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| . DETERMINATION OF SIGNIFICANT IIAZARDS ne change has been evaluated against the standards in 10 CFR 50.92 and has been determined to not involve a significant hazards consideration in that operation of the facility in accordance with the proposed amendment: | | . DETERMINATION OF SIGNIFICANT IIAZARDS ne change has been evaluated against the standards in 10 CFR 50.92 and has been determined to not involve a significant hazards consideration in that operation of the facility in accordance with the proposed amendment: |
| : 1. Would not involve a sigmficant increase in the probability or consequences of an accidentpreviously evaluated. | | : 1. Would not involve a sigmficant increase in the probability or consequences of an accidentpreviously evaluated. |
| The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, Baltimore Gas and Electric Company (BGE) requested approval to use the ABB/ Combustion Ergineering (ABB/CE) convolution technique for determining the values in the Calvert ClirTs Core Operating Limits Report (COLR) related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change does not involve a significant increase in the probability or consequences of an accident presiously evaluated. | | The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By {{letter dated|date=November 1, 1994|text=letter dated November 1,1994}}, Baltimore Gas and Electric Company (BGE) requested approval to use the ABB/ Combustion Ergineering (ABB/CE) convolution technique for determining the values in the Calvert ClirTs Core Operating Limits Report (COLR) related to the pre-trip main steam line break event. Approval was given by the NRC in their {{letter dated|date=May 11, 1995|text=letter dated May 11,1995}}. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change does not involve a significant increase in the probability or consequences of an accident presiously evaluated. |
| : 2. Would not create the possibility ofa new or diferent type ofaccidentfrom any accident previously evaluated. | | : 2. Would not create the possibility ofa new or diferent type ofaccidentfrom any accident previously evaluated. |
| The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved meti.odologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change would not create the possibility of a new or different type of accident from any accident previously evaluated. | | The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved meti.odologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By {{letter dated|date=November 1, 1994|text=letter dated November 1,1994}}, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their {{letter dated|date=May 11, 1995|text=letter dated May 11,1995}}. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change would not create the possibility of a new or different type of accident from any accident previously evaluated. |
| : 3. Would not involve a significant reduction in the margin ofsafety. | | : 3. Would not involve a significant reduction in the margin ofsafety. |
| The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety. | | The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By {{letter dated|date=November 1, 1994|text=letter dated November 1,1994}}, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their {{letter dated|date=May 11, 1995|text=letter dated May 11,1995}}. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety. |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20211J9861999-09-0101 September 1999 Application for Amends to Licenses DPR-53 & DPR-69,changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2 & Correcting Dc Voltage Range Listed in Surveillance Requirement 3.3.6.2 ML20211G7591999-08-27027 August 1999 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.13 to Allow Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities During Continuing Fuel Assembly Movement ML20196E2101998-11-30030 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 sleeves.Non-proprietary Rev 03-P to CEN-633-NP & Proprietary Rev 03-P to CEN-633-P,encl.Proprietary Info Withheld ML20195K3711998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section Xi,Subsections IWE & Iwl,Per 10CFR50.55a ML20196A6001998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69, Requesting Indirect Transfer of Control,Pursuant to 10CFR72.50,of Matls License SNM-2505 for Plant ISFSI ML20195J7131998-11-19019 