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Proposed Tech Specs,Allowing Next Type a Test to Be RescheduledML20098C147 |
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Site: |
Vogtle |
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Issue date: |
10/02/1995 |
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From: |
GEORGIA POWER CO. |
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To: |
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Shared Package |
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ML20098C143 |
List: |
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References |
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NUDOCS 9510060296 |
Download: ML20098C147 (1) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled ML20098A4861995-09-22022 September 1995 Proposed Tech Specs,Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20086G5691995-07-0606 July 1995 Proposed Tech Specs Section 3.8.3.1,Page 3/4 8-15 Re Footnote & Bases & Expansion ML20085G7171995-06-14014 June 1995 Proposed Tech Specs,Clarifying in Revised Bases of 3/4 Chapter 8,that Alignment of Standby Auxiliary Transformer Intended to Be Temporary Alignment & Will Be Utilized When Normal Preferred Offsite Power Source,Rat Unavailable ML20083M0731995-05-12012 May 1995 Proposed Tech Specs Revising SR 4.1.6.2 to Support Exemption from 10CFR50,App J Type a Test Schedule ML20083A1391995-05-0202 May 1995 Proposed Tech Specs,Adding Automatic Load Sequencer to Plant TS ML20082D9881995-04-0404 April 1995 Proposed Tech Spec Page 6-7 Reflecting Corrected Terminology Re Composition of Plant Review Board ML20081J5031995-03-17017 March 1995 Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement ML20081D1591995-03-17017 March 1995 Proposed TS Table 3.3-8, Accident Monitoring Instrumentation, Deleting Loop Numbers 551,552,553 & 554 ML20082E7731995-03-0404 March 1995 Proposed Tech Specs Re Plant Review Board Composition ML20080N2451995-02-28028 February 1995 Proposed Tech Specs Pages Re Accident Montoring Instrumentation 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] |
Text
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.I . ,
i
. T CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONofTf0W FORJPERATION
~
& N8W.
3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of less than or equal to L ,
0.205 by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a pressure not less' than P., 37 psig, or- l t
- b. A combined leakage ~ rate of less than 0.60 L for all penetrations and valves subject to Type 8 and C tests, wk pressurized to a pressure not less than P , 37 psig. l APPLICABILITY: MODES 1, 2, 3, and 4.
EllQt[:
With either the measured overall integrated containment leakage rate exceeding 0.75 L or-the measured combined leakage rate for all penetrations and valves
- subjecl to Types B and C tests exceeding 0.60 L,, restore the overall i integrated leakage rate to less than 0.75 L ;
i all penetrations subject to Type B and sts C teto, less and than the combined leakage 0.60 L, prior to rate fo j increasing the Reactor Coolant System temperature above 200*F.
! l
, SURVEILLANCE REQUIREMENTS l
Enceft as med* died by illlC 0Lfyrond cxetnfti'cq
! 4.6.1.2 Jhe containment leakage rates shall be demonstrated at the following j
test schedule and shall be determined in conformance with the criteria speci-j fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI
- N45.4-1972
- a. Three Type A tests (Overall Integrated Con i t Leakage Rate) i shall be conducted at 40 i 10 month interval ring shutdown at
- a pressure not less than P , 37 psig, during each 10-year service l
! period. The third test of each set-shall be conducted during the F shutdown for the 10-year plant inservice inspection; !
1
- The Ty pe A selecla/ed .fo,- vf 6 P t/nl} l dariny LAG iviW At rescke hulecl h - th e jfq7 {, gg,}g g, 7
V0GTLE UNITS - 1 & 2 3/4 6-2 Amendment No. 63 (Unit 1)
, Amendment No. 42 (Unit 2) 9510060296 951002
! PDR ADOCK 05000424
_P_ PDR
. ..