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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARNOC-AE-000672, Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in1999-10-20020 October 1999 Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in NOC-AE-000651, Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl1999-09-30030 September 1999 Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl NOC-AE-000630, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR NOC-AE-000629, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements NOC-AE-000601, Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR1999-08-24024 August 1999 Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR NOC-AE-000521, Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology1999-08-18018 August 1999 Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology NOC-AE-000564, Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl1999-07-15015 July 1999 Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl NOC-AE-000551, Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-07-13013 July 1999 Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000578, Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan1999-07-0101 July 1999 Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan NOC-AE-000569, Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR1999-06-24024 June 1999 Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR NOC-AE-000465, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables NOC-AE-000471, Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR NOC-AE-000513, Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys1999-04-22022 April 1999 Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys NOC-AE-000367, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-14311999-03-30030 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 NOC-AE-000462, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves1999-03-22022 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves NOC-AE-000396, Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM1999-03-15015 March 1999 Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM NOC-AE-000450, Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-03-0202 March 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000241, Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included1999-01-26026 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included NOC-AE-000264, Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants1999-01-20020 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants NOC-AE-000335, Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-14311998-11-23023 November 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-1431 NOC-AE-000262, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM NOC-AE-000261, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM NOC-AE-000263, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM NOC-AE-0140, Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar1998-09-30030 September 1998 Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar NOC-AE-0162, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria1998-09-30030 September 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria NOC-AE-0231, Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached1998-09-29029 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached ML20154A4121998-09-28028 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,changing TS to Mod Requirements Associated with Control Room & Fuel Handling Building Ventilation Sys.Proposed TS Pages Encl NOC-AE-00203, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys1998-08-31031 August 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys NOC-AE-000280, Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code1998-08-28028 August 1998 Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code NOC-AE-00151, Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR1998-07-28028 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR NOC-AE-0163, Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences1998-07-22022 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences NOC-AE-000178, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs1998-07-0707 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3441998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate TS 3/4.7.13 Requirements for Area Temperature Monitoring Sys to Technical Requirements Manual.Affidavit, SE & Determination of NSHC & marked-up TS Pages Encl NOC-AE-00187, Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR NOC-AE-00020, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20249B5411998-06-16016 June 1998 Application for Transfers of Control Re OLs NPF-76 & NPF-80, Requesting Consent of NRC to Indirect Transfers of Control of Interests That Will Occur Under Proposed Merger of Aep & Central & Southwest Corp NOC-AE-0080, Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences1998-05-0707 May 1998 Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences NOC-AE-000097, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-051998-04-0202 April 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-05 NOC-AE-0074, Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections1998-02-16016 February 1998 Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections NOC-AE-000050, Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary1997-12-31031 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary NOC-AE-000042, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes1997-12-17017 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes ST-HL-AE-5743, Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate1997-09-0404 September 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ST-HL-AE-5689, Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 21997-08-18018 August 1997 Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 2 ST-HL-AE-5623, Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging1997-08-14014 August 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging ST-HL-AE-5675, Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-14311997-07-22022 July 1997 Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431 ST-HL-AE-5640, Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization1997-05-29029 May 1997 Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization ST-HL-AE-5622, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods1997-04-22022 April 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods ST-HL-AE-5550, Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes1997-03-17017 March 1997 Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes ST-HL-AE-5547, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR1997-01-28028 January 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR ST-HL-AE-5491, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys1996-10-23023 October 1996 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys 1999-09-08
