-62 & DPR-71,removing Specific Instrumentation Requirements for Suppression Chamber Water Temp Monitoring from TS 3/4.6.2,on Suppression Chamber BSEP-94-0413, Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times1994-10-28028 October 1994 Application for Amends to Licenses DPR-62 & DPR-71,proposing Ts,Increasing Instrument Surveillance Test Intervals & Allowable out-of-service Times BSEP-94-0386, Application for Amends to Licenses DPR-71 & DPR-62,deleting Remaining Ets,Including Section 2/3.3.1,water Level in Discharge Canal & Section 2/3.4,meteorology1994-10-25025 October 1994 Application for Amends to Licenses DPR-71 & DPR-62,deleting Remaining Ets,Including Section 2/3.3.1,water Level in Discharge Canal & Section 2/3.4,meteorology 1999-09-28
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Carolina Power & Light Company >
P.0, Box 1561 e Reieigh, N C. 27002 ' -\
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SERIAL:- .NLS 90 197 -;
-10CFR50.90 - !
G. E. VAUGHN Vice President Nuclear servicoe Department H
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-i United States Nuclear Regulatory Commission !
ATTENTION: Document Control Desk Washington, DC 20555-BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 -
DOCKET NOS. 50 325 & 50-324/ LICENSE NOS. DPR-71 &-DPR 62 '
REQUEST FOR LICENSE AMENDMENT.
NUCLEAR ASSESSMENT DEPARTMENT ORGANIZATION CHANGES Gentlemen: ,
.In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and.
2.101, Carolina Power & Light Company-(CP&L) hereby requests a revision to the Technical Specifications for the -Brunswick Steam Electric Plant (BSEP) . The proposed change revises Section 6.0, " Administrative Controls,"'of the '
' Technical Specifications to reflect changes'in the organizational structure of-g CP&L.
1 Carolina Power & Light Company (CP&L) has created a Nuclear Assessment Department (NAD) which'will perform internali evaluation'and assessment i activities and will serve as senior management's staff for the objective oversight of. Nuclear Generation Group performance relating to nuclear safety, reliability,-and quality. The department's fundamental. role is to assist senior management-in the early identification' fo those1 barriers which may -
prevent the Company's nuclear projects from achieving the- desired level of i performance on a sustained _ basis and in: ensuring their effective correction.
The NAD will assume the-functions'and responsibilities for (1) administering the Company's independent review program for nuclear-facilities which is currently-provided by the Corporate Nuclear Safety Section (CNSS); and (2) the audit of unit activity currently provided by the Quality-Assurance' Services Section of the Corporate Quality Assurance Department.
Creation of the Nuclear Assessment Department requires that'the Technical
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Specifications be modified to reflect changes in the organizational-structure '
of CP&L. Accordingly, titles of positions and organizations referenced in the Technical Specifications must be changed to reflect this organizational-change.
9101230333 910115 A POR ADOCK 05000324 {
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- i. Document Control Desk NLS 90 197-/ Page 2 i
Enclosure 1 provides a detailed descriptionJof the proposed' changes and the= 6 basis for the changes.-
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Enclosure -2. details t.he basis for .the Company's -determintA'on that the proposed changes do not involve'a significant: hazards consideration. g 1
Enclosure 3 details the.' basis-for the Company's dotermination that the 'l proposed changes- require no environmentalf assessment. .?
':1 Enclosures-4 and 5 providoithe proposed. Technical Specification pages!for each !
unit. 1 In order to allow time' for- procedure revisionf andfordehly ' incorporation;into copies of the Technical Specifications CP&L requests thattthe. proposed:
amendments.-once approved by:the NRC, be-issued with an effective date to be- {
no later than 60 days from the issuance 'of;the -amenctment. l Please refer
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.y quea.i ms regarding;this submittaltto,Mr. M..R. Oates-at j (919) 546 6063. ;
fYoursLvery truly, ;
/
- }
C. E 'Vaughn i
JCP/ecc (824BNP)
Enclosures:
- t
- 1. Basis for Change Request
- 2. 100FR50.92 Evaluation-
- 3. Environmental Considoration >
- 4. Unit 1' Technical Specification Pages- I
- 5. ~ Unit 2 Technical Specification Pages j l
I cc: Mr. Dayne H. Brown. :!
