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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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Carouna Power & Light Company P.o. Box 1551. Raleigh, N.C. 27600 f
APR 2 81989 SERIAL: NLS-89-034 10CFR50 90 A. B CUTTER 89TSB05 Vice President Nuclear Services Department 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 DELETION OF ORGANIZATION CHARTS AND ADMINISTRATIVE CHANGES TO TECHNICAL SPECIFICATION SECTION 6.0 Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) requested a revision to the Technical Specifications for the Brunswick Steam Electric Plant (BSEP),
Units 1 and 2 on July 11, 1988 which proposed a change to delete the organization charts from the Technical Specifications (TS) in accordance with the guidelines provided in Generic Letter 88-06, " Removal of Organization Charts from Administrative Control Requirements"' issued on March 22, 1988.
ECarolina Power & Light Company also requested a revision to the Technical Specifications on April 1,1987 which proposed administrative and organizational changes.
'During recent conversations with the NRC Project Manager, CP&L was advised to
.withdraw both the April 1, 1987 and July 11, 1988 requests for license amendment and submit a new request for license amendment which combined the tuo previous requests. Therefore, CP&L withdrew the two above-mentioned requests by letter dated February 14, 1989 and hereby submits in.its entirety a new request for license amendment to delete organization charts from Technical i scifications, incorporate other organizational changes to Section 6.D, Administrative Controls, and update TS Section 6.5.4 9 to reflect current 10CFR50 72 and 10CFR30.73 reporting requirements.
Enclosure 1 provides a detailed description of the proposed changes and the basis for the changes.
Enclosure 2 details the basis for the Company's determination that the pi posed changes do not involve a significant hazards consideration.
l Enclosure 3 provides instructions for incorpe ition of the proposed changes L into the Technical Specifications.
L l-Enclosure 4 provides a summary of the proposed Technical Specification changes for each unit on a page by page basis. pol 8905010254 090428 PDR P-ADOCK 05000324 I
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- Document Control Desk b NLS-89-034 / Page 2 Enclosure 5 provides proposed Technical Specification pages for Unit 1.
Enclosure 6 provides proposed Technical Specification pages for Unit 2.
Please refer any questions regarding this submittal to Mr. Stephen D. Floyd at (919) 546-6901.
Your m ry tr y, -
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A. B. Cutter ABC/DJK/che
Enclosures:
'1. Basis for Change Request
- 2. 10CFR50.92 Evaluation
- 3. Instructions for Incorporation and Technical Specification Pages
- 4. Summary List of Revisions
- 5. Proposed iechnical Specification Pages - Unit 1
- 6. Proposed Technical Specification Pages - Unit 2 cc: Mr. S. D. Ebneter Mr. E. G. Tourigny Mr. W. H. Ruland Mr. Dayne Brown A. B. Cutter, having been first' duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.
4 . MJ My commission expires: //27 87 i
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K ENCLOSURE 1 BRUNSWICK ~ STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS. 50-325 & 50-324
,3 OPERATINC LICENSES DPR-71 & DPR-62 REQUbot FOR LICENSE AMENDMENT DELETION OF ORGANIZATION CHARTS AND ORGANIZATIONAL CHANCES BASIS'FOR CHANGE REQUEST Proposed Changes Delete the organization charts (Figures 6.2.1-1, 6.2.2-1, and 6.2.2-2) from BSEP Technical Specifications by adding general requirements that capture the essential aspects of organizational structure defined by existing on-site an
- off-site organization charts.- In addition, revise the Index to reflect the title change of Section 6.2.1 and delete reference to Figure 6.2.2-1 in Section 6.3.
Revise Technical' Specification Section 6.0, Administrative Controls, to reflect the followi'ng organizational and individual titles:
" Director - Training"tshould read " Manager - Training (BSEP)."
" Corporate Nuclear Safety Section" should read " Nuclear Safety Section."
"Vice President - Brunswick Nuclear Project" should read " Manager -
Brunswick Nuclear. Project."
, "Vice President - Corporate Nuclear Safety and Research" should read "Vice President - Nuclear' Services."
" Chairman / President and Chief Executive Officer" should read
" Chairman / President."
~" Executive Vice President - Power Supply and Engineering and Construction" should read " Executive Vice President - Power Supply."
" Senior Vice President - Nuclear Generation" should be added.
" Manager - Quality Assurance Service Section" should read " Manager -
Quality Assurance Services Section."
