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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 ML20206C0081999-04-22022 April 1999 Amends 219 & 200 to Licenses NPF-4 & NPF-7,respectively, Changing NAPS TS Casing Cooling & Outside Recirculation Spray Pumps Surveillance Testing Criteria ML20207H4381999-03-0202 March 1999 Amends 218 & 199 to Licenses NPF-4 & NPF-7,respectively, Changing NAPS TS to Provide Allowed Outage Time of 144 Days for PORV Nitrogen Accumulators ML20199C9921999-01-12012 January 1999 Corrected TS Pages to Amends 216 & 197 to Licenses NPF-4 & NPF-7,respectively.TS Bases Changes Associated with Amend Request,Inadvertently Omitted from Licensee 981016 Submittal & Being Sent as Attachment to ML20198A3441998-12-10010 December 1998 Amends 216 & 197 to Licenses NPF-4 & NPF-7,respectively, Changing NAPS TS to Revise Frequency & Voltage Requirements During Starting & steady-state Running Portions of EDG Testing 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 ML20155H0251998-10-30030 October 1998 Amends 215 & 196 to Licenses NPF-4 & NPF-7,respectively, Addressing Changes That Modify Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20237E1821998-08-26026 August 1998 Amends 214 & 195 to Licenses NPF-4 & NPF-7,respectively, Changing NAPS TS to Allow an Extended Allowed Outage Time of 14 Days for One EDG ML20236X3741998-08-0303 August 1998 Amends 213 & 194 to Licenses NPF-4 & NPF-7,respectively, Revising Sections 3.9.7,4.9.7.1,4.9.7.2 & 3/4.9.7 for Unit 1 & Sections 3.9.7,4.9.7.1,4.9.7.2 & 3/4.9.7 for Unit 2, Allowing Movement of Sf Pit Gate Over Irradiated Fuel 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 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 ML20249C1501998-06-23023 June 1998 Amends 212 & 193 to Licenses NPF-4 & NPF-7,respectively, Making Changes to TS by Revising Listed Sections & Modifying Station Mgt Titles ML20248F0391998-05-28028 May 1998 Correction to Amends 210 & 191 to Licenses NPF-4 & NPF-7. Correction Due to Administrative Oversight ML20217E6451998-04-22022 April 1998 Amends 211 & 192 to Licenses NPF-4 & NPF-7,respectively, Revising Surveillance Requirement 4.4.10.1.1,modifying Insp Requirements for RCP Pump Flywheels for Both Units & Eliminating Loop Straightener Insps ML20216G8671998-04-16016 April 1998 Amends 210 & 191 to Licenses NPF-4 & NPF-7,respectively, Revise SRs 4.7.1.7.2.a.1 & 4.7.1.7.2.a.2 for Both Units for Turbine Throttle & Govenor Valves ML20216F1151998-04-14014 April 1998 Amends 209 & 190 to Licenses NPF-4 & NPF-7,respectively, Revising Surveillance Requirement Tables 3.3-1 & 4.3-1 for Both Units Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20216E0101998-04-13013 April 1998 Amends 208 & 189 to Licenses NPF-4 & NPF-7,respectively, Revising TS to Eliminate Records Retention Requirements from Sections 6.10 of TS 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 ML20203C1621997-12-0404 December 1997 Amends 207 & 188 to Licenses NPF-4 & NPF-7,respectively, Changing TS to Revise Surveillance Requirement 4.7.1.7.2 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 ML20149L1761997-07-30030 July 1997 Amends 206 & 187 to Licenses NPF-4 & NPF-7,respectively, Addressing Only Proposed Changes to Intermediate Range Trip Setpoints & Allowable Values 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 ML20116B2311996-07-24024 July 1996 Amends 202 & 183 to Licenses NPF-4 & NPF-7,respectively, Clarifying TS to Allow Switching of Charging & low-head Safety Injection Pumps During Unit Shutdown Conditions ML20117K4031996-06-0505 June 1996 Amends 201 & 182 to Licenses NPF-4 & NPF-7,respectively, Modifying TSs to Increase Min Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm 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 ML20101L6811996-04-0101 April 1996 Amends 200 & 181 to Licenses NPF-4 & NPF-7,respectively, Revising TS to Increase Pressurizer