Mr. S. D.. Ebneter j Mr. N.-B. Le Mr. R. L. Prevatte -
C. E. Vaughn, having been first duly sworn, did depose andcsayLthat the infor.
-mation contained herein is true 'and' correct to theibest of his informationt knowledge and belief; and the sources:of his information are officers, employees, contractors,.and age'nts of Carolina Power 6 Light Company. .
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j ENCihSURE1 BRUNSWICK STEAM ELECTRIC ~ PLANT, UNITS-1.AND 2- d NRC' DOCKETS 50 325 & 50 324:
-OPERATINC LICENSESJDPR 71 & DPR 62- _[
REQUEST FOR LICENSE AMENDMENT. _. ((
NUCLEAR ASSESSMLNT DEPARTMENT,ORCANIZATION' CHANGES 1 BASIS FOR-CHANCE REQUEST- j Prooosed Chances:- ,
Creation of the-Nuclear Assessment Department (NAD)1 requires:that the j Technical-Specifications be modified.to reflectfchanges;in the-. organizational 4 structure,: Accordingly,4 titles of-positions?and organizations referenced in. y the Technical Specifications must; be changed tol reflect this -organizational t A change. 'The proposed change modifies the following; sections of the-Technical a Specifications as. indicated:- f Section 6.2 I d
q
-6.2.3 Revised to reflect that ~ thel Project Assessme_nt -(PA) Group of_ tho ' ,9 Nuclear Assessment Department (NAD) shall; assume the functions, .
responsibilities and authority currently described;in-_this-section-for 3 the Onsite Nuclear Safety---(ONS) unit of the Nuclear Services: Department. 3 3
-Section 6.5 -!
6.5.2.-9 Revised to specify that~in'accordance. with !
Specification 6.5.4,9 the NAD rather than' the. Corporate Nuclear Safety. }
Section (CNSS) shall review. safety' evaluations prepared in1accordance: 1 with 6.5.2.1.d and 6.5.2.1.o.-
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- , 6. 5. 3,8. Revised to specify that the Manager - NAD rather than thel Ei l Manager - CNSS'be.'n
- recipient of reports covering evaluationsjand' L recommendations to prevent recurrence offviolation Lof; Technical :
Specifications. Revised.to authorize the Manager 1.NAD;rather than'the--
f- Manager - CNSS to' request the: Plant-Nuclear l Safety CommitteeT(PNSC).to: '
- - perform special reviews, investigationsL(or? analyses)~and; reports.1 ,
Revised to require forwarding:of PNSC. reports covering evaluation ~,- y recommendations and' disposition _of corrective action:to prevent:
recurrence-of accidental', unplanned-orl uncontrolled radioactive releases to the' Manager - NAD rather than:the Manager :CNSS. ,
L 6.5,3.9 Revised to specify that the~-Manager NAD rather_than the Vice .;
President Nuclear Service'sthe the recipient of.thes24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written; -
i notification of .a disagreement between recommendations ofia majority -ofl the PNSC and the actions contemplated by the1 General _ Manager - Brunswick-Plant. ,
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6.5.3.10 Revised to require submittal of copies of v.*itten PNSC meeting minutes to the Manager NAD rather than the Manager CNSS.
6.5.4 Revised to reassign to the NAD rather than the (NSS responsibility for administering the independent review program described in this section. Revised to define the qualifications for the Manager NAD rather than the Manager - CNSS. Revised to address documentation, distribution and summation of NAD reviews, recommendations, and concerns rather than those of the-CNSS.
6.5.5 Revised to reassign to the NAD rather than the Quality Assurance Auditing Unit, responsibility for performing audits of facility activities described in Technical Specification 6.5.5.2. Revised to authorize-the Manager - NAD rather than the Manager - Quality Assurance Services Section, responsibility for administering the NAD audit program and approving individuals selected to conduct audits. Also , revises distribution of audit reports to delete Vice -President Nuclear Services due_to this function being reassigned to NAD.
