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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 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 1999-08-04
[Table view] |
Text
i . .
a Ysito NIA I?titrTrilO AND I' owl lf COhil'ANY ltican>to w n Vinoix 4 unuoi June 8, 1992 U.S. Nuclear Regulatory Commission Serial No. 92 392 Attention: Document Control Desk NAPS /RMN Washington, D.C. 20555 Docket Nos. 50 338 50 339 License Nos. NPF 4 NPF 7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY RORTH ANNA POWER STATION UNITS 1 AND 2 EROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Yechnical Specifications, to Operating License Numbers NPF 4 and NPF 7 for North Anna Power Station Units 1 and 2, respectively. The proposed change will revise the-current Technical Specifications to permit staggered testing of the Reactor Trip System instrumentatien and to permit up to two hours to test cortain Emergency Safeguards Feature Actuation System instrumentation. Some minor administrative changes are also included.
A discussion of the proposed changes is provided in Attach 1ent 1. The proposed changes are presented in Attachment 2 for Units 1 -and 2, respectively.
This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee, it has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our determination that no signification hazards consideration is involved is presented in Attachment 3.
Should you have any questions or require additional information, please contact us at your earliest convenience, Very truly yours e Mf..
1 ,
W. L. Stewart j Senior Vice President - Nuclear 38- g p PDR
~
Attachments
- 1. Discussion of Proposed Changes
- 2. Proposed Technical Specification Change for North Anna Units 1 and 2
- 3. 10 CFR 50.92 Significant Hazards Consideration ec: U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
d COMMONWEALTHOFVIRGINIA )
)
COUN1YOFHENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L Stewart who is. Senior Vice Procldent - Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the doct. ment are true to the best of hic knowledge and belief.
Acknowledged before me this day of- . //A , - , 19 72.
My Commission Expires: fd/A o3 / , 19 3
]
Notary Public W
(SEAL) u l
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Discussion of Proposed Changes i
. North Anna Units.1'and 2 l
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a DISCUSSION OF PROPOSED CHANGES Introduction The proposed changes described herein are being made to Technical Specification 4.3.1.1.1, " Reactor Trip System Insrumentation," Table 4.31, item 19 and Technical Specification 3.3.2.1, " Engineered Safety Feature Actuation System (ESFAS) Instrumentation," Table 3.3 3, Action 20. Currently, Table 4.3-1, Itern 19 requires that the Safety injection Input from ESF logic function be testea on a monthly basis. The proposed change will add Notation 5 and increaue the surveillance interval from monthly (overy 31 days) to every 62 days on a staggered test basis. Table 3.3 3, Action 20 allows bypassing one channel for testing purposes for one hour. The proposed change willincrease the time that a channel may be bypassed for testing purposes from one to two hours.
The proposed changes also include administrative changes to the Technical Specifications. These changes serve to clarify the Technical Specification requirements and do not change the technical content.
Background
There are two trains of Reactor Trip System and ESFAS instrumentation. The two trains of instrumentation are verified operable by performing surveillance procedures PT-36.1 A and PT-36.1B,
- Solid State Protection System Test."
These tests place one train of the Solid State Protection System (SSPS) in bypass and test the inputs and outputs to ensure that the train is operable.
Specifically, the Safety injection input from ESF, Auxiliary Feedwater Pump Ctart Autonutic Actuation Logic and Steam Line isolation Automatic Actuation Logic functions are proven operable by those tests.
Technical Specification 3.3.1.1 requires that the Reactor Trip System instrumentation channels and interlocks of Table 3.31 be operable with response times as shown in Table 3.3 2. The Safety injection input from ESF function is part of the Reactor Trip System instrumentation.
Recently, we conducted a review to ensure that surveillance requirements are incorporated into appropriate surveillance test procedures. During this review, we determined that Technical Specification 4.3.1.1.1 requires testing both trains of Safety injection input from ESF logic each month. Since that time, both trains of SSPS have been tested each month in order to meet the surveillance requirement.