" Manager - Technical and Administrative Support" and " Assistant to Plant General Manager" should be removed from the list of Plant Nuclear Safety Committee members, and the quorum requirement should be adjusted accordingly.
Revise Technical' Specification Section 6.5.4.9, Nuclear Safety Section review of " events requiring 24-hour written notification" to " reportable events" required by 10CFR50.72 and 10CFR50.73.
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' Basis' The content 1 required in the Administrative Control Section of the Technical Specifications (TS) is specified in 10CFR50.36c(5). The regulation requires E that.the Technical Specification contain the controls and provisions that are necessary to assure. operation of the facility in a safe manner and does not
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- specifically require inclusion of organization charts in Technical Specifications.
The removal of organization charts is a line item improvement that was proposed on a lead plant basis for the Shearon Harris Nuclear Power Plant and
- was endorsed by'the Westinghouse owners Group. This change was reviewed as part of the NRC's program for improvements in Technical Specifications. The objectives of that program were established by the Commission's Interim Policy Statement on Technical Specification Improvements. The staff concluded that the removal'of organization charts from Technical Specifications will provide greater flexibility for licensees to implement changes in both the on-site and
- off-site organizational structure, consistent with Commission policy.
The NRC has encouraged licensees to propose changes to delete organization charts from their Technical Specifications which are consistent with the guidance provided in Generic Letter 88-06. Carolina Power & Light Company's Shearon Harris Nuclear Power Plant and H. B. Robinson Steam Electric Plant have been issued amendments to delete organization charts from their Technical Specifications.
- Technical' Specification Section 6.0,' Administrative Controls should be revised to reflect current organizational and individual titles. Most of these changes were submitted April 1, 1987, but some recent changes are being submitted for the first time.
Also, the Manager - Technical and Administrative Support and the Assistant to Plant General Manager positions have been eliminated from the plant organization; therefore, reference to these two positions should be removed from the list.of Plant Nuclear Safety Committee (PNSC) members.- P; 2 to the reduction in the total number of PNSC membership, the quorum requirement should be reduced by one. The quorum (which was six out of ten members or 60 percent).is now five out of eight members or 62 1/2 percent. The margin of safety will not be affected since the percentage of the PNSC membership which makes up the quorum has increased.
Technical Specification Secton 6.5.4.9 should be updated to reflect the current 10CFR;0.72 requirements of immediate notification (one-hour or four-hour reports) via the Emergency Notification System and 10CFR50.73 requirement of Licensee Event Report within 30 days after discovery of the
- event. This supercedes the old requirement of 24-hour written notification.
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References
- 1. Generic Letter 88-06, " Removal of Organization Charts from Administrative Control Requirements," March 22, 1988
- 2. Shearon Harris Nuclear Power Plant, Amendment No. 3 to Facility Operating License, Appendix A, Technical Specifications, January 27, 1988
- 3. H. B. Robinson Steam Electric Plant, Unit 2, Amendment No. 120 to Facility Operating License, Appendix A, Technical Specifications, November 3,1988 i
I El-3 (200CRS)
ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATINC LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT DELETION OF ORGANIZATION CHARTS AND ORGANIZATIONAL CHANCES 10CFR50.92 EVALUATION The Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation 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, (2) create the possibility of a new or different Liad of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Carolina 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 determination are as follows:
Proposed Changes Delete the organization charts (Figures 6.2.1-1, 6.2.2-1, and 6.2.2-2) from BSEP Technical Specifications.by adding general requirements that capture the essential aspects of organizational structure that are defined by existing on-site and off-site organization charts. In addition, revise the Index to reflect the title change of Section 6.2.1 and delete the reference to Figure 6.2.2-1 in Section 6.3.
Revise Technical Specification Section 6.0, Administrative Controls to reflect current organizational and individual titles. Also, remove " Manager -
Technical and Administrative Support" from the list of Plant Nuclear Safety Committee members and adjust the quorum requirement accordingly. !
Revise Technical Specification Section 6.5.4.9, Nuclear Safety Section review of " events requiring 24-hour written notification" to " reportable events" required by 10CFR50.72 and 10CFR50.73.
