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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210L1501999-08-0404 August 1999 Application for Amends to Licenses NPF-4 & NPF-7,ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification Time ML20206N3601999-05-0606 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels ML20206G8271999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,deleting &/Or Relocating Addl primary-to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206G8641999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20195J4351998-11-18018 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9291998-11-10010 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising TSs to Clarify Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20236U8571998-07-28028 July 1998 Application for Amend to Licenses NPF-04 & NPF-07,revising TS 3/4.1.2 Re RWST & Boron Concentration Ph Range Bases Change ML20236U8611998-07-28028 July 1998 Application for Amend to Licenses NPF-4 & NPF-7,revising EDG Section to Be Consistent W/Station Procedures Associated W/ Steady State Conditions & W Nuclear Safety Advisory Ltr,Nsal 93-022 ML20236U8261998-07-28028 July 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML18153A2891998-03-25025 March 1998 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Station Mgt Titles to Reflect New Positions Approved by Vepc Power Board of Directors on 980220 ML20217E8931998-03-25025 March 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Frequency of EDGs & Establishing Configuration Risk Mgt Program to Support Risk Informed Tech Specs ML20202C5621998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Requirements & Frequency for RCP Flywheels & Eliminating Insp Requirements for Unit 1,reactor Coolant Flow Straighteners ML20202C3281998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199H3661997-11-18018 November 1997 Application for Amends to Licenses NPF-4 & NPF-7,permitting Quarterly Testing of Turbine Governor & Throttle Valves. Non-proprietary Tr,Rev 1 to WCAP-14733 & Proprietary Tr,Rev 1 to WCAP-14732,encl.Proprietary Rept Withheld ML20199A1411997-11-0505 November 1997 Application for Amends to Licenses NPF-4 & NPF-7, Respectively.Amends Will Provide Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3691997-05-14014 May 1997 Application for Amends to Licenses NPF-4 & NPF-7,revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided in TS 3/4.7.1.7 ML20132E6091996-12-17017 December 1996 Application for Amends to Licenses NPF-4 & NPF-7,requesting Temporary Changes to Service Water Sys Piping Repair and Refurbishment ML18153A6331996-11-26026 November 1996 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,respectively,eliminating Records Retention Requirements Section of Ts,Per GL 95-06 & Adminstrative Ltr 95-06 ML20134H0001996-11-0606 November 1996 Application for Amends to Licenses NPF-4 & NPF-7,modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20107L3881996-04-25025 April 1996 Application for Amends to Licenses NPF-4 & NPF-7,providing Suppl Info That Clarifies TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101F7891996-03-21021 March 1996 Application for Amends to Licenses NPF-4 & NPF-7,clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguard Area Ventilation Sys ML20097C0001996-01-31031 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy SR Required in Shutdown ML20097J4281996-01-30030 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Modifying Table 3.2.-1 TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9811996-01-23023 January 1996 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML20094N7881995-11-20020 November 1995 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0131995-10-25025 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5851995-10-17017 October 1995 Application for Amend to License NPF-7,modifying Table 4.4-1 of TS 4.4.5.1 to Reduce from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6011995-10-17017 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,modifying TS to Allow Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4171995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J2951995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2421995-09-0101 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087G3421995-03-30030 March 1995 Application for Amends to Licenses NPF-4 & NPF-7, Re Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operation in Order to Refurbish Isolated Svc Water Headers ML20080Q5421995-03-0202 March 1995 Application for Amends to Licenses NPF-4 & NPF-7,changing TS Associated W/Type a Testing Requirements Specified in App J to 10CFR50 ML20080B6801994-11-29029 November 1994 Application for Amends to Licenses NPF-4 & NPF-7,updating Environ Protection Plans to Reflect Current Obligations to Commonwealth of VA & Revise Portions of Transmission Corridor rights-of-way Erosion Control Program ML20076L5751994-10-25025 October 1994 Application for Amends to Licenses NPF-4 & NPF-7,extending Functional Surveillance Testing Frequency for Hydrogen Recombiners from Once Per 6 Months to Once Per 18 Months ML20069P3851994-06-16016 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,revising TS Re Removal of Unnecessary EDG Surveillance Requirements,Per GL 93-05 ML20069K2371994-06-0909 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,relocating TS Tables of Response Time Limits for RTS & ESFAS from TS to Station Controlled Documents,Per GL 93-08 ML20065K0981994-04-15015 April 1994 Application for Amends to Licenses NPF-4 & NPF-7,modifying P/T Operating Limitations During Heatup & Cooldown & LTOP Sys Pressure Setpoints & Enabling Temps for Units 1 & 2. Nonproprietary Westinghouse Rept WCAP-13831,Rev 1 Encl ML20065E1531994-03-30030 March 1994 Application for Amends to NPF-4 & NPF-7,revising High Head Safety Injection Flow Balance Surveillance Requirements by Removing Specific Numerical Values & Replacing W/Broader Requirement to Ensure HHSI Rate Meet LOCA Criteria ML20064F9681994-03-0909 March 1994 Correction to 930716 Proposed TS Change,Modifying TS to Conform W/Recent Changes to 10CFR20,correcting Administrative Error on TS Bases Page B 3/4 7-7 for Unit 2 as Issued by Amend 159 to License NPF-7 on 940217 ML20064C1531994-03-0101 March 1994 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Unnecessary EDG Surveillance Requirements in Accordance W/Gl 93-05 & NUREG-1366 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML20058M0581993-12-10010 December 1993 Application for Amends to Licenses NPF-4 & NPF-7,modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 ML20058C4491993-11-19019 November 1993 Application for Amend to Licenses NPF-4 & NPF-7,allowing Use of Solid Rods or Zirconium Alloy or Stainless Steel Filler Rods to Replace Fuel Rods Which Have Been Identified as Failed & Deleting Individual Fuel Rod U Weight Limit ML20059K1271993-11-10010 November 1993 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Simulated Reactor Coolant Pump Seal Injection Flow Requirement for Flow Balancing of High Head Safety Injection Lines ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML20045G7591993-07-0808 July 1993 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Deleting Requirement to Periodically Review Certain Administrative & Technical Procedures ML20045G6831993-07-0202 July 1993 Application for Amends to Licenses NPF-4 & NPF-7 Modifying Table 4.4-1 of TS 4.4.5.1 to Reduce Minimum Number of SGs Required to Be Opened for Insp During First Insp (I.E.,Refueling Outage)Following SG Replacement 1999-08-04
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210L1501999-08-0404 August 1999 Application for Amends to Licenses NPF-4 & NPF-7,ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification Time ML20206N3601999-05-0606 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels ML20206G8271999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,deleting &/Or Relocating Addl primary-to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206G8641999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20195J4351998-11-18018 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9291998-11-10010 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising TSs to Clarify Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20236U8611998-07-28028 July 1998 Application for Amend to Licenses NPF-4 & NPF-7,revising EDG Section to Be Consistent W/Station Procedures Associated W/ Steady State Conditions & W Nuclear Safety Advisory Ltr,Nsal 93-022 ML20236U8571998-07-28028 July 1998 Application for Amend to Licenses NPF-04 & NPF-07,revising TS 3/4.1.2 Re RWST & Boron Concentration Ph Range Bases Change ML20236U8261998-07-28028 July 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20217E8931998-03-25025 March 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Frequency of EDGs & Establishing Configuration Risk Mgt Program to Support Risk Informed Tech Specs ML18153A2891998-03-25025 March 1998 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Station Mgt Titles to Reflect New Positions Approved by Vepc Power Board of Directors on 980220 ML20202C3281998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Testing Requirements for Reactor Trip Bypass Breaker ML20202C5621998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Requirements & Frequency for RCP Flywheels & Eliminating Insp Requirements for Unit 1,reactor Coolant Flow Straighteners ML20199H3661997-11-18018 November 1997 Application for Amends to Licenses NPF-4 & NPF-7,permitting Quarterly Testing of Turbine Governor & Throttle Valves. Non-proprietary Tr,Rev 1 to WCAP-14733 & Proprietary Tr,Rev 1 to WCAP-14732,encl.Proprietary Rept Withheld ML20199A1411997-11-0505 November 1997 Application for Amends to Licenses NPF-4 & NPF-7, Respectively.Amends Will Provide Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20149F1201997-07-17017 July 1997 Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively, Addressing Proposed Temporary (Limit by Time Duration) TS Changes for Svc Water Sys Refurbishment ML20141F3691997-05-14014 May 1997 Application for Amends to Licenses NPF-4 & NPF-7,revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided in TS 3/4.7.1.7 ML20132E6091996-12-17017 December 1996 Application for Amends to Licenses NPF-4 & NPF-7,requesting Temporary Changes to Service Water Sys Piping Repair and Refurbishment ML18153A6331996-11-26026 November 1996 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,respectively,eliminating Records Retention Requirements Section of Ts,Per GL 95-06 & Adminstrative Ltr 95-06 ML20134H0001996-11-0606 November 1996 Application for Amends to Licenses NPF-4 & NPF-7,modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20107L3881996-04-25025 April 1996 Application for Amends to Licenses NPF-4 & NPF-7,providing Suppl Info That Clarifies TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101F7891996-03-21021 March 1996 Application for Amends to Licenses NPF-4 & NPF-7,clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguard Area Ventilation Sys ML20097C0001996-01-31031 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy SR Required in Shutdown ML20097J4281996-01-30030 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Modifying Table 3.2.