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.6, SWS, by Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20154N1861998-10-16016 October 1998 Application for Amends to Licenses DPR-53 & DPR-69 to Incorporate Revised TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S1341998-07-20020 July 1998 Application for Amend to License DPR-59,implementing Mod That Involves Replacing SW Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20236S5591998-07-20020 July 1998 Application for Amend to Licenses DPR-53 & DPR-69,providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20198K9591998-01-12012 January 1998 Rev 11 to 961204 Application for Amends to Licenses DPR-53 & DPR-69,converting to Improved Sts,Per NUREG-1432 ML20217K6591997-10-22022 October 1997 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20211J2691997-10-0202 October 1997 Application for Amend to License DPR-53,revising TS to Reflect New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20141F9181997-05-16016 May 1997 Application for Amend to License DPR-53,implementing Mod Involves Replacing Service Water Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20136A9751997-03-0606 March 1997 Application for Amend to License DPR-69,allowing Mod to Unit 2 SW Sys Which Constitutes Unreviewed Safety Question in 10CFR50.59 ML20134D2871997-01-31031 January 1997 Application for Amends to Licenses DPR-53 & DPR-69,changing to Support Larger Number of Plugged SG Tubes for Future Operating Cycles ML20149M0801996-12-0404 December 1996 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs to Be Generally Consistent w/NUREG-1432,Rev 1,thus Replacing 2 Current Sets of TSs W/Single Set Applicable to Both Units ML20135A5171996-11-26026 November 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J,To Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20128H5971996-10-0303 October 1996 Application for Amend to License DPR-53,changing Provisions for Receiving,Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7801996-09-10010 September 1996 Application for Amends to Licenses DPR-53 & DPR-69 Requesting Extension of ESFAS Automatic Actuation Logic Surveillance from Monthly to Quarterly ML20116F8231996-08-0101 August 1996 Application for Amends to Licenses DPR-53 & DPR-69,allowing Use of Blind Flanges During Modes 1-4 in Plant Containment Purge Sys ML20116E3571996-07-26026 July 1996 Application for Amends to Licenses DPR-53 & DPR-69,to Repair Defective SG Tubes by Electrosleeving ML20117J1911996-05-28028 May 1996 Application for Amend to License DPR-53 & DPR-69,requesting Exigent Amends to Allow Installation of Proposed Modification of Unit 1 & 2 Service Water (SRW) Systems ML20101K5911996-03-28028 March 1996 Application for Amends to Licenses DPR-53 & DPR-69, Requesting to Reduce Moderator Temp Coefficient Limit Shown on TS Figure 3.1.1-1 ML20101D8211996-03-15015 March 1996 Suppl to LAR Re Sleeving Option for SG Tube Repair.Proposes Rev to TS Wording in Attachments (A-3) & (A-4) by Removing Generic Ref to Technical Repts & Replace W/Ref to Specfic Approved Repts ML20096D4291996-01-16016 January 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095K2701995-12-21021 December 1995 Application for Amends to Licenses DPR-53 & DPR-59, Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 ML20095C7421995-12-0707 December 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant ML20094S1481995-11-30030 November 1995 Application for Amends to Licenses DPR-53 & DPR-59,allowing Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20094D6131995-11-0101 November 1995 Application for Amends to Licenses DPR-53 & DPR-69,upgrading ESF Electrical Sys at Plant to Provide Addl Protection from Loss of Electrical Power ML20093M4141995-10-20020 October 1995 Application for Amend to License DPR-53,extending 18-month Surveillances to 960331 ML20098C0661995-10-0202 October 1995 Application for Amend to License DPR-69,requesting Extension of Unit 2 TS Action Statements 3.7.6.1.a & B from 7 Days to 30 Days for Loss of Emergency Power to Support 1996 Refueling Outage ML20086N2341995-07-13013 July 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 5.2.1 to Allow Use of Lead Fuel Assemblies & Requests Temporary Exemption from Requirements of 10CFR50.46, 10CFR50.44 & 10CFR50,App K for Ccnpp Unit 1 ML20085D4901995-06-0909 June 1995 Application for Amends to Licenses DPR-53 & DPR-69, Implementing Changes to Radiological Effluent TS Per GL 89-01 ML20084R0111995-06-0606 