Section 6.6 6.6.1 Revised to specify that the Manager - NAD rather than the Manager - CNSS be a recipient of REPORTABLE EVENT reports.
Section 6.7 6.7.1 Revised to specify that the Manager - NAD rather than the Manager - CNSS shall be notified in the-event a Safety Limit is violated. Revised to specify that the Manager - NAD rather than the -
Manager - CNS shall be a recipient of Safety Limit violation reports.
Section 6.10-6.10.2 Revised to require that records of independent review performed by the NAD shall be retained for the duration of the facility operating license.
Basis The content required in the Administrative Controls Section of the Technical Specifications is specified in 10 CFR 50.36c(5). The regulation requires that the Technical Specifications contain the controls and provisions that are necessary to assure operation of the facility in a safe manner.
Creation of the Nuclear Assessment Department (NAD) requires that the Technical Specifications'be modified to reflect changes in the organizational structure. Accordingly, titles of positions and organizations referenced in the Technical Specificatiors must be changed to reflect this organizational change.
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The independent review function currently provided by the-Corporate Nuclear Safety Section (CNSS) as outlined 11n theiTechnical Specifications, will not- be_- -
altered.by the. change. 'Rather the proposed' change' will merely reflect a
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reporting realignment-of the individuals and organizations currentlysproviding the independent review function. Similarly,;.the audit of unit activity; _
function currently,provided by-the Quality Assurance Auditing Unit of-..the Corporate; Quality Assurancc~ Department will.not-be altered by the' change;-but-will-reflect a reporting realignment of_theiindividuals'and organizations ;
currently providing the audit-function, Consistent with current;and previous record retention _ requirements,_recordsiof Nuclear Assessment Department' reviews and Nuclear _ Assessment, Department: audits- +
will be retained as life time records:of the plant.
In accordance with Specification _6.2.la,flines of_ authority,; responsibility,.
and communication will be documented and provided in the next: annual. update of' the Final Safety Analysis Report'(FSAR) as required by:105CFRl50.71(c).--
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ENCLOSURE 2 i
BRUNSWICK STEAM ELECTRIC-PLANT, UNITS 1 AND 2: ~
-NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES'DPR 71 & DPR 62' REQUEST FOR LICENSE AMENDMENT' NUCLEAR-ASSESSMENT-DEPARTMENT ~ ORGANIZATION CHANCES-
-10 CFR 50.92 EVALUATION.
TheCommissionhasprovidedstandards'in10fCFR50'92'(chfordetermining whether.a significant hazards consideration exists. iA~ proposed: amendment to-an operating. license.for.a facility involves no significant: hazards-consideration if operatAon of the facility in-accordance_with the proposed-amendment would not: -(1) involve a'significant increase in the probability or ;
consequences of'an accident previously evaluated,1(2) create the possibility -!
of a new or different kind of-accidentffrom any accident previously~ evaluated, '
or (3) involve a significant reduction :in: a' mar 6 n :of 1 _ safety.1- - Carolina 1 Power & Light Company has reviewed this" proposed, license-_ amendment. request and
- determined that its adoption would not involve a' significant" hazards consideration , The bases for this'detecmination are as:follows:-
-Pronosed Chance *-
Creation of the-Nuclear Assessment Department (NAD)? requires:that the-
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p Technical Specifications be modified to yoflect changes'in the organizational structure. Accordingly,= titles.of'positionstand' organizations referenced in-the Technical Specifications ~mustLbe changed to reflectethis' organizational d change.- ]
)
Basis 4
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The change does.not involve a-significant' hazards consideration for the' i following' reasons:
- 1. The proposed amendment does not involvo a.significant increase in the probability'or consequences of an_ accident previously evaluated:because .
it is administrative in nature and.does not physically alter _ any safety- ' l" related systems nor does'it affect the'way in which any safety related systems: perform their' functions. The revisions:to.Section 6,0-of the ;
Technical Specifications reflect changes 11n the organizational. reporting' ;
structure of CP&L due to the creation of the. Nuclear Assessment 1 Department (NAD). The proposed change is administrative in nature in 1 that the changes reflect organizational reporting changesirather than changes Lin the nature or depth of reviewsuand : audits; recommendations ,
for procedures, modifications, maintenance and operations. activities; or other means.of affecting unit safety. . The independent review'functioni currently provided by"the Corporate Nuclear'3afety Section-(CNSS)'as !
outlined-in the Specifications, will not be altered by the change.