No Significant Hazards Analysis The change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because deletion of the organization charts, updating of individual titles, and removal of two Plant Nuclear Safety Committee (PNSC) members from the Technical Specifications does not affect plant operation. As in the past, the NRC will continue to be informed of organizational changes through other required controls. The Code of Federal Regulations, E2-1 (200CRS)
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8 4-Title 10, Part 50.34(b)(6)(i) requires that the organizational structure be included in the Final' Safety Analysis Report (FSAR). Chapter 13 of the FSAR provides a description of the organization and detailed organization charts. As required by 10CFR50.71(e), the company submits annual updates to the FSAR. Appendix B to 10CFR50 and 10CFR50.54(a)(3) govern changes to the organization described in the Quality Assurance Program. Some of these organizational changes cequire prior NRC approval. Also, it is CP&L's practice to inform the NRC of organizational changes affecting the nuclear facilities prior to implementation. The company intends to continue this practice for
!. future organizational changes.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes are administrative in nature and involve no physical alterations of plant configuration or changes to setpoint or operating parameters.
- 3. The proposed amend-ent does not involve a significant reduction in the margin of safety bt .ause CP&L, through its Quality Assurance Programs, its commitment to maintain only qualified personnel in positions of responsibility, and other required controls assure that safety functions will be performed at a high level of competence. 'Therefore, removal of the organization charts from the Technical Specifications will not affect the margin of safety.
Also, revising Section 6.0 to reflect current organization by revising individual titles, removing two Plant Nuclear Safety (PNSC) members, and adjusting the quorum requirements will not affect the function of the organization or PNSC. The PNSC will continue to review, overview, evaluate, and maintain plant operational safety; therefore, the margin of safety will not be affected.
Updating of.the Technical Specifications to reflect current 10CFR50.72 and 10CFR50.73 reporting requirements which superceded the old reporting requirement of 24-hour written notification will not affect the margin of safety.
Based on the above reasoning, CP&L has determined that the proposed amendment does not involve a significant hazards consideration.
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ENCLOSURE 3 BRUNSW4 ;K STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325-& 50-324 OPERATING LICENSES DPR-71 & DPR-62
(; REQUESS FOR LICENSE AMENDMENT-P , DELETION OF ORGANIZATION CHARTS AND' ORGANIZATIONAL CHANGES INSTRUCTIONS FOR INCORPORATION
~ The- proposed chan'ges to the Technical Specifications (Appendix A to Operating
' Licenses DPR-71 and DPR-69.) would-be incorporated as follows:
UNIT 1 Remove Page Insert Page XIV XIV XV XV XVI .
XVI 6-1 through 6-30 6-1 through 6-27 UNIT 2 Remove Page Insert Page XIV XIV XV. 'XV XVI XVI
.6-1 through 6-30 6-1 through 6-27 .
E3-1 (200CRS)
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, :. .n ENCLOSURE'4
' BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2'
[. NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62
= REQUEST FOR LICENSE AMENDMENT q DELETION OF ORGANIZATION CHARTS ORGANIZATIONAL CHANGES.
g
SUMMARY
LIST OF REVISIONS.
' UNIT 1 o
Pages Description of Changes XIV Revise the Index to change Section 6.2.1 title from "Offsite" to "Offsite and Onsite Organizations."
Revise page number references due to
. repagination.
XV Revise Index to change Section 6.5.4 title from " Corporate Nuclear Safety Section" to " Nuclear Safety Section."
Revise page number reference due to repagination..
XVI Revise.page number references due to
. repagination.
6-1 Section 6.2.1 - Delete reference to Figure 6.2.1-l'by adding general requirements that capture the' essential aspects of organizational structure:
that was defined by onsite and offsite z
organi'ation charts.
Section 6.2.2 - Delete reference to Figure 6.2.2-1. Insert a new Item d.
to revise the section to include requirements for Shift Operator Supervisors, Shift Foremen, and Senior Control Operators to hold Senior Reactor Operator License and Control Operators to hold Re.-etor Operator License. Also re-letter Item d. to e.,
Item e. to f., Item f. to g.
6-2 Re-letter Item g to h.
6-3 Delete Figure 6.2.1-1.
E4-1 (200CRS)
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UNIT 1 CONTINUED l
1 Pages Description of Changer t
6 Delete Figure 6.2.2-1. j g
6-3 Delete Figure 6.2.2-2.
5-6 Revise page number to 6-3.
6-7 Revise page number to 6-4.
L Section 6.2.3.3 - Revise " Manager -
6-8 Corporate Nuclear Safety Section" to
" Manager - Nuclear Safety Section."