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARNOC-AE-000672, Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in1999-10-20020 October 1999 Suppl 1 to 990930 Application for Amend to Licenses NPF-60 & NPF-80,reflecting Replacement SG Rc Flow Differences.Encl Notarized Affidavit Page Replaces Affidavit Page Originally Transmitted in NOC-AE-000651, Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl1999-09-30030 September 1999 Suppl to 980507 Application for Amends to Licenses NPF-76 & NPF-80,to Remove Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow. Ts,With Changes,To Demonstrate Intended Affect,Encl NOC-AE-000630, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3/4.8.1,by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 8.3.1.1.4.8 of UFSAR NOC-AE-000629, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements1999-09-0808 September 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements NOC-AE-000601, Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR1999-08-24024 August 1999 Suppl 2 to Application for Amends to Licenses NPF-76 & NPF-80,relocating Cycle Specific Operating Parameters from TSs to COLR NOC-AE-000521, Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology1999-08-18018 August 1999 Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology NOC-AE-000564, Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl1999-07-15015 July 1999 Suppl to 990322 Amends to Licenses NPF-76 & NPF-80,revising TS 3.7.1.6, Atmospheric Steam Relief Valves. Replacement Proposed TS Encl NOC-AE-000551, Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-07-13013 July 1999 Suppl to Proposed Amend to Licenses NPF-76 & NPF-80, Clarifying Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000578, Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan1999-07-0101 July 1999 Application for Amend to License NPF-80 to Change TSs 3.3.2 & 3.7.8 to Allow All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period Not to Exceed 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan NOC-AE-000569, Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR1999-06-24024 June 1999 Suppl to 990607 Application for Amends to Licenses NPF-56 & NPF-80,relocating cycle-specific Operating Parameters from TS to Colr.Suppl Adds Min Measured RCS Flow to TS Section 6.9.1.9.a Which Lists Parameters Included in COLR NOC-AE-000465, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1 & 3.3.2 & Associated Bases.Amend Would Delete Total Allowance,Sensor Error & Z Terms from ESFAS & Reactor Trip Sys Instrumentation Trip Setpoints Tables NOC-AE-000471, Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR1999-06-0707 June 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating cycle-specific RCS-related TS Parameter Limits to COLR NOC-AE-000513, Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys1999-04-22022 April 1999 Suppl to Application for Amends to Licenses NPF-76 & NPF-80, Changing Tech Specs to Modify Requirements Associated with CR & Fuel Handling Bldg Ventilation Sys NOC-AE-000367, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-14311999-03-30030 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 NOC-AE-000462, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves1999-03-22022 March 1999 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves NOC-AE-000396, Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM1999-03-15015 March 1999 Supplemental Application for Amends to Licenses NPF-76 & NPF-80,relocating TS 3/4.7.9 for Snubbers to TRM NOC-AE-000450, Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B1999-03-0202 March 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration in TS 3.6.3 Action B NOC-AE-000241, Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included1999-01-26026 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,proposing Rev to TS 4.4.10 for Alternate ISI of RCP Flywheels.Se,Nshc Determination & TS Page 3/4 4-39,included NOC-AE-000264, Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants1999-01-20020 January 1999 Application for Amends to Licenses NPF-76 & NPF-80,revising Descriptive Details of TS Surveillance Requirement 4.7.1.2.1.a Re Performance Testing of AFW Pumps to More Closely Adhere to NUREG-1431,ISTS for W Plants NOC-AE-000335, Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-14311998-11-23023 November 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section,Per NUREG-1431 NOC-AE-000262, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amends Would Relocate Snubber TS 3/4.7.9 to TRM NOC-AE-000261, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Proposed Amend Would Relocate Portions of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM NOC-AE-000263, Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM1998-10-29029 October 1998 Application for Amends to Licenses NPF-76 & NPF-80, Respectively.Amend Would Relocate Turbine Overspeed Protective TS 3/4.3.4 to TRM NOC-AE-0140, Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar1998-09-30030 September 1998 Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar NOC-AE-0162, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria1998-09-30030 September 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria NOC-AE-0231, Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached1998-09-29029 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,allowing Use of Revised Methodology to Calculate Mass & Energy Release Following Postulated Large Loca.Proposed Changes to Units 1 & 2 UFSAR Attached ML20154A4121998-09-28028 September 1998 Application for Amends to Licenses NPF-76 & NPF-80,changing TS to Mod Requirements Associated with Control Room & Fuel Handling Building Ventilation Sys.Proposed TS Pages Encl NOC-AE-00203, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys1998-08-31031 August 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Changes to Reflect Revised Cold Overpressure Mitigation Curve Associated W/Replacement SGs Into TS 3.4.9.3, Overpressure Protection Sys NOC-AE-000280, Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code1998-08-28028 August 1998 Application for Exigent Amends to Licenses NPF-76 & NPF-80, Excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code NOC-AE-00151, Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR1998-07-28028 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Addressing