-1 TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9811996-01-23023 January 1996 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML20094N7881995-11-20020 November 1995 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0131995-10-25025 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K6011995-10-17017 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,modifying TS to Allow Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20093K5851995-10-17017 October 1995 Application for Amend to License NPF-7,modifying Table 4.4-1 of TS 4.4.5.1 to Reduce from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20092J4171995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J2951995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2421995-09-0101 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087G3421995-03-30030 March 1995 Application for Amends to Licenses NPF-4 & NPF-7, Re Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operation in Order to Refurbish Isolated Svc Water Headers ML20080Q5421995-03-0202 March 1995 Application for Amends to Licenses NPF-4 & NPF-7,changing TS Associated W/Type a Testing Requirements Specified in App J to 10CFR50 ML20080B6801994-11-29029 November 1994 Application for Amends to Licenses NPF-4 & NPF-7,updating Environ Protection Plans to Reflect Current Obligations to Commonwealth of VA & Revise Portions of Transmission Corridor rights-of-way Erosion Control Program ML20076L5751994-10-25025 October 1994 Application for Amends to Licenses NPF-4 & NPF-7,extending Functional Surveillance Testing Frequency for Hydrogen Recombiners from Once Per 6 Months to Once Per 18 Months ML20069P3851994-06-16016 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,revising TS Re Removal of Unnecessary EDG Surveillance Requirements,Per GL 93-05 ML20069K2371994-06-0909 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,relocating TS Tables of Response Time Limits for RTS & ESFAS from TS to Station Controlled Documents,Per GL 93-08 ML20065K0981994-04-15015 April 1994 Application for Amends to Licenses NPF-4 & NPF-7,modifying P/T Operating Limitations During Heatup & Cooldown & LTOP Sys Pressure Setpoints & Enabling Temps for Units 1 & 2. Nonproprietary Westinghouse Rept WCAP-13831,Rev 1 Encl ML20065E1531994-03-30030 March 1994 Application for Amends to NPF-4 & NPF-7,revising High Head Safety Injection Flow Balance Surveillance Requirements by Removing Specific Numerical Values & Replacing W/Broader Requirement to Ensure HHSI Rate Meet LOCA Criteria ML20064F9681994-03-0909 March 1994 Correction to 930716 Proposed TS Change,Modifying TS to Conform W/Recent Changes to 10CFR20,correcting Administrative Error on TS Bases Page B 3/4 7-7 for Unit 2 as Issued by Amend 159 to License NPF-7 on 940217 ML20064C1531994-03-0101 March 1994 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Unnecessary EDG Surveillance Requirements in Accordance W/Gl 93-05 & NUREG-1366 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML20058M0581993-12-10010 December 1993 Application for Amends to Licenses NPF-4 & NPF-7,modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 ML20058C4491993-11-19019 November 1993 Application for Amend to Licenses NPF-4 & NPF-7,allowing Use of Solid Rods or Zirconium Alloy or Stainless Steel Filler Rods to Replace Fuel Rods Which Have Been Identified as Failed & Deleting Individual Fuel Rod U Weight Limit ML20059K1271993-11-10010 November 1993 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Simulated Reactor Coolant Pump Seal Injection Flow Requirement for Flow Balancing of High Head Safety Injection Lines ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML20045G7591993-07-0808 July 1993 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Deleting Requirement to Periodically Review Certain Administrative & Technical Procedures 1999-08-04
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VIRGINIA ELECTRIC AND POWER COMPANY RxcunoNn, VIRGINIA 202G1 W.L.STEWANT woe [.""[.'"1 oi . July 6, 1983 Mr. Harold R. Denton, Director Serial No. 726D Office of Nuclear Reactor Regulation GLD/RWC:brh:0555C rtn: Mr. Robert A. Clark, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:
SUPPLEMENT TO AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNIT NOS.1 AND 2 REACTOR COOLANT SYSTEM TEMPERATURE OF 587.8vF In our letter dated December 30,1982 (Serial No. 726), Vepco requested an amendment to Operating Licenses NPF-4 and NPF-7 to allow operation of North Anna Unit Nos. I and 2 at a reactor coolant system average temperature of 587.80F This letter provides in Attachment 1 supplemental infomation in answer to questions discussed with members of the Staff's Reactor Systems Branch on April 27, 1983 and June 21, 1983.
Should you have any further questions, please contact us at your earliest convenience.
_Very truly yours, 8307120356 830706 , ,
PDR ADOCK 05000338 W. L. Stewart P PDR Attachment (1) Response to Reactor Systems Branch for North Anna Operation at RCS Average Temperature of 587.80F cc: Mr. James P. O'Reilly Mr. Charlie Price Regional Administrator Department of Health Region II 109 Governor Street Richmond, Va. 23219 l
Mr. Richard Barrett i Reactor Systems Branch 00 Mr. M. B. Shymfock
, NRC Resident Inspector l \
l North Anna Power Station
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- RESPONSE TO REACTOR SYSTEMS BRANCH
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! AT RCS AVERAGE TEMPERATURE OF 587.8 F i
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l ATTACHMENT 1 RESPONSE TO NRC REACTOR SYSTEMS BRANCH QUESTIONS .