- _ _ - _ _ _ - _ _ _ - _ - -. __ ____ A
Technical Specification 3.3.2.1 requires that the ESFAS instrumentation channels shown in Table 3.3 3 are operable with the trip setpoints set ,
cons! stent w!th the values shown in the inp setpoint column of Table 3.3 4 and with response times as shown in Table 3.3 5. The Auxiliary Feedwater Pump Start Automatic Actuation Logic and the Steam Line isolation Automatic Actuation Logic functions are part of the ESFAS instrumentation. It was determined during a recent rev:ew that Table 3.3 3, Action 20 did not allow adequate time to perform the required monthly testing of either the Auxiliary Feedwater Pump Start Automatic Actuation Logic function for Units 1 and 2 or the Steam Line Isolation Automatic Actuation Logic function for Unit 2. (Table 3.3 3 does permit sufficient time (i.e., two hours) when testing the Steam Line Isolation Automatic Actuation Logic function for Unit 1, and therefore, no change is required.)
Technical Specification Changes General The Technical Specification char.ges described herein apply to North Anna Units 1 and 2, unless otherwise stated.
Technical Soecification 4.3.1.1 1. TableA.3-1. Item 19 This change will modify Technical Specification 4.3.1.1.1, Reactor Trip System Instrumentation, Table 4.31, item 19, Safety injection input from ESF, to increase the surveillance interval from monthly (every 31 days) to every 62 days on a staggered test basis. This is accomplished by adding Notation 5, which states "Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS," to item 19.
The change is consistent with the requirements for the rest of the SSPS and is more stringent than the requirements- of NUREG -- 0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors, Revision 4. Before the review indicated the need to perform testing on both trains each month, all testing for the SSPS was performed on a staggered test basis frequency. The frequency at which the SSPS is now being tested increases the possibility of incdvertent actuations and decreases the amount of time that both trains of SSPS are operable. Testing on a staggered test basis is edequate to ensure the continued reliability of the system, limit the possibility of inadvertent actuations, and maximize the arnount of time that both trains of SSPS are operable.
Technical Soecification .4.3.1.1.1. Table 4.31. Items 21 and 22 The word "and" has been changed to "&"in several places for consistency.
Technical Suecification 3.3.2.1. Table 3.3 3. Action 17 The statement consists of two independent statements that have been spliced together with a comma. This change will substitute a period for the comma and capitalize the next word.
Iechnical Soecification 3 3 2.1 Table 3.3 3. Action 19 The word " requirements" is changed to singular to agree with the verb.
Technical Soecification 3.3.2.1, Table 3.3 3. Action 20 This change will modify Technical Specification 3.3.2.1, Table 3.3 3, Action 20, to allow a channel to be bypassed for up to two hours for testing purposes.
The monthly channel functional test requirement is met by implementing surveillance procedures PT 36.1 A and PT-36.18, Solid State Protection System Test. These tests place one train of SSPS in bypass and test the different inputs and outputs to ensure that the system is operable. During the time that the inputs and outputs are bypassed, the channel is inoperable. One of the actions that must be entered during this time frame IF Action 20. Action 20 states that "With the number of OPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 1 nour for surveillance testing per Technical Specification 4.3.2.1.1 provided the other channel is OPERABLE." However, the entire channel functional test takes between one and two hours to complete.
The proposed change is consistent with Table 3.3 3, Action 22, of NUREG 0452, Standard Technical Specifications for Westinghouse Pressurized Water Reacters, Revision 4. Action 22 allows the Auxiliary Feedwater Pump Start Automatic Actuation Logic and the Steam Line Isolation Automatic Actuation Logic functions to be bypassed for up to two hours when testing in accordance with Technical Specification 4.3.2.1.1. In addition, the NRC has previously issued guidance that it is not desired to knowingly perform maintenance or a surveillance wh!ch will require entoring an action statement that would cause a unit to shut down.
The change also converts "WITHIN" to lower case letters for Unit 1 only because it is not a defined term.
Technical Soecification 3.3.2.1. Table 3.3 3. Action 21 This change willinsert "the next" after
- HOT STANDBY within* to clarify the fact that the six hours to HOT STANDBY starts after the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore the channel ends. This does not change the intent of the requirement.