Section 6.3 - Delete reference to Figure 6.2.2-1 in Section 6.3.
Section 6.4.l~and 6.4.2 - Revise
" Director - Training" to " Manager -
Training (BSEP)."
Revise page number to 6-5.
6-9 Revise page number to 6-6.
6-10 Section 6.5.2.9, item b. - Revise
" Corporate Nuclear Safety Section" to
" Nuclear Safety Section."
Revise page numbcr to 6-7, 6-11 Section 6.5.3.2 - Revise " audit" to
" audits."
Section 6.5.3.3 - Remove " Manager -
Technical and Administrative Support" and " Assistant to Plant Manager" from list of Plant Nuclear Safety Committee Members.
Section 6.5.3.7 - Revise minimum quorum ;
from " Chairman or designated alternate and five members" to " Chairman or designated alternate and four members."
Revise page number to 6-8.
6-12 Section 6.5.3.8, Item e., f., and k., -
Revise " Manager - Corporate Nuclear Safety Section" to " Manager - Nuclear Safety Section."
Revise "Vice President - Brunswick Nuclear Project" to " Manager -
Brunswick Nuclear Project."
i E4-2 l a00CRS)
UNIT 1 CONTINUED t
Pages Description of Changes Section 6.5.4.10 - Revise "6.5.4.9(e) through (g)" to read "6.5.4.9(e) through (i)."
Revise page number to 6-9.
, 6-13 Section 6.5.3.9 - Revise "Vice President - Brunswick Nuclear Project" to " Manager - Brunswick Nuclear Project."
Section 6.5.3.9 - Revise "Vice President - Corporate Nuclear Safety &
Research" to "Vice President - Nuclear Services."
Section 6.5.3.10 - Revise "Vice President - Brunswick Nuclear Project" to " Manager - Brunswick Nuclear Project."
Section 6.5.3.10 - Revise " Manager -
Corporate Nuclear Safety Section" to
" Manager - Nuclear Safety Section."
Section 6.5.4 - Revise " Corporate Nuclear Safety Section" to " Nuclear Safety Section."
Section 6.5.4.1 - Revise " Corporate Nuclear Safety Section (CNSS) of the Corporate Nuclear Safety & Research Department" to " Nuclear Safety Section 1 (NSS) of the Nuclear Services Department."
Revise page number to 6-10.
6-14 Section 6.5.4.3, 6.5.4.5, 6.5.4.8, and 6.5.4.9 - Revise " Corporate Nuclear l Safety Section" to " Nuclear Safety l S e c t i or. . " i Revise page number to 6-11.
6-15 Section 6.5.4.9, Item g. - Revise ,
" Manager - Corporate Nuclear Safety i Section" to " Manager - Nuclear Safety Section" (twice in same paragraph).
l l
E4-3 (200CRS) l I;
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H '
UNIT 1 CONTINUED.
(* ,
Ln '
'Pages Description'ofLChanges F d 1' Section~6.5'.4'.9 -' Delete item e., and renumber."e'.1" to "e", "e.2" to "f".
- , Add new item "g. reportable events" and;
';
- o renumber "f" to "h, and "g" ' to "i".
Section 6.5.4.11 - Revise " Corporate b Nuclear Safety Section" to " Nuclear.
Safety.Section'."
L Section'6.5.4.11, Item a. - Revise "CNSS" to "NSS."
h Section.6.5.4.11, Item b. - Revise "Vice President - Brunswick Nuclear f Project" to " Manager.- Brunswick P' Nuclear Project."
L>
. Section 6.5.4.11, Item c. - Revise
" Corporate Nuclear Safety"'to " Nuclear m
Safety Section's."
1.fn Revise " Chairman / President and Chief Executive Of ficer to "Chai- un/
President.".
l!
! Revise " Executive Vice President -
L- Power Supply and Engineering and
! Construction"=to " Executive Vice President - Power Supply."
1 Add " Senior Vice President - Nuclear 7
Ceneration."
Revise "Vice President - Brunswick-Nuclear Project" to " Manager -
Brunswick Nuclear Project."
Revise "Vice President - Corporate Nuclear Safety and Research" to "Vice President - Nuclear Services."
i' Revise page number to 6-12.
g 6-16 Revise page number t o 6-13.
6-17 Section 6.5.5.5 - Revise " Quality i Assurance Service Section" to " Quality Assurance Services Section."