June 1995 Application for Amends to Licenses DPR-53 & DPR-69.Amends Would Revise TSs to Extend Certain 18-month Frequency Surveillances to Refueling Interval ML20084P9681995-06-0202 June 1995 Application for Amends to Licenses DPR-53 & DPR-69,proposing TS Re Pressurizer Safety Valves Lift Tolerance ML20087H9141995-04-28028 April 1995 Application for Emergency Amend to License DPR-53.Amend Would Revise CREVS TSs to Provide an Extension of Allowed Outage Time ML20081D0411995-03-15015 March 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Reformat Current Administrative Controls Section & Relocate Several Requirements to Other Documents & Programs ML20079A5771995-02-24024 February 1995 Application for Amend to License DPR-69,allowing Extension of Interval Between First & Second Type a Test During Second Service Period & Extension of Second Service Period to 12 Years to Coincide w/1999 Plant Inservice Insp ML20078G8161995-01-31031 January 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS to Increase Min Amount of Trisodium Phosphate Dodecahydrate Verified in TS Surveillance ML20073G2401994-09-23023 September 1994 Application for Amends to Licenses DPR-53 & DPR-69,allowing one-time Extension from 7 to 14 Days of AOT for Dedicated Class 1E Emergency Power Source During 1995 Refueling Outage ML20071P4421994-08-0404 August 1994 Application for Amend to License DPR-53 & DPR-69,eliminating TS 3/4.3.3.3 for Seismic Monitoring Instrumentation, Relocating Requirements for Operation & Testing of Seismic Monitoring Instrumentation to Plant Updated FSAR ML20149E8321994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising Surveillances Associated W/Edgs to Add High Crankcase Pressure to EDG Trips Which Are Verified to Be Automatically Bypassed on Safety Injection Actuation Signal ML20071N2961994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating TS 3.9.1, Refueling Operations,Boron Concentration ML20069H6471994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.6.2.2.d,extending Surveillance Interval from 18 to 24 Months ML20069H6191994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.8.1.1.1.b,extending Alternate Offsite Power Circuit Surveillance Frequency from 18 to 24 Months ML20069H6311994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.7.1.2.c,extending Interval for Three Auxiliary Feedwater Surveillance Requirements from 18 to 24 Months ML20069C3921994-05-27027 May 1994 Application for Amend to License DPR-69,revising Heatup & Cooldown Curves & LTOP Controls for Unit 2 to Support Mods to LTOP Sys Scheduled for Spring 1995 Refueling Outage ML20069C2801994-05-27027 May 1994 Application for Amends to Licenses DPR-53 & DPR-69, Revising TS Surveillance Test Interval from Monthly to Quarterly for Several Channel Functional Tests for RPS & ESFAS ML20058K2831993-12-0808 December 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TS Associated W/Content of Design Features ML20059L4051993-11-11011 November 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs by Relocating Tables of Response Time Limits for Reactor Protection Sys & ESFAS Instruments from TSs to Updated FSAR 1999-09-01
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211J9861999-09-0101 September 1999 Application for Amends to Licenses DPR-53 & DPR-69,changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2 & Correcting Dc Voltage Range Listed in Surveillance Requirement 3.3.6.2 ML20211G7591999-08-27027 August 1999 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.13 to Allow Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities During Continuing Fuel Assembly Movement ML20196E2101998-11-30030 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 sleeves.Non-proprietary Rev 03-P to CEN-633-NP & Proprietary Rev 03-P to CEN-633-P,encl.Proprietary Info Withheld ML20195K3711998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section Xi,Subsections IWE & Iwl,Per 10CFR50.55a ML20196A6001998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69, Requesting Indirect Transfer of Control,Pursuant to 10CFR72.50,of Matls License SNM-2505 for Plant ISFSI ML20195J7131998-11-19019 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.6, SWS, by Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20154N1861998-10-16016 October 1998 Application for Amends to Licenses DPR-53 & DPR-69 to Incorporate Revised TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S1341998-07-20020 July 1998 Application for