Rev 4 to ISI-P-002, Preservice Insp ProgramML20215N665 |
Person / Time |
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Site: |
Vogtle ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
10/30/1986 |
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From: |
GEORGIA POWER CO. |
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To: |
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Shared Package |
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ML20215N662 |
List: |
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References |
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ISI-P-002, ISI-P-2, NUDOCS 8611070139 |
Download: ML20215N665 (5) |
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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program. ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program. ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program. ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20091L8331989-05-19019 May 1989 Rev 0 to Corporate Guidelines 1.1.2, Positive Discipline ML20246N6241989-05-10010 May 1989 Rev 3 to Vogtle Electric Generating Plant Unit 1 Inservice Insp Program ML20078A5401988-11-15015 November 1988 Updated Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20195J9191988-11-11011 November 1988 Rev 4 to ISI-P-010, Preservice Insp Program Vogtle Electric Generating Plant Unit 2 ML20196B1551988-10-25025 October 1988 Rev 0 to ISI-P-014, Inservice Insp Program ML20195B3901988-10-18018 October 1988 Aw Vogtle Simulator Certification Plan ML20091L8931988-10-0303 October 1988 Voided Rev 9 to Procedure 10000-C, Conduct of Operations ML20155C0751988-09-15015 September 1988 Rev 0 to Abnormal Operating Procedures 18038-2, Operation from Remote Shutdown Panels ML20091L8821988-09-0808 September 1988 Voided Rev 10 to Procedure 35110-C, Chemistry Control of Rcs ML20155C0871988-08-19019 August 1988 Rev 9 to Procedure 12006-C, Unit Cooldown to Cold Shutdown ML20151G1851988-07-18018 July 1988 Rev 1 to ISI-P-006, Inservice Insp Program ML20151G1881988-07-18018 July 1988 Rev 2 to ISI-P-006, Inservice Insp Program ML20078A6221988-07-12012 July 1988 Readiness Review Program Module 20 - Instrumentation & Controls ML20078A5931988-06-28028 June 1988 Readiness Review Program Module 13B - Coatings ML20078A5831988-06-22022 June 1988 Readiness Review Program Module 12 - Electrical Cables & Terminations ML20091L7821988-06-0707 June 1988 Rev 0 to Procedure 49006-C, Health Physics & Chemistry Dept Outage Activities Implementing Procedure ML20078A5461988-05-12012 May 1988 Rev 1 to Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20078A5751988-04-13013 April 1988 Readiness Review Program Module 11 - Pipe Stress & Supports ML20151R0331988-04-13013 April 1988 Rev 3 to Inservice Test Program ISI-P-008, Summary of Changes ML20078A6311988-03-16016 March 1988 App F, Inspector Qualification of Vogtle Electric Generating Plant Unit 2 Readiness Review Program ML20148K4301988-03-0202 March 1988 Inservice Test Program 1998-05-25
[Table view] |
Text
_ _. _
SOUTHERN COMPANY SERVICES INSPECTION, TESTING, AND ENGINEERING SECTION FOR ,
GEORGIA POWER COMPANY ISI-P-002 PRESERVICE INSPECTION PROGRAM VOGTLE ELECTRIC GENERATING PLANT UNIT 1 O
SCS GPC SUPT REV DATE DESCRIPTION PREP'[ REV'O DEPT REV'O PLANT GEN BY BY MGR BY ENG MGR 0 4/19/84 Issued for PSI g g' f P
1 1/31/85 General Update g (( Of,1Q
!E53:!$",_ c@
porated Deviation
%)/* Cs @b '
001 ,
Incorocrated Info 9/15/86 in Sumary Table ph N $
3 g '[7[/y R6 M.k . 442, f/3/g 1mA 'I Y/#
4 10/23/96 Revised RR-33 and M RR LS so 4 A 10*Li'80 'ola*/84 b-Xt.g4 sclnl# ()jf l
l 8611070139 PDR 861103 i
ADOCK 05000424 i.__. . _ _ _ . -
PDR
i VEGP-1 RR-33 O
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Component or Relief Area Volumetric examination of pressure-retaining bolting in Safety Injection Pump Housing. (Class 2)
Safety Injection Pump casing studs I.D. Nos. - 11204-P6-003-801 through B32.
Requirement From Which Relief is Requested Item No. C4.30, Category C-D, Table IWC-2500-1 of ASME Section XI, requires a volumetric examination of pressure-retaining bolts and studs that are greater than two inches in diameter. The examination is ifmited to the bolting in one pump from a group of pumps which are similar in design, size, function, and service. Relief is requested from the volumetric examination of pump casing studs during Preservice Inspection. .g a
Basis for Relief The pressure retair.ing studs of safety injection pumps are inaccessible for volumetric examination while in place under tension. To reach the studs for examination, the cap nuts must be removed, which requires breaking the pressure boundary of the pump. Disassembly of the pumps to solely perform a p baseline examination is not warranted during the preservice inspection.
d Alternate Examination A surface examination of these studs has been performed by the pump manufacturer during fabrication. Fabrication examination records will be documented and identified in the Vogtle Unit 1 PSI final report. An ASME Section III hydrostatic test has been performed to further ensure the integrity of the pumps.