Safety Valve Lift Setpoint Tolerance & Reduce Pressurizer High Pressure Reactor Trip Setpoint & Allowable Value 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 ML20101B3751996-03-0606 March 1996 Amends 199 & 180 to Licenses NPF-4 & NPF-7,respectively, Revising TS Re Neutron Flux High Trip Setpoints W/Inoperable MSSVs ML20100K9951996-02-27027 February 1996 Amends 198 & 179 to Licenses NPF-4 & NPF-7,respectively, Revising TS 3.9.4 to Allow Both Containment Pal Doors to Remain Open During Fuel Movements or Core Alterations Provided That One Door Operable ML20097F3411996-02-0909 February 1996 Amends 196 & 177 to Licenses NPF-4 & NPF-196,respectively, Revising TS Re Use of performance-based Containment Leakage Rate Testing ML20097D2231996-02-0808 February 1996 Amends 195 & 176 to Licenses NPF-4 & NPF-7 Increasing Surevillance Test Interval for Turbine Reheat Stop & Intercept Valves from Once Per 31 Days to Once Per 18 Months & Extending Insp Interval of Turbine Stop 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 1999-08-04
[Table view] |
Text
,
VIHOINIA Eu:criac Ann l'own:n Co.suwxy Ricusioun,Waaisir unu ci August 29, 1991 l~
U.S. Nuclear Regulatory Commission Serial No.:
91-506 Attention: Document Control Desk NAPS /MJB/TAH:R2 Washington, D.C. 20555 Docket Nos : 50-338 50-339
(
License Nos.: NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC' AND PUWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2
}
PROPOSED TECHNICAL SPECIFICATION CHANGE TABLE 3.3-4. STATION BLACKOUT. LOSS OF VOLTAGE. AND l
DEGR ADED VOLTAGE. TRIP SETPOINTS AND ALLOWABLE VALUES
+
L L
Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests amendments, in the form of changes to Technical Specifications, to Operating Licenses Number NPF-4 and NPF-7 for North Anna Power Statio. Units 1 and 2.
These amendments will revise the Station Blackout, Loss of Voltage and Undervoltage trip setpoints and allowable values located in Specification 3.3.2, Table 3.3 4, Engineered Safety Feature Actuation System instrumentation Trip Setpoints.
The proposed change for Specification 3/4.3.2 Table 3.3-4 Item 6.e, Station Blackout, is administrative in nature. The Trip Setpoint and Allowable Value are currendy listed i
I to a percentage of the transfer bus voltage. This will be changed to an actual voltage.
Tut,.roposed change for Spacification 3/4.3.2 Table 3.3 4 Items 7,a and 7.b, Loss of i
V),tage and Degraded Voltage, removes the tolerance values associated c'ith the Allowable Values listed in Technical Specification 3/4.3.2 Table 3.3-4 Items 7.a and l
7.b, Loss of Voltage and Degraded Voltage. These changes are intended to promote l
l clarity and ease of t.se of the specification.
In addition, the Trip Setpoints and Allowable Values for the Loss of Voltage and Degraded Voltage specifications (items v
7.a and 7.b of Table 3.3-4) have been revised.
i This request has been reviewed by the Station Nuclear Safety and Operating
[
L Committee and the Management Safety Review Committee. It has been determined that this request does not involve an unrevieNd safety question as defined in 10CFR50.59, or a significant hazards consideration as defined in 10CFR50.92. The changes and the determination of no significant hazards are presented in the
~
proposed final copy of the specification, a detailed discussion of the proposed Attachment.
I
'9109040379 91o829 DR AD7CK 05000338
[OOb PDR g
~ - - ~, _ _ _.
.. ~
Dochet Nos.: 50-338&339 serial No.:
91 506 Technical Specification 3.3.2.1-requires ESFAS surveillance testing to be performed every 18 months. Establishing new setpoints for the 4160 volt emergency bus undervoltage trip setpoints and the performance of associated post maintenance testing is not desired during power operations because of the increased possibility of inadvertent disconnection of the emergency buses from the preferred off site power l
sources.