Amend to License DPR-59,implementing Mod That Involves Replacing SW Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20236S5591998-07-20020 July 1998 Application for Amend to Licenses DPR-53 & DPR-69,providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20198K9591998-01-12012 January 1998 Rev 11 to 961204 Application for Amends to Licenses DPR-53 & DPR-69,converting to Improved Sts,Per NUREG-1432 ML20217K6591997-10-22022 October 1997 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20211J2691997-10-0202 October 1997 Application for Amend to License DPR-53,revising TS to Reflect New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20141F9181997-05-16016 May 1997 Application for Amend to License DPR-53,implementing Mod Involves Replacing Service Water Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20136A9751997-03-0606 March 1997 Application for Amend to License DPR-69,allowing Mod to Unit 2 SW Sys Which Constitutes Unreviewed Safety Question in 10CFR50.59 ML20134D2871997-01-31031 January 1997 Application for Amends to Licenses DPR-53 & DPR-69,changing to Support Larger Number of Plugged SG Tubes for Future Operating Cycles ML20149M0801996-12-0404 December 1996 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs to Be Generally Consistent w/NUREG-1432,Rev 1,thus Replacing 2 Current Sets of TSs W/Single Set Applicable to Both Units ML20135A5171996-11-26026 November 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J,To Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20128H5971996-10-0303 October 1996 Application for Amend to License DPR-53,changing Provisions for Receiving,Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7801996-09-10010 September 1996 Application for Amends to Licenses DPR-53 & DPR-69 Requesting Extension of ESFAS Automatic Actuation Logic Surveillance from Monthly to Quarterly ML20116F8231996-08-0101 August 1996 Application for Amends to Licenses DPR-53 & DPR-69,allowing Use of Blind Flanges During Modes 1-4 in Plant Containment Purge Sys ML20116E3571996-07-26026 July 1996 Application for Amends to Licenses DPR-53 & DPR-69,to Repair Defective SG Tubes by Electrosleeving ML20117J1911996-05-28028 May 1996 Application for Amend to License DPR-53 & DPR-69,requesting Exigent Amends to Allow Installation of Proposed Modification of Unit 1 & 2 Service Water (SRW) Systems ML20101K5911996-03-28028 March 1996 Application for Amends to Licenses DPR-53 & DPR-69, Requesting to Reduce Moderator Temp Coefficient Limit Shown on TS Figure 3.1.1-1 ML20101D8211996-03-15015 March 1996 Suppl to LAR Re Sleeving Option for SG Tube Repair.Proposes Rev to TS Wording in Attachments (A-3) & (A-4) by Removing Generic Ref to Technical Repts & Replace W/Ref to Specfic Approved Repts ML20096D4291996-01-16016 January 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095K2701995-12-21021 December 1995 Application for Amends to Licenses DPR-53 & DPR-59, Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 ML20095C7421995-12-0707 December 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant ML20094S1481995-11-30030 November 1995 Application for Amends to Licenses DPR-53 & DPR-59,allowing Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20094D6131995-11-0101 November 1995 Application for Amends to Licenses DPR-53 & DPR-69,upgrading ESF Electrical Sys at Plant to Provide Addl Protection from Loss of Electrical Power ML20093M4141995-10-20020 October 1995 Application for Amend to License DPR-53,extending 18-month Surveillances to 960331 ML20098C0661995-10-0202 October 1995 Application for Amend to License DPR-69,requesting Extension of Unit 2 TS Action Statements 3.7.6.1.a & B from 7 Days to 30 Days for Loss of Emergency Power to Support 1996 Refueling Outage ML20086N2341995-07-13013 July 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 5.2.1 to Allow Use of Lead Fuel Assemblies & Requests Temporary Exemption from Requirements of 10CFR50.46, 10CFR50.44 & 10CFR50,App K for Ccnpp Unit 1 ML20085D4901995-06-0909 June 1995 Application for Amends to Licenses DPR-53 & DPR-69, Implementing Changes to Radiological Effluent TS Per GL 89-01 ML20084R0111995-06-0606 June 1995 Application for Amends to Licenses DPR-53 & DPR-69.Amends Would Revise TSs to Extend Certain 18-month Frequency Surveillances to Refueling Interval ML20084P9681995-06-0202 June 1995 Application for Amends to Licenses DPR-53 & DPR-69,proposing TS Re Pressurizer Safety Valves Lift Tolerance ML20087H9141995-04-28028 