Revise " Executive Vice President -
Power Supply and Engineering and Construction" to " Executive Vice President - Power Supply."
E4-4 (200CRS)
0M'
l UNIT 1 CONTINUED r
y .
. Description of~ Changes
~
Pages-Add " Senior Vice President - Nuclear-
, Generation."
Revise "Vice President - Brunswick Nuclear' Project" to " Manager -
Brunswick Nuclear Project."
Revise "Vice President - Corporate Nuclear Safety and Research" to "Vice President - Nuclear Services."
Revise page number to 6-14.
18 Section 6.6.1, Item b.; 6.7.1, Item b.
and d. - Revise'" Corporate Nuclear Safety'Section" to " Nuclear Safety.
Section".and "Vice President -
Brunswick Nuclear Project" to
" Manager - Brunswick Nuclear. Project."
Revise page number to 6-15.
6-19 Revise page number to.6-16.
6-20 Revise page number to.6-17.
6-21' Revise page number to 6-18.
6 Revise page number to 6-19.
6 Revise page number to 6-20.
6-24 Revise page number to 6-21.
6-25 Revise page number to 6-22.
6-26: Revise page number to 6-23.
6-27 Section 6.10.2, Item n. - Revise
" Corporate Nuclear Safety Section" to
" Nuclear Safety Section."
Revise page number to 6-24.
6-28 Revise page number to 6-25.
6-29 Revise page number to 6-26.
6-30 Revise page number to 6-27.
E4-5 (200CRS)
'4% .
1 D UNIT'2' Pages Description of Changes =
1.
L .XIV. Revise the Index to change Section 6.2.1 title from "Offsite" to "Offsite and Onsite Organizations."'
i Revise page number references due to repagination.
t XV Revise Index to change Section 6.5.4-title from " Corporate' Nuclear Safety l;g Section" to " Nuclear Safety Section."
Revise page number reference due.to repagination.
XVI' Revise page number references due to repagination.
6-1 Section 6.2.1 - Delete reference to Figure 6.2.1-1 by adding general requirements that capture the essential aspects of organizational structure that was defined by onsite and offsite organization charts.
Section'6.2.2 - Delete reference to Figure 6.2.2-1. Insert a new Item d.
to revise the section to include requirements for Shift Operator-Supervisors, Shift Foremen, and Senior control Operators to hold Senior Reactor Operator License and Control Operators to hold Reactor Operator License. Also re-letter Item d. to e.,
Item'e. to f., Item f. to g.
6-2 Re-leN 2r Item g to h.
6-3 Delete Figure 6.2.1-1.
6-4 Delete Figure 6.2.2-1.
6-5 Delete Figure 6.2.2-2. j 6-6 Revise page number to 6-3. .l 6 Revise page number to 6-4. 1 I
6-8 Section 6.2.3.3 - Revise " Manager - ]
Corporate Nuclear Safety Section" to
" Manager - Nuclear Safety Section." J I,
E4-6 ')
aooCRS) l
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.;n s . J.
i i
'* E - UNIT 2 CONTINUED
.: !i .
K 1
l >
?pL Pages Description of Changes.
Di ..
Section 6.3 - Delete reference to y Pigure 6.2.2-1 in Section 6.3.
Section'6.4'.1 and 6.4.2 - Revise
" Director - Training" to " Manager.--
Training (BSEP)."
Revise page number to 6-5.
- 6-9 Revise page number to.6-6'.
6-10 Section 6.5.2.9, Item b. - Revise
, " Corporate Nuclear Safety Section" to
" Nuclear Safety Section."
l Revise page number to 6-7.
6-11 Section 6.5.3.3 - Remove " Manager -
Technical and Administrative Support" and " Assistant to Plant General Manager" from the list of Plant Nuclear Safety Committee members.
Section 6.5.3.7 - Revise minimum quorum from " Chairman or designated alternate and five members" to " Chairman or-designated alternate and four-members."
Revise page number to 6-8.
12 ' Sect. ion 6.5.3.8, Item e., f., and k., -
Revise " Manager - Corporate Nuclear Safety Section"'to " Manager - Nuclear Safety Section."
Revise "Vice President - Brunswick Nuclear Project" to " Manager'-
Brunswick Nuclear Project."
' Revise page number to 6-9.
6-13 Section 6.5.3.9 - Revise "Vice President - Brunswick Nuclear Project" to " Manager - Brunswick Nuclear Project."'