Operator Action to Be Used in Event of Small Break Loca.W/Affidavit,Safety Evaluation,No Significant Hazards Determination & Revised Updated FSAR NOC-AE-0163, Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences1998-07-22022 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Replacing SG Water Level Trip Setpoint Differences NOC-AE-000178, Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs1998-07-0707 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3441998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80,to Relocate TS 3/4.7.13 Requirements for Area Temperature Monitoring Sys to Technical Requirements Manual.Affidavit, SE & Determination of NSHC & marked-up TS Pages Encl NOC-AE-00020, Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating TS 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual NOC-AE-00187, Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR1998-07-0606 July 1998 Application for Amends to Licenses NPF-76 & NPF-80, Relocating RCS Design Features from TS 5.4 to UFSAR ML20249B5411998-06-16016 June 1998 Application for Transfers of Control Re OLs NPF-76 & NPF-80, Requesting Consent of NRC to Indirect Transfers of Control of Interests That Will Occur Under Proposed Merger of Aep & Central & Southwest Corp NOC-AE-0080, Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences1998-05-0707 May 1998 Application for Amends to Licenses NPF-76 & NPF-80 to Reflect Replacement SG Reactor Coolant Flow Differences NOC-AE-000097, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-051998-04-0202 April 1998 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Tech Specs 3.4.5 Re 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections,Per GL 95-05 NOC-AE-0074, Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections1998-02-16016 February 1998 Application for Amend to License NPF-80,incorporating Attached Amend to TS 3.4.5.Amend Will Implement 1-volt voltage-based Repair Criteria for SG Tube Support plate-to- Tube Intersections NOC-AE-000050, Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary1997-12-31031 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS Sections 2.1,2.2 & 3/4.2.5 by Including Alternate Operating Criteria to Allow Continued Plant Operation W/ Reduced Measured RCS Flow Rate If Necessary NOC-AE-000042, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes1997-12-17017 December 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years. W/Ser & Proposed TS Changes ST-HL-AE-5743, Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate1997-09-0404 September 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS to Allow Elbow Tap Differential Pressure Measurements to Be Used Instead of Precision Heat Balance Measurements to Determine RCS Total Flow Rate ST-HL-AE-5689, Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 21997-08-18018 August 1997 Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 2 ST-HL-AE-5623, Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging1997-08-14014 August 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Allowed Tolerance of RCS Volume Provided in TS 5.4.2 to Account for SG Tube Plugging ST-HL-AE-5675, Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-14311997-07-22022 July 1997 Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431 ST-HL-AE-5640, Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization1997-05-29029 May 1997 Submits Supplemental Info in Support of 960815 License Amend Request Re Removal of Surveillance Requirement 4.7.7.e.5. Supplement Provides Administrative Changes to Affected Page of TSs to Ensure Consistent Punctuation & Organization ST-HL-AE-5622, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods1997-04-22022 April 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Specs 5.3.1, Fuel Assemblies & 6.9.1.6, COLR, to Allow Use of Alternate zirconium-based Fuel Cladding,Zirlo & Limited Substitution of Fuel Rods by ZIRLO Filter Rods ST-HL-AE-5550, Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes1997-03-17017 March 1997 Application for Amends to Licenses NPF-76 & NPF-80,amending Tech Specs 3/4.4.5 & 3.4.6.2 to Allow Installation of Laser Welded Tube Sleeves as Alternative to Plugging Defective SG Tubes ST-HL-AE-5547, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR1997-01-28028 January 1997 Application for Amends to Licenses NPF-76 & NPF-80,revising TS 6.2.3 to Remove Reference to Independent Safety Engineering Group (Iseg) & Relocate All Details and Functions of Iseg to UFSAR ST-HL-AE-5491, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys1996-10-23023 October 1996 Application for Amends to Licenses NPF-76 & NPF-80, Incorporating Proposed Change to TS 3.4.6.1, Reactor Coolant Leakage Detection Sys 1999-09-08
[Table view] |
Text
. _ . . .
The Light c o mp a ny """ ***' "d*" '"'""*"E**'" "" "" "'"""' ""' "
Houston Lighting & Power November 30, 1993 ST-HL-AE-4599 File No.: G9.06 ;
10CFR20 10CFR50.90 i
U. S. Nuclear Regulatory Commission Attention: Document Control Desk ;
Mashington, DC 20555 South Texas Project >
Units 1 and 2 Docket Nos. STN 50-498: STN 50-499 Revision 1 to Proposed Amendment to the .
Unit 1 and Unit 2 Technical Specifications For Implementing the New Requirements -
j of 10CFR20 (TAC Nos. MR7735/87736)
Reference:
Letter from Houston Lighting & Power (ST-HL-AE-4566) dated September 15, 1993 to U. S.
NRC Document Control Desk.
Houston 1.Ighting & Power Company (HL&P) submitted a proposed amendment to Facility Operating Licenses Nos. NPF-76 and NPF-80 f or South Texas Project Units 1 and 2 in the referenced letter. The purpose of the proposed amendment was to implement the new i requirements of 10CFR20.
Based on subsequent discussions wi*h the NRC, HL&P is :
submitting the attached revision. The changes from the original submittal are generally editorial in nature and are indicated by revisitc bars in the margin.
Attachment 1 ir an affidavit. Attachment 2 is the Safety :
Evaluation and No Significant Hazards Consideration Detcrmination. I Attachment 3 is a copy of the current Technical Specifications :
marked with the proposed changes. j HL&P is scheduled to fully implement the requirements of the l new 10CFR20 on January 1, 1994. Therefore, HL&P requests that the )
proposed changes to the Technical Specifications be approved prior to January 1, 1994, but not be required to be implemented until I that date.
0700"1 9312090236 931130 h PDR ADOCK 05000498 3 P PM jj '
Project Manager on lichalf of the Participanta in the South Texas Project Tsc-03\93-295.001 1
i Houston Lighting & Power Company ST-HL-AE-4599 '{
South Texas Project Electric Generating Station File No.: G9.06 .
