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 95-06ML18153A633 |
Person / Time |
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Site: |
Surry, North Anna |
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Issue date: |
11/26/1996 |
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From: |
OHANLON J P VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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Shared Package |
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ML18153A634 |
List: |
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References |
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96-492, AL-95-06, AL-95-6, GL-95-06, GL-95-6, NUDOCS 9612020234 |
Download: ML18153A633 (7) |
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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 ML18152B6571999-04-28028 April 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TSs Re Refueling Water Chemical Addition Tank Min Vol ML18152B5501999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,proposing Administrative Change That Will Consolidate AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5431999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TS Re Augmented Insp Requirements for Reactor Coolant Pump Flywheels 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 ML18152B6131998-11-0404 November 1998 Application for Amends to Licenses DPR-32 & DPR-37,revising EDG Start & Load Time Testing Requirements in TS 4.6.A.1.b ML18153A3291998-09-24024 September 1998 Application for Amends to Licenses DPR-32 & DPR-37,modifying Testing Requirements for Reactor Trip Bypass Breaker 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 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 ML18151A6801998-06-19019 June 1998 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers.Application Revised 971105 Submittal 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 ML18153A3451997-12-18018 December 1997 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Terminology Used for Describing Equipment Surveillances Conducted in Refueling Interval Frequency. Amend Consistent W/Info Provided in Rev 1 of NUREG-1431 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 ML18152A0761997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML18151A9791997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Respectively.Amends Will Revise TS to Increase Maximum Allowable Fuel Enrichment from 4.1 to 4.3 Weight Percent U-235.Description of Change Encl 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 ML18153A6881996-04-15015 April 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Applicability of Quadrant Power Tilt Ratio Requirements ML18153A5371996-03-21021 March 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Requirements for Testing Charcoal Adsorbent in Auxiliary Ventilation & Control Room Air Filtration Sys as Outlined in Tech Specs 4.12 & 4.20,respectively 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 ML18153A5781996-01-30030 January 1996 Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Surveillance Requirement for Certain Reactor Coolant Liquid Samples 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 ML18153A6741995-11-20020 November 1995 Application for Amends to Licenses DPR-32 & DPR-37,permiting 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 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 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 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 ML18153A7121995-07-20020 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to Ts,By Establishing New Setpoint Limit for Steam Generator high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6971995-07-14014 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing Su Accumulators in Lieu of Isolation 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 ML18152A1841995-02-14014 February 1995 Application for Amends to Licenses DPR-32 & DPR-37,revising TS 4.4.D to Permit Approved Exemptions to ILRT Frequency Requirements,Including one-time Exemption Request from Section III.D.1(a) of 10CFR50,App J for Surry Unit 2 ML18153B2111995-01-24024 January 1995 Application for Amends to Licenses DPR-32 & DPR-37,modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves 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 ML18152B6571999-04-28028 April 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TSs Re Refueling Water Chemical Addition Tank Min Vol ML18152B5431999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TS Re Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152B5501999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,proposing Administrative Change That Will Consolidate AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 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 ML18152B6131998-11-0404 November 1998 Application for Amends to Licenses DPR-32 & DPR-37,revising EDG Start & Load Time Testing Requirements in TS 4.6.A.1.b ML18153A3291998-09-24024 September 1998 Application for Amends to Licenses DPR-32 & DPR-37,modifying Testing Requirements for Reactor Trip Bypass Breaker 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 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 ML18151A6801998-06-19019 June 1998 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers.Application Revised 971105 Submittal 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 ML18153A3451997-12-18018 December 1997 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Terminology