Therefore, we request that the amendments become effective with their issuance, with implementation required prior to restart after each. unit's next refueling outage.
Currently, Unit 1 is scheduled for refueling outage from April 18,1992 through June 30,1992, and Unit 2 from February 1,1992 through April 14,1992.
Please contact us if you have any questions or require additionalinformation.
Very truly yours,
}
&W-
/ W. L Stewart [#D Senior Vice President - Nuclear
Attachment:
Proposed License Amendment for North Anna Units 1 and 2.
i pc: U.S. Nuclear Regulatory Commission Region il 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser L
NRC Senior Resident inspector l
North Anna Power Station Commissioner Department of Health Room 400
- 109 Governor Streel L
Richmond, Virginia 23219 l
i COMMONWEALTH OF VIRGINIA )
)
COUbfTYOF HENRICO
)
i The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by F. K. Moore who is Vice President - Nuclear Engineering Services, for W. L. Stewart who is Senior Vice President - Nuclear, of Virginia Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of L
that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this _[f_. day of A7/2af,198/_.
My Commission Expires:
8/A 8/
,19 9N 0
l l
IW Notary Public (SEAL) 1 l
- _.. ~.
d I
ATTACHMENT PROPOSED CHANGES TO TECHNICAL SPECIFICATIOf(S 6
NORTH ANNA POWER STATION-l-
i I.
l l-i..
Virginia Electric and Power Company
-w a--
---_--._---,-------,-----,.,--,.,---__-_-_-------_-_-_-_--__-----------------------____--..-__-.----_---__-----__--s
Dochet Nos. 338 & 339 Serial No. 91506 Attachment Pg 1/11 r
CONTENTS Saction Page 1
Discussion of Proposed Changes 2
2 Final Copy of Proposed Change Page::
6 3
Determination of No Significant Hazards 9
(10 CFR 50.92 Evaluation) 1 t
Virginia Electric and Power Company
Docket Nog. 338 & 339 Serial No. 91506 Attachment Pg 2 /11 SECTION 1 PROPOSED CHANGES TO NORTH ANNA POWER STATION l
l TECHNICAL SPECIFICATION 3/4.3.2 l
l UNITS 1 AND 2 l
l l
1 DISCUSSION OF PROPOSED CHANGES l
I l
l l
l l
l l
l l
Virginia Electric and Power Company
Dochet Nos. 338 a 339 serial No.91-506 Attachment Pg 3 /11 QLEQUSSION OF PROPOSED CH ANGES BACKGROUND During a design basis event, the Engineered Safety Feature (ESF) systems are supplied electrical power by the 4160 Volt Emergency Busses. The availability of this equipment is assured by the Emergency Diasel Generators (EDGs) which provide full capacity back-up supplies.
The ESF electrical equipment is prevented from operatin0 n a reduced voltage i
condition, which could damage or incapacitate it, by anticipatory undervoltage inp relays which strip the emergency buses of electrical loads, start the EDGs, and then permit reloading the necessary ESF loads. The setpoints for these relays are subject to Technical Specification controls.
PROPOSED CHANGES Technical Soecification 3/4.3.2 Table 3.3-4 Item 6.e.
The Trip Setpoint specified for undervoltage protection of the Auxiliary Feedwater Pumps in Technical Specification 3/4.3.2 Table 3.3-4 Item 6.e, is currently listed as 257.5% of transfer bus voltage. This will be changed to 22392 volts on the transfer bus which is the actual voltage represented by 57.5% of 4160 volts (nominal voltage of the transfer buses). The Allowable Value is similarly presented as 252.5% of transfer l
bus voltage and is changed to 22184 volts on the transfer bus which is equal to 52.5%
l of 4160 volts. Therefore, these changes are administrative in nature and are intended to promote clarity and ease of use of the specification.
Technical Soecification 3/4.3.2 Table 3.3-4 Items 7.a. and b.