April 1995 Application for Emergency Amend to License DPR-53.Amend Would Revise CREVS TSs to Provide an Extension of Allowed Outage Time ML20081D0411995-03-15015 March 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Reformat Current Administrative Controls Section & Relocate Several Requirements to Other Documents & Programs ML20079A5771995-02-24024 February 1995 Application for Amend to License DPR-69,allowing Extension of Interval Between First & Second Type a Test During Second Service Period & Extension of Second Service Period to 12 Years to Coincide w/1999 Plant Inservice Insp ML20078G8161995-01-31031 January 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS to Increase Min Amount of Trisodium Phosphate Dodecahydrate Verified in TS Surveillance ML20073G2401994-09-23023 September 1994 Application for Amends to Licenses DPR-53 & DPR-69,allowing one-time Extension from 7 to 14 Days of AOT for Dedicated Class 1E Emergency Power Source During 1995 Refueling Outage ML20071P4421994-08-0404 August 1994 Application for Amend to License DPR-53 & DPR-69,eliminating TS 3/4.3.3.3 for Seismic Monitoring Instrumentation, Relocating Requirements for Operation & Testing of Seismic Monitoring Instrumentation to Plant Updated FSAR ML20149E8321994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising Surveillances Associated W/Edgs to Add High Crankcase Pressure to EDG Trips Which Are Verified to Be Automatically Bypassed on Safety Injection Actuation Signal ML20071N2961994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating TS 3.9.1, Refueling Operations,Boron Concentration ML20069H6471994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.6.2.2.d,extending Surveillance Interval from 18 to 24 Months ML20069H6191994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.8.1.1.1.b,extending Alternate Offsite Power Circuit Surveillance Frequency from 18 to 24 Months ML20069H6311994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.7.1.2.c,extending Interval for Three Auxiliary Feedwater Surveillance Requirements from 18 to 24 Months ML20069C3921994-05-27027 May 1994 Application for Amend to License DPR-69,revising Heatup & Cooldown Curves & LTOP Controls for Unit 2 to Support Mods to LTOP Sys Scheduled for Spring 1995 Refueling Outage ML20069C2801994-05-27027 May 1994 Application for Amends to Licenses DPR-53 & DPR-69, Revising TS Surveillance Test Interval from Monthly to Quarterly for Several Channel Functional Tests for RPS & ESFAS ML20058K2831993-12-0808 December 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TS Associated W/Content of Design Features ML20059L4051993-11-11011 November 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs by Relocating Tables of Response Time Limits for Reactor Protection Sys & ESFAS Instruments from TSs to Updated FSAR 1999-09-01
[Table view] |
Text
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l Ro:EST E. DENTON Baltimore G:s and Electric Company Vice President Calven Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 1
410 586-2200 Ext.4455 local 410 260-4455 Baltimore December 7,1995 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Add the Convolution Analytical Technique to the Technical Soecifications
REFERENCES:
(a) Letter from Mr. R. E. Denton (BGE), to NRC Document Control Desk, dated November 1,1994, Request for Approval to Use Convolution Technique in Main Steam Line Break Analysis (b) Letter from Mr. D. G. Mcdonald, Jr. (NRC), to Mr. R. E. Denton (BGE),
dated May 11,1995, Approval to Use Convolution Technique in Main Steam Line Break Analysis - Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898)
Pursuant to 10 CFR 50.90, the Baltimore Gas and Electric Company (BGE) hereby requests an amendment to Operating Licenses Number DPR-53 and DPR-69 to add an analysis technique to the list of approved core operating limits analytical methods in the Technical Specifications for Calvert Cliffs Units 1 and 2. In Reference (a), BGE requested NRC approval to use the convolution technique for determining the values ir. the Core Operating Limits Report related to the pre-trip main steam line break event. The NRC approved the use in a Safety Evaluation attached to Reference (b). This amendment would add the convolution technique to the list of approved methodologies in Technical Specification 6.9.1.9.b. As noted above, the convolution technique is already approved, therefore this change is not technical in nature.