Used for Describing Equipment Surveillances Conducted in Refueling Interval Frequency. Amend Consistent W/Info Provided in Rev 1 of NUREG-1431 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 ML18152A0761997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML18151A9791997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Respectively.Amends Will Revise TS to Increase Maximum Allowable Fuel Enrichment from 4.1 to 4.3 Weight Percent U-235.Description of Change Encl 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 ML18153A6881996-04-15015 April 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Applicability of Quadrant Power Tilt Ratio Requirements ML18153A5371996-03-21021 March 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Requirements for Testing Charcoal Adsorbent in Auxiliary Ventilation & Control Room Air Filtration Sys as Outlined in Tech Specs 4.12 & 4.20,respectively 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 ML18153A5781996-01-30030 January 1996 Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Surveillance Requirement for Certain Reactor Coolant Liquid Samples 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 ML18153A6741995-11-20020 November 1995 Application for Amends to Licenses DPR-32 & DPR-37,permiting 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 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 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 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 ML18153A7121995-07-20020 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to Ts,By Establishing New Setpoint Limit for Steam Generator high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6971995-07-14014 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing Su Accumulators in Lieu of Isolation 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 ML18152A1841995-02-14014 February 1995 Application for Amends to Licenses DPR-32 & DPR-37,revising TS 4.4.D to Permit Approved Exemptions to ILRT Frequency Requirements,Including one-time Exemption Request from Section III.D.1(a) of 10CFR50,App J for Surry Unit 2 1999-08-04
[Table view] |
Text
1. rr \.r ii e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 26, 1996 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE REMOVAL OF RECORD RETENTION REQUIREMENTS Serial No.96-492 NL&OS/GSS Docket Nos. 50-338, 339 50-270, 271 License Nos. NPF-4, 7 DPR-32, 37 Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Facility Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2 and DPR-32 and 37 for Surry Power Station Units 1 and 2. The proposed changes will eliminate the records retention requirements for the Adminstrative Section of the Technical Speciations in accordance with Generic Letter 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance." A discussion of the proposed Technical Specifications changes is provided in Attachment
- 1. The proposed Technical Specifications changes are provided for both stations in Attachment
- 2. It has been determined_
that the proposed Technical Specifications changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as. defined in 1 o* CFR 50.92. The basis for our determination that the changes do not involve a significant hazards consideration is provided in Attachment
- 3. The proposed Technical Specifications changes have been reviewed and approved by the Station Nuclear Safety and Operating Committees and the Management Safety Review Committee.
f 9612020234 961126 PDR -ADOCK 050.00280.
p . _J=!D8 __ f\CC>l ii u Should you have any questions or require additional information, please contact us. Very truly yours, James P. O'Hanlon Senior Vice President
-Nuclear Attachments cc: U.S. Nuclear Regulatory Commission Region II
- 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRG Senior Resident Inspector North Anna Power Station Mr. R. A. Musser NRG Senior Resident Inspector Surry Power Station Commissioner Department of Radiological Health Room 104A 1500 East Main Street Richmond, VA 23219 Ii COMMONWEAL TH OF VIRGINIA ) ) COUNTY OF HENRICO ) The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, 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 that Company, and the statements in the document are true to the best of his knowledge and belief. Acknowledged before me this ~ay of~l&h,heJ, 19~. My Commission Expires: 3/ , 199.[. &1fu~ Notary Phlic (SEAL)
.,., ATTACHMENT 1 DISCUSSION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY SURRY AND NORTH ANNA POWER STATIONS UNITS 1 AND 2
' e e Discussion of Changes Introduction Currently, North Anna Units 1 and 2 Technical Specifications and Surry Units 1 and 2 Technical Specifications provide retention requirements for certain operations phase records in the Administrative Controls Section. These requirements specify which records are to be retained for five years and those which are to be retained for the duration of the Facility Operating License (lifetime retention).
As discussed in NRC Administrative Letter 95-06, these technical specification requirements are substantially redundant to requirements established in licensees' quality assurance programs, in other NRG-approved programs (i.e., emergency preparedness plans, physical security plans, radiation protection plans, and fitness-for-duty programs), and in current regulations.
Also, in NRG Administrative Letter 95-06, the NRG has determined that the provisions of 10 CFR 50.54(a) provide appropriate controls to ensure that sufficient records continue to be retained for commercial nuclear facilities.