Rather the proposed change will merely reflect'a reporting realignment ;
of the individuals and; organizations currently providing the independent '
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review function. Similarly,- the audit of unit activity function '
currently provided by the Quality Assurance Auditing Unit of the Corporate Quality Assurance Department will not be altered by the change, but will reflect a reporting realignment of the individuals and organizations currently providing the audit function. The other revisions to titles and' organizations in the proposed change solely revise the Technical Specifications to reflect the revised organizational structure of the company,
- 2. The proposed amendment does not create the possibility of a new or
- different kind of accident from any accident previously evaluated. As j stated in Item 1, the proposed change is. administrative in nature and does not physically alter any safety related systems, nor does it a ffect j the way in which any safety related systems perform their function-e.
Therefore, the proposed amendment does not create the passibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed amendment does not-involve a significant reduction in the margin of safety. The proposed change in-administrative in nature and does not physically alter any safety related systems nor does it affect the way in which any safety related systems perform their functions. As a result of the change, the Brunswick Technical Specifications.will better reflect the actual-management structure at both the Brunswick
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Planc and the Corporate Office, Therefore, the proposed amendment does-not involve a significant reduction in margin of safety.
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l ENCIDSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 i NRC DOCKETS 50 325~& 50-324-REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT ORGANIZATION CHANGES ENVIRONMENTAL CONSIDERATION 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an- 1 environmental assessment. A proposed _ amendment to an operating license for_a '
facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of atj effluents that_may be released offsite; and (3) result in an increase in an individual or cumulative occupational radiation exposure. Carolina Power & Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. This basis for this determination follows:
Pronosed Chance Carolina Power & Light Company (CP&L) has created a Nuclear Assessment -
' Department (NAD) which will perform internal evaluation and assessment-activities and will serve as senior management's staff for the objective oversight of Nucicar Generation Group performance relating to r.uclear safety, reliability, and quality. The department's fundamental role _-is to assist senior management in the early identification of those barriors Yhich may prevent the Company's nuclear projects from achieving the desired level of performan.:e en a sustained basis and in ensuring their effective correction.
The NAD will assuue the functions and respcasibilities for- (1) idministering the Company's independent review program for nuclear facilities which is currently provided by the Corporate Nuclear Safety Section (CNSS); and (2) the audit of unit activity currently provided by the Quality Assurante Services
-Section of the Corporate Quality Annurance Department.
Creation of the Nuclear Assessment Department requires that the Technical Speci.fications be modified to reflect changes in the organizational structure of CP&L. Accordingly, titles of positions and organizations referenced in the Technten1 Specifications must be changed to reflect this or6anizational change.
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Basis This change meets the eligibility criteria for categorical exclusion set forth- j in 10 CFR 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Enclosure 2, the proposed amendment does not=involveL a significant hazards consideration, l
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- 2. The proposed amendment does not resultsin a significant change in'the types or significant increase in=the amounts of-any; effluents that may be released offsite. c]i i
The proposed change is-purely administrative in nature:and-only revises Section 6 " Administrative Controls",of the Technical Specifications to i
reflect changes in the organizational: reporting structure'of.CP&L
-- due to ;
the creation of the NAD. The proposed amendment does'notcintroduce any ?,
new equipment nor does it_ require-any; existing-equipment or. systems to j perform a different type of= function than-they are currently designed to .j perform. As such, the-change cannot affect the' types or amounts of any '
effluents that may be released offsite. !
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- 3. The proposed amendment does-not result-in an increase in' individual'or- l cumulative occupational radiation exposure.- The proposed change is purely-administrative in nature and .only-revises--Section16
" Administrative Controls" of the Technical Specifications to: reflect changes in the organizational reporting structure of CP6L due'to the
- creation of the NAD. LNo additional surveillances or testingf results 5
from the amendment. Therefore, L the amendment has no~ affect cn) either individual or cumulative occupational radiation exposure.
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