10CFR20 10CFR50.90 l Page 2 !
f HL&P has reviewed the attached proposed amendment pursuant to j 10CFR50.92 and determined that it does not involve a significant !
hazard consideration. The basis for this determination is provided in Attachment 2. In addition, HL&P has reviewed the proposed- .!'
changes against the criteria of 10CFR51.22 for' categorical ,
exclusion from environmental impact considerations. The proposed i changes do not involve a significant hazards consideration, or significantly increase the amounts or change the types of ef fluents 1 that may be released offsite, nor do they significantly increase d individual or cumulative occupational radiation exposure.
- Therefore, HL&P concludes that the proposed changes satisfy the -,
criteria given in 10CFR51.22 (c) (9) for categorical exc3usion from l the requirement for an Environmental Impact Statement.
In accordance with 10CFR50.91, HL&P is providing the State of Texas with a copy of this proposed amendment.
If you should have any questions on this matter, please l contact Mr. A. W. Harrison at (512) 972-7298. ;
, 1 AA/\ - j i F. G ot l
[icePresident, Juclear Generation :
1 1
i DNB/pa Attachments: 1. Affidavit
- 2. Safety Evaluation and No Significant Hazards Consideration Determination for Implementing the New Requirements of 10CFR20.
- 3. Proposed Changes to the Technical Specifications for Implementing the New Requirements of 10CFR20 t
l 750-93\93-295.001
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l Houston Lighting & Power Company ST-HL-AE-4599' !
South Texas Project Electric Generating Station - File No.: G9.06
? 10CFR20 ,
10CFR50.90 Page 3 c:
i i
Regional Administrator, Region IV Rufus S. Scott ;
U. S. Nuclear Regulatory Commission Associate General Counsel l 611 Ryan Plaza Drive, Suite 400 Houston Lighting & Power Company k Arlington, TX 76011 P. O. Box 61867 )
Houston, TX 77208 -!
Lawrence E. Kokajko Institute of Nuclear Power 'l Project Manager Operations - Records Center ~f U. S. Nuclear Regulatory Commission 700 Galleria Parkway !
Washington, DC' 20555 13H15 Atlanta, GA 30339-5957 j David P. Loveless Dr. Joseph M. Hendrie f Sr. Resident Inspector 50 Bellport Lane .I c/o U.S. Nuclear Regulatory Comm. Bellport, NY 11713 ;!
P. O. Box 910 f Bay City, TX 77404-910 4 J. ~R. Newman, Esquire D. K. Lacker !
I Newman & Holtzinger, P.C., STE 1000 Bureau of Radiation Control ~'
1615 L Street, N.W. Texas Department of Health washington, DC 20036 1100 West 49th Street i Austin, TX 78756-3189 i K. J. Fiedler/M. T. Hardt !
City Public Service P. O. Box 1771 San Antonio, TX 78296 ,
J. C. Lanier/M. B. Lee City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 G. E. Vaughn/T. M. Puckett Central Power and Light Company P. O. Box 2121 Corpus Christi, TX 78403 b
Tf,C 93\9b295.001
Attachment 1 ST-HL-AE-4599 [
Page 1 of 1 .
t l
UNITED STATES OF AMERICA {
NUCLEAR REGULATORY COMMISSION l In the Matter of )
)
Housten Lighting & Power ) Docket Nos. 50-498 Company, et al., ) 50-499 !
) ,
South Texas Project ) l Unit 1 and Unit 2 ) ;
AFFIDAVIT I, J. F. Groth, being duly sworn, hereby depose and say that I am ,
Vice Plesident, Nuclear Generation, of Houston Lighting & Power Company; that I am duly authorized to sign and file with the Nuclear Regulatory Commission the attached proposed changes to the South Texas Project i Electric Generating Station Technical Specifications for implementing the new requirements of 10CFR20; that I am familiar with the content thereof; !
and that the matters set forth therein are -ue and correct to the best of my knowledge and belief.
i k .w - ., !
J F. Groth ice President, :
Nuclear Generation i STATE OF TEYAS ) !
) I
)
a hTotary Public in and for the a State of subscribed Texas, this andjoVA sworn to day before of me,.
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ATTACHMENT 2 l i
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Safety Evaluation and No Significant Hazards Consideration Determination for )
Implementing the New Requirements of 10CFR20 ';
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J Attachment 2 ST-HL-AE-4599 l Page 1 of 11- l Safety Evaluation and No Significant Hazards l Consideration Determination for ,
Implementina the New Requirements of 10CFR20 1 l
)
Table of Contents i l
6 E
Backaround . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 i
i Descriotion of Proposed Chances . . . . . . . . . . . . . . . . . .2 j i
Safety Evaluation . . . . . . .. . . . . . . . . . . . . . . . . 4 l Environmental Impact Analysis . . . . . . . . . . . . . . . . . . 11 ,
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!- Attachment 2 l ST-HL-AE-4599 i Page 2 of 11 ;
i Backaround
'On May 21, 1991, the Nuclear Regulatory Commission (NRC) issued a !
revision to its standards for protection against' ionizing.
radiation, 10CFR20.