Thus, these records retention requirements can be removed from the Technical Specifications provided that they currently exist in another appropriately controlled document or if the specific requirements are relocated to one or more of these documents.
The proposed changes remove the retention requirements from the Administrative Controls Section of Technical Specifications.
The record retention requirements presently in the Technical Specifications that are not identified in the Operational Quality Assurance Program (QA Topicai Report) by reference to ANSI N45.2.9-1974, "Requirements for Collection, Storage, and Maintenance of QA Records for Nuclear Power Plants," are being relocated to the QA Topical Report. Chapter 17 of the UFSARs for both Surry and North Anna is the Operational Quality Assurance Program. The proposed changes are administrative in nature and do not affect the design or operation of the plant in any way. Therefore, an unreviewed safety question or significant hazards consideration is not generated by the proposed Technical Specifications changes. Background NRG efforts related to technical specification improvements_
include a revision to 10 CFR 50.36, --revisions to Standard Technical**
Specifications, some generic communications, and many individual license amendments.
Part of this effort is the relocation of certain Technical Specification requirements that are controlled directly by regulations and related licensee programs.
On December 12, 1995, the NRC issued Administrative Letter 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance." Administrative Letter 95-06 discusses relocating certain Technical Specification administrative sections to licensee controlled documents/programs.
The Records and Record Retention requirements were included in the Generic Letter for relocation from Technical Specifications.
In addition, to relocating the record retention requirements for Technical Specifications in accordance with the guidance of Administrative Letter 95-06, we intend to evaluate
- e ' the r~cord retention requirements against the current regulations, ASME Code, and
- other applicable industry standards to provide consistency between stations and possibly reduce record retention requirements.
Any change in record retention requirements will be submitted to the NRC in accordance with 10 CFR 50.54 (a). Licensing Basis The current requirements for retention are included in the Operational Quality Assurance Program by commitment to Regulatory Guide 1.88, "Collection, Storage, and Maintenance of QA Records for Nuclear Power Plants," which endorses ANSI N45.2.9-1974. In addition, to the above record retention requirements, record retention requirements are also included in the Administrative Control Section of the Technical Specifications for Surry and North Anna. Description Of Specific Changes The proposed amendment would delete the Technical Specifications requirements for record retention and relocate those requirements to the Operational Quality Assurance Program. Specifically, the North Anna and Surry Technical Specifications are revised as follows:
has been relocated to the Operational Quality Assurance Program, and pages TS 6.5-2 and TS 6.5-3 have been deleted in their entirety."
has been relocated to the Operational Quality Assurance Program" on page 6-22 and with "This Page Intentionally Left Blank" on page 6-23.
has been relocated to the Operational Quality Assurance Program" on page 6-23. Safety Significance Relocation of the Technical Specifications record retention requirements to the Operational Quality Assurance Program is administrative in nature and in no way affects the design or operations of the plant. The probability that an accident will occur will neither be increased nor decreased by these proposed Technical Specification changes. The proposed changes have no direct impact on the function or method of operation of plant equipment.
Thus, there is no increase or decrease in the probability of a previously analyzed accident due to these changes. Plant structures, systems, and components are not affected by the proposed changes. As such, the consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR are not increased by these changes.
- Reco'rd retention requirements do not contribute to the initiation of accidents or mitigate the consequences of postulated accidents.
The relocation of record retention requirements from the Technical Specifications to the Operational Quality Assurance Program will not adversely impact these applications since these changes are administrative in nature and do not affect the design or operation of the plant. Therefore, the proposed changes to Technical Specifications neither produce a new accident scenario nor produce a previously unanalyzed type of equipment malfunction.
The proposed changes to Technical Specifications are administrative in nature. Only the retention periods for certain quality assurance records are affected, not the design nor the operation of facility structures, systems, or components.
Therefore, the proposed Technical Specification change package does not involve an unreviewed safety question as determined by the criteria of 10 CFR 50.59.