ON NORTH ANNA 7.50F UPRATING SUBMITTAL NSSS TRANSIENT ANALYSES Q1. Loss of Normal Feedwater (FSAR p.15.2-50, UFSAR p.15.2-40)
Assumption 4 in the existing FSAR states that the following was used in the calculation:
"A heat transfer coefficient in the steam generator associated with reactor coolant system natural circulation."
Why did the uprating submittal delete this assumption?
A1. The original FSAR analysis assumed a loss of offsite power occurred simula-taneously with the loss of normal feedwater, so the SG heat transfer co-efficient used was one appropriate for natural circulation conditions. A later reanalysis in response to an NRC question assumed offsite power was available. The 7.5 F0 uprating analysis employed current methodology, which is to analyze the loss of feedwater with and without offsite power available.
In each case, the SG heat transfer coefficient is calculated as a function of local SG conditions.
Q2. Loss of Normal Feedwater (FSAR p.15.2-52, UFSAR p.15.2 41)
The FSAR states that at no time during the transient does the water level in the steam generators receiving auxiliary feedwater uncover the tubesheet and there is no water relief from the pressurizer. There are figures of pressurizer and steam generator water level response in the FSAR, but no steam generator water level figure in the uprating submittal. What happens to SG water level during the transient?
A2. The loss of normal feedwater accident analyzed for the FSAR was simulated using the BLK0VT Code (Ref. WCAP-7501). The digital program computes pertinent variables including the SG level, pressurizer water level, ar.d reactor coolant average temperature; however, for the 7.50F uprating analysis, the LOFTRAN code (Ref. WCAP-7378, Rev. 3) was used to simulate the loss of normal feedwater accident. The LOFT 4 digital program computes pertinent variables including the steam generator mass versus time, pressurizer water volume, and reactor coolant average temperature. The capacity 0.f the auxiliary feedwater pumps are such that the water level in the fed steam generators _does not recede below the lowest level at which sufficient heat transfer area is available to dissipate core residual heat without water relief from the reactor coolant system relief or safety valves.
Q3. Excessive Load Increase (FSAR Fig.15.2-33, UFSAR Fig.15.2-46)
The existing UFSAR results (Fig.15.2-46) for an excessive load increase at BOL without automatic rod control show the nuclear power increasing from 1.02 to approximately 1.08 times nominal. Explain the difference between this and the uprating analysis, in which the power increases from 1.02 to 1.05 times nominal.
A3. The UFSAR analysis was performed by changing only the moderator density coefficient in the BOL and EOL cases. Current methodology analyzes the excessive load increase event for minimum and maximum reactivity feedback conditions. This requires minimum feedback values for the Doppler tempera-ture coefficient, the Doppler power defect, beta and lambda star; in addi-tion to the moderator density coefficient. Using these minimum reactivity feedback coefficients yields a lower steady state power level than that predicted in the UFSAR.
. Attached are revised FSAR Figures 15.2-33, -34, -35, 37, -38, -39, and
-40, and Table 15.2-1 which have been relabeled to reflect the minimum and maximum feedback conditions included in the 7.50F reanalyses.
Q4. Accidental Depressurization of the Main Steam System The uprating submittal includes neither a reanalysis of this event, nor a statement explaining why it was not reanalyzed.
A4. In FSAR Section 15.2.13, the existing analysis of this event assumes a steam release equal to the maximum capacity of any single steam dump or safety valve. The transient is assumed to be initfated at no load plant -
conditions, which are unchanged by the proposed 7.5 F increase in RCS average temperature. It is typically analyzed as a special case of the main steamline break accident, which is listed as one of the zero power transients requiring no reanalysis at the uprated conditions (enclosure 1, Page 14 of 7.50F uprating submittal).
QS. Main Feedline Rupture (proposed Fig.15.4.2-7A, 7B)
Why are the results of the uprating analysis (Figs.15.4.2-7A, 7B), e.g.,
pressurizer pressure and cors average temperature, less severe than the existing FSAR results (UFSAR Figs. 15.4-30,31)?
A5. The change in the florth Anna feedwater system from a headered (which was assumed in the FSAR analysis) to a one-on-one arrangement.(which was assumed in the '
-7.50F uprating analysis) is the major reason for the reduced severity of the main _feedline rupture results.
! Also, the results presented in F5AR are calculated using the MARVEL code, I whereas the results presented in the 7.50 F uprating analysis are italculated by the LOFTRAN code, using assumptions consistent with the Westinghouse Feedline Break topical WCAP-9230.
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