Section 6'.5.3.9 - Revise "Vice President - Corporate Nuclear Safety &
Research" to "Vice President - Nuclear Services."
Section 6.5.3.10 - Revise "Vice President - Brunswick Nuclear Project" E4-7 (200CRS) x_______--_--- . - _ -
Q .; ,
- UNIT 2 CONTINUED '
/.
p Pages' Description'of Changes 1
Lu -to " Manager - Brunswick Nuclear Project."
Section 6.5.3.10'- Revise " Manager -
Corporate Nuclear Safety Section" to
" Manager - Nuclear Safety Section."
Section 6.5.4 - Revise " Corporate Nuclear. Safety Section" to " Nuclear Safety Section'."
Section 6.5.4.1 - Revise " Corporate Nuclear Safety Section (CNSS) of the Corporate Nuclear Safety 6.Research Department" to " Nuclear ~ Safety Section (NSS)'of the Nuclear. Services Department."
Revis'e page number to 6-10.
6-14 Section 6.5.4.3, 6.5.4.5, 6.5.4.8, and 6.5.4.9 - Revise " Corporate. Nuclear Safety Section" to " Nuclear Safety Section."
Revise page number _to 6-11A 6-15. Section 6.5.4.9, Item g. - Revise
" Manager - Corporate Nuclear Safety Section" to " Manager - Nuclear Safety Section" (twice in same paragraph).
Section 6.5.4.9 - Delete item e., and renumber "e.1" to "e", "e.2" to "f".
Add new item "g. reportable events"'and renumber "f" to "h", "g" to "i".
Section 6.5.4.10 - Revise "6.5.4.9(e) through (g)" to read "6.5.4.9(e) through (i)."
Section 6.5.4.11 - Revise " Corporate Nuclear Safety Section" to " Nuclear Safety Section."
Section 6.5.4.11, Item a. - Revise "CNSS" to "NSS."
Section 6.5.4.11, Item b. - Revise "Vice President - Brunswick Nuclear Project" to " Manager - Brunswick Nuclear Project."'
E4-8 (200CRS) r-- __ __
UNIT 2 CONTINUED Pages Description : Changes Section 6.5.4.11, Item c. - Revise
" Corporate Nuclear Safety" to " Nuclear Safety Section's."
' Revise " Chairman / President and Chief Executive Officer" to " Chairman /
President."
Revise " Executive Vice President -
Power Supply and Engineering and Construction" to " Executive Vice President - Power Supply."
Add " Senior Vice President - Nuclear Generation."
Revise "Vice President - Brunswick Nuclear Project" to " Manager -
Brunswick Nuclear Project."
Revise "Vice President - Corporate Nuclear Safety and Research" to "Vice President - Nuclear Services."
Revise page number to 6-12.
16 Revise page number to 6-13.
6-17 Section 6.5.5.5 - Revise " Quality Assurance Service Section" to " Quality Assurance Services Section."
Revise " Executive Vice President -
Power Supply and Engineering and Construction" to " Executive Vice President - Power Supply."
Add " Senior Vice President - Nuclear Generation."
Revise "Vice President - Brunswick Nuclear Project" to " Manager -
Brunswick Nuclear Project."
Revise."Vice President - Corporate Nuclear Safety and Research" to "Vice President - Nuclear Services."
Revise page number to 6-14.
E4-9 (200CRS)
L_-__-___
.- 1 UNIT 2 CONTINUED l i
Pages Description of Changes 6-18 Section 6.6.1, Item b.; 6.7.1,. Item b.
and d. - Revise " Corporate Nuclear Safety Section" to " Nuclear Safety Section" and "Vice President --
Brunswick Nuclear Project" to
" Manager - Brunswick Nuclear Project." x l
Revise page number to 6-15. s 6-19 Revise page number to 6-16.
6-20 Revise page number to 6-17.
6-21 Revise page number to 6-18. 1 6 Revise page number to 6-19.
6-23 Revise page number to 6-20.
6-24 Revise page number to 6-21.
6-25 Revise page number to 6-22.
6-26 Revise page number to 6-23.
6-27 Section 6.10.2, Item n. - Revise
" Corporate Nuclear Safety Section" to
" Nuclear Safety Section."
Revise page number to 6-24.
6-28 Revise page number to 6-25.
6-29 Revise page number to 6-26.
6-30 Revise page number to 6-27.
E4-10 (200CRS)
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