The purpose of the revision was to modify the Radiation Protection l Standards to reflect developments in the principles and scientific knowledge underlying radiation protection. In addition, the ;
revision addresses International Radiation Protection Standards in '
order to attain more consistency with the requirements of other nations. The revised 10CFR20 became effective on June 20, 1991 and requires implementation on or before January 1, 1994. Houston Lighting and Power, on behalf of South Texas Project Units 1 and 2, q
plans to implement the new 10CFR20 requirements on January 1,1994. l 1
l Descrir> tion of Proposed Chances In accordance with 10CFR50.90, the following changes to the South !
Texas Project Units 1 and 2 Technical Specifications are being i proposed to implement the new requirements of 10CFR20:
- 1. Technical Specification 1.18 MEMBERS OF THE PUBLIC, l Technical Specification 1.31 SITE BOUNDARY, and Technical l Specification 1.39 UNRESTRICTED AREA definitions were l ;
similar to those of 10CFR20.1003. The revised definitions correspond to the revised 10CFR20.1003. l
- 2. Technical Specification 3/4.11.1.4 Liquid Holdup Tanks for -l LCO 3.11.1.4 limits the quantity of radioactive material contained in each unprotected outdoor tank. No change to .
the Technical Specification is required. The basis for the
- Technical Specification has been edited to clarify the 10
, Curie limit. ,
4 I 3 3. Technical Specification 5.1.3 Map Defining UNRESTRICTED j AREAS and SITE BOUNDARY for Radioactive Gaseous and Liquid ,
i Effluents requires a change to remove reference _ to l ,
10CFR20.3 (a) (17) . Maps (Figures 5.1-1, 5.1-2, 5.1-3, l 5.1-4) were updated to make the notes more legible and to clarify the location of unrestricted, controlled- and restricted areas. ]
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. TSC- 9 3\ 914 % . 001
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Attachment 2 i ST-HL-AE-4599 t Page 3 of 11 ;
- 4. Technical Specification 6.8.3.g.2) defines the radioactive !
effluent control program limiting the concentration of :
radioactive material released in liquid effluents to [
UNRESTRICTED AREAS " conforming to 10CFR20, Appendix B, l Table II, Column 2." A change is required to change the j quoted section of the preceding sentence to " conforming to 1 10 times 10CFR20.1001-20.2401 Appendix B, Table 2, Column 2." i t
- 5. Technical Specification 6.8.3.g.3) defines the radioactive i effluent control program for monitoring, sampling, and i analysis of radioactive liquid and gaseous effluents. A >
change is required to change "10CFR20.106" to "10CFR20.1302".
4 i
- 6. Technical Specification 6.8.3.g.7) defines the radioactive effluent control program limiting the dose rate resulting >
from radioactive material released in gaseous effluents to ,
areas beyond the SITE BOUNDARY " conforming to the doses .
associated with 10CFR20, Appendix B, Table II, Column 1,". l A change is required to change the quoted section of the [
preceding sentence to: !
"shall be limited to the following: ]
s
. a. For noble gases: Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to i a dose rate of 3000 mrems/yr to the skin, and
- b. For Iodine-131, for Iodine-133, for . tritium, and for all I radionuclides in particulate form with half-lives i greater than 8 days: Less than or equal to a dose rate of 1500 mrems/yr to any organ, and 1
- 7. Technical Specification 6.9.1.2.a defines annual reports
- for tabulation of personnel receiving exposures greater
-than 100 mrem /yr. A note referencing 10CFR20.407 will be
, changed to reference 10CFR20.2206. The wording of Technical Specification 6.9.1.2.a was clarified by adding the phrases in boldface type. This is consistent with the requirements of 10CFR20.2206. -) i
[6.9.1.2)
- a. A tabulation on an annual basis of the number of station, utility, and other individuals, for whom monitoring was required, (including contractors),
receiving exposures greater than 100 mrem in one ;
calendar year and their associated man-rem exposure i !
I TSC-93\93-295,001
f
l Attachment 2 -!
ST-HL-AE-4599 Page 4 of 11
- 8. Records - Technical Specification 6.10.2.f was moved to 6.10.3.p. 10CFR20.2108 requires longer retention of records of disposal of licensed material. Technical Specification ,
6.10.3.c was edited to be consistent with the record :
keeping requirements of 10CFR20.2106. .