He proposed change to Section 6.9.1.9.b is shown in Attachments (2) and (3). He final Technical Specification pages will be renumbered to accommodate the insertion of this change. The same change will be made in the Core Operating Limits Report using the 10 CFR 50.59 process.
We have considered the possibility of significant hazards associated with this change and have determined that there are none (see Attachment I for a complete discussion). We have also determined that operation with the proposed amendment would not result in any significant change in the types or amounts of any I
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Document Control Desk December 7,1995 Page 2 -
effluents that may be released offsite, nor would it result in any significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR SI.22(c)(9). Pu suant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment is needed in connection with the proposed amendment.
'Ihese proposed changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations Safety Review Committee and Offsite Safety Resiew Committee, and they have concluded that implementation of these changes will not result in an undue risk to the health and safidy of the public.
This change is requested to be approved by May 15, 1996. No operation of the facility is dependent on approval.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, r am h
STATE OF MARYLAND :
- TO WIT:
COUNTY OF CALVERT :
I hereby certify that on the 9(1) day of . 19 5 befpre me, the subscriber, a Notary Public of the State of Maryland in and for CalAAAL) E/ . personally appeared Robert E. Denton, being duly sworn, and states that he is Vice President o%e Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, j information, and b: lief; and that he was authorized to provide the response on behalf of said Corporation. l WITNESS my Hand and Notarial Scal: l MWM b M i Notary Public My Commission Expires: b h Date RED /EMT/ dim Attachments: (1) Determination of Significant llazards (2) Marked-up Technical Specification Page - Unit 1 (3) Marked-up Technical Specification Page - Unit 2
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Dxument Control Desk l December 7,1995 l 1
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cc: D. A. Brune, Esquire J. E. Silberg, Esquire L. B. Marsh, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC Resident Inspector, NRC R. I. McLean, DNR J. H. Walter, PSC 1
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. DETERMINATION OF SIGNIFICANT IIAZARDS ne change has been evaluated against the standards in 10 CFR 50.92 and has been determined to not involve a significant hazards consideration in that operation of the facility in accordance with the proposed amendment:
- 1. Would not involve a sigmficant increase in the probability or consequences of an accidentpreviously evaluated.
The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, Baltimore Gas and Electric Company (BGE) requested approval to use the ABB/ Combustion Ergineering (ABB/CE) convolution technique for determining the values in the Calvert ClirTs Core Operating Limits Report (COLR) related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change does not involve a significant increase in the probability or consequences of an accident presiously evaluated.
- 2. Would not create the possibility ofa new or diferent type ofaccidentfrom any accident previously evaluated.
The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved meti.odologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, the change would not create the possibility of a new or different type of accident from any accident previously evaluated.
- 3. Would not involve a significant reduction in the margin ofsafety.
The proposed change is to add the convolution analysis technique previously approved by the NRC to the list of approved methodologies in Calvert Cliffs' Unit I and 2 Technical Specifications. By letter dated November 1,1994, BGE requested approval to use the ABB/CE convolution technique for determining the values in the Calvert Cliffs COLR related to the pre-trip main steam line break event. Approval was given by the NRC in their letter dated May 11,1995. The addition of this technique to the list of approved analytical methods in Technical Specification 6.9.1.9.b is simply intended to identify it as an approved methodology. Therefore, operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety.
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'j 6-22 Baltimore Gas and Electric Company December 7,1995