In addition, the safety injection pumps for VEGP-2 are identical in design, size, function, and service as well as were fabricated under the same specifications.
A baseline ultrasonic examination of the studs in both of the VEGP-2 safety injection pumps will be performed during the Preservice Inspection.
7-57 002 Rev. 4 O
~
VEGP-1 O. aa-4s Component or Relief Area Acceptance standards for the twenty-four welds (see Attachment 1) which were evaluated to have non-geometric recordable NDE indications during the VEGP-1 PSI.
Requirement from which Relief is Requested ASME Code Section XI 1980 Edition with Winter 1980 Addenda Subparagraph IW8-3410.1 states that .the acceptance standards referenced in Table IW8-3410-1 shall be applicable to those components (a) whose material properties are in accordance with those stated in the referenced tables and (b) where the 3
l maximum postulated defect that detemines the Ifmiting operating conditions -
conforms with the reconsnendations stated in Section III, Division I Appendices.
Basis for Relief A review of the material specifications for the components Itsteo in Attachment 1 indicates that not all of the criteria in the appitcable IW8-3500 table are met for these welds. A comparison of the material properties in the O. IW8-3500 tables versus the actual material properties shows that the differences listed in Attachment I have no effect on using the applicable-tables for the evaluation of indications as shown by the notes for Attachment 1.
Alternate Examination The Code-required examinations were performed on these components and the non-geometric recordable indications were detemined to be acceptable per the applicable Winter 1980 IWB-3500 table.
O 7-82 002 Rev. 4
Notes for Attachment 1
- 1. Table IWB-3511-1 references NB-2300 while the secondary side of the steam generators is typically ASME Class 2 which would imply material testing per NC-2300.
As noted in Paragraph 5.4.2.1 of the VEGP FSAR, the secondary side of the VEGP. steam generators was fabricated per Section III of the ASME Code for Class 1 components.
Table IWB-3511-1 of the Winter 1980 Addenda was used to evaluate the planar indications and they are Code-allowable.
Furthermore, this position is technically justified since the Winter 1983 -
Addenda includes IWC-3500 tables with acceptance standards essentially
~ the same or more flexible than those of IWB-3500 of the 1980 Edition.
These indications Addenda were and they are evaluated to Table IWC-3510-1 in the Winter 1983 Code-allowable.
2.
Tables IWB-3511-1 and -2 apply only to component with thickness greater than or equal to four inches, while the steam generator thickness is less than four inches. .
This position is technically justified since the Winter 1981 Addenda permitted Tables IWB-3511.1 and -2 to be used for thicknesses down to 2-1/2 inches. These indications were evaluated to the Winter 1980 Addenda tables and they are Code-allowable.
3.
The minimum yield strength in Table IWB-3511-1 does not agree with the Q actual minimum yield strength of the components.
The use of higher specified minimum yield strength materials is justified in the component design in accordance with _ Paragraph G-2110 (b) of Appendix G of ASME Section III, using the standard postulated defect size in this appendix. Westinghouse has generated the supporting fracture-toughness data for these materials as referenced in the applicable stress reports and VEGP FSAR Paragraph 5.2.3.3.1. Satisfying these Section III requirements demonstrate applicability of ASME Section j
XI Table IWB-3511-1,.even considering the higher minimum yield strength materials of these components.
- 4. Tables IWB-3511-1 and -2 apply only to components with thicknesses greater than or equal to four inches while the Pressurizer thickness is less than four inches.
O 7-87 002 REV. 4
. .T . i i
O i Tais tted peruf aa=ittaa Tables '= t caatcaiis IW8-3511-1 and a=>t1<< -2'to be used 4 =$ac ta w'at rdown for thicknesses i>sitoa, 2-1/2 inches.
Addenda tabler and they ar* Code-allowable.These indications I wl
~
- 5. Table I'W8-3514-2 ,
constructed to NC-2300. references NS-2300 while the Class 2 pfpf ag 'was l IWC-3000 states that 114-3000 1980 Edition of ASME Section XI.may bo.used for Class i' components in the states that the materials'must meet the requirerets ofSince N8-2300.Th
' Class 2 components implicit in IWC-3000 that NC-2300 applies.' This is consistent '
purchase specification for these piping materials The 1, subse ASE Section III NC-2300, without modification or e1 in accordance wf th test requirements. xemptian to the impact rules for Class 2 components.This is consistent with the ASME Section.III de .
s O
. O 4
7-88 002 Rev. 4
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