{6.10.3] j
- c. Records of doses received by all individuals for whom l monitoring was required; I
.i
- 9. Technical Specification 6.12 High Radiation Area requires l Technical Specification change to change measurement distances and 10CFR20 references. l
- 10. Technical Specification 6.14.a.2 references 10CFR20.106 and !
was changed to 10CFR20.1302. l l t
I safety Evaluation )
The proposed changes to the South Texas Project Technical Specifications are editorial changes that provide consistency ;
'between the Technical Specifications and the revised 10CFR20 or are l changes to the effluent limits cross referenced to the former 10CFR20 in the implementation of 10CFR50, Appendix I limits. ;
The basic requirements concerning effluents from nuclear power !
reactors are stated in 10CFR50.36a. These requirements indicate !
that compliance with effluent Technical Specifications will keep i average annual releases of radioactive material in effluents to !
small percentages of the limits specified in the former 10CFR20.106 ;
(revised 10CFR20.1301). The requirements further indicate that j operational flexibility is allowed, compatible with considerations l of health and safety, which may temporarily result in releases 4 higher than such small percentages, but still within the limits specified in l'0CFR20.106 which references Appendix B, Table II ;
concentrations (MPCs). The. limits correlate to an annual dose of s 500 mrem. 10CFR50.36a indicates that when using operational ,
flexibility, best efforts shall be exerted to keep levels of !
radioactive materials in effluents as low as is leasonably. j achievable (ALARA) as set forth in 10CFR50, Appendix I. !
1 The changes proposed to the South Texas Project Technical I Specification are consistent with the philosophy to keep dose to the public as low as is reasonably achievabie (ALARA) and below the limits set forth in 10CFR50, Appendix I.
i TSC P3\93 295.001 l
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Definitions - (Technical Specifications 1.18, 1.31, 1.39) r t
MEMBER OF THE PUBLIC, SITE BOUNDARY, and UNRESTRICTED AREA !
definitions were revised to correspond to 10CFR20.1003. l l
'l Liquid Waste Holdup Tanks - (Technical Specification 3.11.1.4) !
}
No change is proposed to the Technical Specification. The purpose i for the Technical Specification is to restrict the radioactivity j content such that an uncontrolled release of the tank's contents would not exceed the limits of 10CFR20, Appendix B, Table 2, Column 2 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. The Technical Specification bases i should indicate that limiting tank contents to 30 Curies is a conservative and more realistic limit than the concentration that l :
would exceed the limits of 10CFR20, Appendix B, Table 2, Column 2. l Section 15.7.3 of NUREG 0800 and Sections 2. 4.13. 3.2 and 15.7. 3 of the South Texas Project Updated Final Safety Analysis Report (UFSAR) indicate that the radioactive source term previously evaluated was approximately 10 Curies for an accidental tank
- rupture. The calculated concentrations offsite were below the .
Effluent Concentration (EC) Limits by several orders of magnitude. I The clarification to the bases of the Technical Specifications :
indicates that the total curie content is the limiting factor !
rather than concentration.
I Site Maps - (Technical Specification 5.1.3) f The description of the design features related to gaseous and i liquid effluents was edited and Figures 5.1-3 and 5.1-4 were revised and clarified to reflect the revised 10CFR20.1003 concepts I i of restricted, controlled and unrestricted areas. All areas within I the SITE BOUNDARY can be controlled, if necessary, for purposes of. ]
limiting dose to MEMBERS OF TEE PUBLIC. Figures 5.1-1 through 4 are ;
updated such that the notes are more legible. '
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i Liquid Effluents - (Technical Specification 6.8.3.g.2) i Current wording: " Limitations on the concentrations of radioactive '
material released in liquid effluents to UNRESTRICTED AREAS conforming to 10CFR20, Appendix B, Table II, Column 2."
Proposed wording: " Limitations on the concentrations of radioactive material released in liquid-effluents to UNRESTRICTED AREAS conforming to 10 times 10CFR20.1001-20.2401, Appendix B, ;
Table 2, Column 2."
The Introduction to Appendix B of the revised 10CFR20 indicates ;
that the liquid effluent concentration limits given in Appendix B, Table 2, Column 2, are based on an annual dose of 50 mrem. Under ;
the former 10CFR.20, effluent concentration limits (i.e.
unrestricted area MPCs) corresponded to a dose limit of 500 mrem in ;
a year for liquid effluents. Operational history at South Texas ;
Project has demonstrated that the use of the concentration values ,
associated with the former 10CFR20.106 as Technical Specification !
limits has resulted in calculated maximum individual doses to a member of the public that are small percentages of the requirements !
of 10CFR50, Appendix I. The effluent concentrations listed in the '
revised 10CFR20, Appendix B, Table 2, Column 2, correspond.to a -
dose of 50 mrem in a year. When applied as a dose rate, 50 mrem / year corresponds to a dose rate of 5.7 -microrem/hr. !'