Changes in Trip Setpoint Voltage and Tolerance Values The Trip Setpoints values, time delays, and the tolerance values listed in Technical Specification 3/4.3.2 Table 3.3-4 Items 7.a and 7.b. are modified by this change.
l-These proposed values represent the minimum voltage and appropriate time delays l
required for the actuation of the Loss of Power sensing relays and are based on two considerations, The first consideration is to insures that during sustained reduced voltage situations, adequate voltage is provided to the ESF equipment for continued operation cnd that the equipment control power voltage is adequate to operate I
equipment control relays and contacts. The second consideration is to minimize the possibility of discconecting the emergency buses from the offsite power source during short term voltage drops, such as those caused by energizing large electrical loads.
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Docket flos 338 & 339 sonal rJo. 91-s00 Attachmont Pg 4 /11 The proposed Trip Setpoint voltage limits and tolerance values have been developed with these considerations to include relay drift, and conform to eur current undervoltage/ degraded voltage analyses and methodology.
The Trip Setpoint changes will assure that the the maximum analyzed relay drift will not result in the actual emergency bus voltage deviating from the degraded voltage analysis assumptions during a normal surveillance interval. The proposed voltage limits for Loss of Voltage and Degraded Voltage (Items 7.a and b.) and the tolerance for Loss of Voltage (item 7.a) are more restrictive than the current specification. The tolerance value for Degraded Voltage (Item 7.b) appears to be less restrictive, however a change of 17 volts on the 4160 volt emergency buses, results in the minimum discernible variance of the test instrumentation.
Bus voltage is determined by measuring the vo;tage output from a potential transformer with a voltage ratio factor of 60.6-to 1. Therefore a change of 7 volts on the 4160 volt primary side wu! result in a secondary sido change of only 0.1 volt.
Changes in Allowable Value Voltage Time Delays, and Tolerance Values The Allowable Values voltage ;imits, time delays, and tolerance values listed in Technical Specification 3/4.3.2 Table 3.3 4 Items 7.a and 7.b. are also modified by this change. These provide the minimura voltage and appropriate time delay values for the Technical Specification surveillance of undervoltage protection devices.
The proposed Allowable Value voltage limits and tolerance values have been developed in accordance with our current undervoltage/ degraded voltage (GDC-17) analyses and methodology. The proposed voltage limits for Loss of Voltage and Degraded Voltage (items 7.a and b.) are more restrictive than the current specification and conform to our current undervnitage/ degraded voltage analyses and methodology.
The time delay for the Degraded Voltage (Item 7.b) Allowable Value is also reduced from 7513 seconds to 563 seconds.
This is more restrictive than the existing specification and insures that the Emergency Diesel Generators will be supplying power to the emergency buses within 74 seconds.
The Trip Setpoint values contains adequate margins to prevent unnecessary disconnection from the offs :e po'vei source during transient, reduced voltage situations.
Therefore, it is not necessary to specify an upper boundary for the Allowable Values.
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Docket Nos. 338 & 339 serial No. 91506 Aitachment Pg 5 /11 The Allowabie Values for these items represent actual emergency bus voltage and time delay values. Relay drift will be accounted for in calculating the surveillance test acceptance criteria. The Surveillance test acceptance criteria will specify a range of values which will include the appropriate relay drift allowances calculated _to protect both ESF equipment from undervoltage situations and minimize the possibility of disconnection of the emergency buses from the offsite power source during short term voltage drops.
Therefore this amendment request changes the Technical Specification Allowable
- Values for items 7.a and 7.b, from bands defined by specific values with plus-or-minus deviations, to greater-than or-equal-to given minimum values, as well as providing new minimu ~ values based on the current undervoltage / degraded voltage (GDC-17) analyses and methodology.
Conclusion The new values for the Trip Setpoints and the Allowable Values ensure the continued protection of the ESF equipment from undervoltage conditions while minimizing the possibility _of unnecessary disconnecting from the preferred off-site power sources.
_ The values for the ~ rip Setpoints and the Allowable Values are at least as or more restrictive than the existing specification and are consistent with the regulatory basis for the Loss of Power and Degraded Voltage protection and the North Anna Units 1 and 2 Loss of Offsite ?ower (GDC-17) analysis while providing additional operating margins for future electncal loads.
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