Considering monitor background, sensitivity, and performance, it is impractical to base liquid effluent monitor setpoints on this low value for many liquid effluent release situations. The operational ;
flexibility needed for liquid effluent releases requires that l release rate limits be revised to allow ten times the concentrations stated in the revised 10CFR20, Appendix B, Table 2, Column 2.
if
. The factor of ten is based on the ratio of former annual dose limit '
of 500 mrem, to the revised annual dose limit of 50 mrem. The i i
proposed change provides operational flexibility consistent with '
10CFR50 Appendix I, concurrent with the implementation of the revised 10CFR20.
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f Effluent Monitoring - (Technical Specification 6.8.3.g.3) i Current wording: " Monitoring, sampling, and analysis of radioactive .
liquid and gaseous effluents in accordance with 10CFR20.106 and f with the methodology and parameters in the ODCM." [
t Proposed wording: " Monitoring, sampling, and analysis of I radioactive liquid and gaseous effluents in accordance with l 10CFR20.1302 and with the methodology and parameters in the ODCM." l The proposed change to Technical Specification 6.8.3.g.3 is purely !
editorial, correcting the ref erence section of 10CFR20 as necessary i f or consistency with other changes to the Technical Specifications. :
No changes in p;ograms or procedures are intended as a result of i
- this change. I t
4 Gaseous Effluents - (Technical Specification 6.8.3.g.7) {
Current wording: " Limitations on the dose rate resulting from r 4 radioactive material released in gaseous effluents to areas beyond
, the SITE BOUNDARY conforming to the doses associated with 10CFR20, !
Appendix B, Table II, Column 1." !
t Proposed wording: " Limitations on the dose rate resulting from !
radioactive material released in gaseous ef fluents from the site to l areas at or beyond the SITE BOUNDARY shall be limited to the ,
following: i i
- a. For noble gases: Less than or equal to a dose rate of 500 l mrems/yr to the total body and less than or equal to a dose. !
rate of 3000 mrems/yr to the skin, and j
- b. For Iodine-131, for Iodine-133, for tritium, and for all !
radionuclides in particulate form with half-lives greater-than 8 days: Less than or equal.to.a dose rate of ,1500 -
, mrems/yr to any organ, and"
'l Technical Specification 6.8.3.g.7 provides for a program to limit i the dose from gaseous effluents at anytime, at and beyond the site boundary, to within the annual dose limits for unrestricted areas as specified by 10CFR20. The current annual dose. limits are.the ,
doses associated with the concentrations in 10CFR20, Appendix B, Table II, Column 1 (10CFR20.106) and equate to 500 mrem in a year.
These limits on radioactive material discharged in gaseous '
effluents provide reasonable assurance that a member of the public
, in an unrestricted area, outside of the site boundary, would not be.
exposed to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10CFR20 (10CFR20.106(b)).
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Attachment 2 ST-HL-AE-4599 i Page 8 of 11 4 j Gaseous Effluents - (Technical Specification 6. 8.3.g.7) [ Cont'd]
The South Texas Project Offsite Dose Calculation Manual (ODCM)-
currently establishes release rate controls, at all times, to i restrict gamma and beta dose rates to a member of the public, at or beyond the site boundary, to less than or equal to 500 mrem / year to. ,
the whole body or to less than or equal to 3000 mrem / year to the l skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate via the inhalation pathway to less than or equal to 1500 mrem / year. These limits are consistent with the guidance provided in NUREG-0133, " Preparation of Radiological 1 Effluent Technical Specifications for Nuclear Power Plants.'" j t The dose rate controls in the ODCM ensure that licensees meet the !
10CFR50 Appendix I requirements. The proposed change does not ?
revise the dose rate controls identified in the Technical )
Specifications and implemented by the South Texas Project ODCM. The proposed change . deletes the reference to 10CFR20, Appendix B, I l 4
Table II and instead, explicitly identifies the dose rate controls. -l i
1 Annual Reports - (Technical Specification 6.9.1.2.a) !
'L s Technical Specification 6.9.1.2.a requires a report to be submitted annually which includes a tabulation oi individuals ~ receiving exposures greater than 100 mrem /yr and their associated man-rem {
exposure according to work and job functions. Since the revised !
10CFR20 only requires reporting for monitored individuals as i defined in 10CFR20.1502, Technical Specification 6.9.1.2.a is being ;
revised to clearly identify the individuals for whom tabulation in I the annual report is required. This is an administrative change !
which clarifies reporting requirements. This change does not alter South Texas Project requirements or responsibilities for protection of the public and employees against radiation hazards. The ]
footnote in this paragraph was edited to reference the revised !
criteria in 10CFR20.2206. 4 Records - (Technical Specification 6.10)
The retention period for records of disposal of licensed material changed from 5 years to the duration of the operating license as required by 10CFR20.2108, so Technical Specification 6.10 2.f was moved to 6.10.3.p. Technical Specification 6.10.3.c was edited to be consistent with the requirements of 10CFR20.2106.
l c. Records of " doses received by all individuals for whom monitoring was required";
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- High Radiation Area - (Technical Specification 6.12) l The revised 10CFR20 provides a new definition of a high radiation area which is based on a radiation level measurement made at 30 cm. '
Therefore, the measurement distance identified in Technical Specifications 6.12.1 and 6.12.2 are being changed from 18 inches '
to 30 cm (12 inches) to be consistent with 10CFR20.1601(a). This i represents a conservative change since 30 cm is a shorter distance i than 18 inches. Implementing this change will result in higher dose i
~
measurements and more conservative identification of high radiation areas. An upper limit of 500 Rad in one hour at one . meter was !
incorporated into this Technical Specification to specify an upper ,
bound to HIGH RADIATION AREA. The upper limit of 500 Rad in one hour at one meter denotes a boundary between HIGH RADIATION AREA and VERY HIGH RADIATION AREA. Posting and controls for-VERY HIGH .
RADIATION AREAS will be consistent with the requirements of 10CFR20.1602 and 10CFR20.1902(c) independent of the Technical !
Specifications. Other terminology changes are proposed in this j Technical Specification for consistency (i.e., Mr/h to mrem /h; i axposure to dose; personnel to individuals) . The phrase referencing !
the Health and Safety Services Manager was changed to health t physics supervision to eliminate an organizational title and .
preserve administrative control.
ODCM - (Technical Specification 6.14.a.2) I Technical Specification 6.14.a.2 has been edited to change the-reference to 10CFR20.106 to 10CFR20.1302. This change will maintain 1 consistency with the effluent limitations in both liquid -and !
gaseous effluents as was previously justified.
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1 Attachment 2 ST-HL-AE-4599 Page 10 of 11 4.0 No Sionificant Hazards Consideration Determination In accordance with 10CFR50.92, any proposed change to a Operating 3 License (Technical Specifications) must be evaluated for-significant hazards considerations. The operation of th2 facility :
in accordance with the proposed change shall not: {
- 1) involve a significant increase in the probability or )
consequences of any accident previously evaluated, or j The proposed revisions to the liquid and gaseous release ;
limits will not change the type or amount of effluent l released nor will there be an increase in individual or !
cumulative dose. The changes will result in levels of i
' radioactive materials in effluents being maintained ALARA l and comply with 10CFR50.36a and 10CFR50 Appendix I. The change to the high radiation area dose measurement distance will ensure that high radiation areas are conservatively posted per 10CFR20.1601 (a) (1) and provide controls to r minimize individual dose. The changes do not impact the operation or design of any plant structure, system or l component. Other proposed changes are administrative only. ,
Therefore, the proposed changes do not involve an increase in the probability or consequences of an accident previously evaluated.
- 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or !
4 The proposed changes do not affect the plant design or l operation nor do they result in a change to the configuration of any equipment. No change is proposed that will change the type or quantity of effluents released off site or change the source terms available for release.
Therefore, the proposed changes do not create .the possibility of a new or different kind of accident from any
- previously evaluated. ,
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- 3) involve a significant reduction in a margin of safety.
I l The proposed changes do not change the type or increase the amount of effluents released off site. No change in the
, methodology used to control radioactive . waste' or >
radiological environmental monitoring is proposed. Control-of radioactive effluents and effluent monitor setpoints will be based on current dose to the public limitations.
Under the proposed change, high radiation area measurements j are more conservative and will not result in an increase in individual or cumulative occupational radiation exposures. i Compliance with the limits of the revised 10CFR20.1301 will )
3 be demonstrated by operating within the limits of 10CFR50 Appendix I and 40CFR190. Therefore, these changes do not reduce the margin of safety.
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e Attachment 2 ST-HL-AE-4599 Page 11 of 11 ,
Based upon the foregoing, South Texas Project concludes that the do
- 1. proposed changes not involve a significant hazards
[ consideration.
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Environmental Impact Analysis ;
i The proposed changes to the South Texas Project Technical l Specifications have been reviewed against the criteria of ;
- 10CFR51,22 for environmental considerations. The proposed changes ;
do not involve a significant hazards consideration; nor increase l the types and amounts of effluents that may be released offsite; ,
nor increase the individual or cumulative occupational radiation !
I exposures. The prooosed effluent concentration limits requested :
j will allow the liquid and gaseous effluent release rates. to l j correspond to the current annual dose limits. Compliance with the ;
annual dose limits of the new 10CFR20.1301 will be demonstrated by
! operating within the requirements of 10CFR50 Appendix I and i 40CFR190. Therefore, the proposed Technical Specification changes
! meet the criteria given in 10CFR51. 22 (c) ( 9) for a categorical exclusion from the requirement for an Environmental Impact l j Statement.
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