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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 REPORT
MONTHYEARML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20084S3601995-05-31031 May 1995 Rcb Integrated Leak Rate Test Unit 2 - Second Periodic ML20058G8841993-11-0505 November 1993 Cycle 4 Startup Test Rept ML20045A9631993-04-30030 April 1993 Reactor Containment Bldg Integrated Leakage Rate Test Rept for Apr 1993, Final Rept ML20102B2401992-06-30030 June 1992 First Periodic Reactor Containment Bldg Integrated Leakage Rate Test,June 1992 ELV-02004, Fourth Suppl to Summary Rept of Startup Test Program1990-08-14014 August 1990 Fourth Suppl to Summary Rept of Startup Test Program ML20042G7101990-05-11011 May 1990 Third Suppl to Summary Rept of Startup Test Program. W/900511 Ltr ML20044B0741990-03-30030 March 1990 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept. ELV-00789, Initial Startup Rept for Period 890209-05201989-08-21021 August 1989 Initial Startup Rept for Period 890209-0520 ELV-00318, Cycle 2 Startup Test Rept1989-03-13013 March 1989 Cycle 2 Startup Test Rept ML20195K4541988-11-30030 November 1988 Response to NRC Bulletin 88-005 for Plant Vogtle. Response Consists of Records Review,Testing Results,Analyses & Conclusions from Program for Determining Whether Ref safety- Related Fittings & Flanges Consistent W/Asme Code Criteria ML20235U6861988-11-30030 November 1988 Reactor Containment Bldg Integrated Leakage Rate Test ML20150C2841987-12-31031 December 1987 Test Rept on Electrical Separation Verification Testing for Southern Co Svcs for Use in Vogtle Electric Generating Station ML20236V5731987-11-30030 November 1987 Suppl 1 to Initial Startup Rept for Vogtle Unit 1, for 870801-1115 ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20237J5311987-07-31031 July 1987 Initial Startup Rept for Vogtle Unit 1, for 870116-0731 ML20235H5201987-06-17017 June 1987 Rev 1 to Dynamic Testing of Flexibly Supported Fire Protection Sys-Vogtle Unit Ii. W/Three Oversize Drawings ML20215C3671987-06-0909 June 1987 Addenda to Preoperational Integrated Leak Rate Test Final Rept ML20212B1441986-10-22022 October 1986 Loss of Offsite Power Transient Test of Nuclear Svc Cooling Water Sys ML20213G2911986-10-13013 October 1986 Prototype Bellows Test Rept for Georgia Power,Waynesboro, Ga ML20215G0701986-10-10010 October 1986 Rev 1 to Addendum 1 to Nuclear Environ Qualification Rept of Isolation Device Panels for Aw Vogtle Nuclear Plant,Units 1 & 2,Georgia Power Co ML20211P8991986-08-31031 August 1986 Reactor Containment Bldg Integrated Leakage Rate Test,Aug 1986, Final Rept ML20207B8571986-06-18018 June 1986 Rev a to Test Rept on Electrical Separation Verification Testing for Bechtel Power Corp for Use in Georgia Power Co Vogtle Electric Generating Station ML20215F7361986-05-22022 May 1986 Electrical & Temp Test Rept of 7.5 Kva Cvs Transformer ML20195F2301986-04-14014 April 1986 Fire Test of 3 H Curtain Type Fire Damper Utilizing Alternate Methods of Installation ML20195F2231986-03-13013 March 1986 Fire Test of 3 H Curtain Type Fire Damper Utilizing Alternate Methods of Installation ML20098H0131984-09-30030 September 1984 Rept on Confirmatory Lab Testing Program for Category 1 Backfill ML20207H7971984-05-0404 May 1984 Rev 3 to Functional Test Procedures & Results for Isolation Boards Used in Vogtle 1 & 2 ML20207H8051984-05-0404 May 1984 Rev 1 to Surge Withstand Capability Test Procedure & Results. Related Info Encl ML20153C4971984-04-25025 April 1984 Mine Safety Appliances GMR-1 Canister for Use Against Radio Iodine & Organic Iodides ML20155H1561980-11-0707 November 1980 Qualification Test Rept for 20-Inch Type 9200 Butterfly Valve W/Bettis Actuator 1998-01-16
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i ' Georgte Power Company l~
.d 333 Piedmont Avenue -
f' Atlanta. Georgia 30308 -
.,:: ' Teephono 404 526 3195
. Maiting /ddress' . .
40 inverness Center Parkway .
- Post ORce Dox 1295 Domingham, Nabama 06201 Telephone 205 608 5501 -
-May:11, 1990 n, mo,,,,n marc mm,n W. G. Hairston, til Serwor Vco Presdent Nuclear Operat ons ELV-01635 ;
0380 ;
Docket No. 50-425 U. S. Nuclear Regulatory Commission ATTN: - Document Control: Desk Washington, D. C. 20555 Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT THIRD-SUPPLEMENT TO
SUMMARY
REPORT OF STARTUP TEST PROGRAM In accordance with Technical Specification 6.8.1.1, attached is the-third supplement to the initial startup-report which-was submitted by letter ELV-00789 ~!
dated August 21, 1989. !
i If you have any questions, please contact this office. '! 4 Sincerely, j fod
'W. G.-Hairsto ,'III i WGH,III/NJS/gm Attachment xc: Georaia Power Comoany Mr.-C. K. McCoy Mr. G. Bockhold, Jr.
Mr. P. D. Rushton Mr. R. M. Odom "
NORMS U. S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional- Administrator i Mr. T. A.- Reed, Licensing Project Manager, NRR Mr. R. F.- Aiello, Senior Resident Inspector, Vogtle
[0051503249005,1y p,DR ADOCK 05000425 PDC .
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V0GTLE ELECTRIC GENERATING' PLANT - UNIT 2 .
THIRD SUPPLEMENT TO
SUMMARY
REPORT OF STARTUP TEST PROGRAM i
This third supplement to the initial startup report addresses the remaining startup test that was incomplete at the time of submittal of the initial startup :
report,
- The test is identified according to the section numbering scheme used in the initial report.. The test procedure number is provided in parenthesis.
7.6.10 Thermal Expansion Test (2-600-11)
The only remaining' testing to be completed consists of cold post-test readings :
which require the plant-to be in a cold shutdown condition. The readings will l be performed during the Unit 2 refueling outage under Procedure 2-600-11.
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ADMINISTRATIVE CONTROLS
, h 6.8 REPORTING REQUIREMENTS I ROUTINE REPORTS 6.B.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional
( Administrator of the Regional Office of the NRC unless otherwise noted.
STARTUP REPORT 6.8.1.1 A-summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to I the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of either unit.
The initial Startup Report shall address each of the startup tests iden-tified in the Final Safety Analysis Report and shall include a description of .
the measured values of the operating conditions or characteristics obtained during the test program and a comparison of ~ these values with design predictions and specifications. Any corrective actions Any that were required to obtain satis-additional specific details !
factory operation shall also be described. !
required in license conditions based on other commitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to demonstrate the acceptability of changes and/or modifications.
g Startup Reports shall be submitted within: (1) 90 days following comple-tion of the Startup Test Program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all.three events (i.e., initial criticality, completion of Startup Test Program, and resumption e commencement of commercial operation), supplementary. reports shall be submitted 'at least every 3 months until all three . events have been completed.
ANNUAL REPORTS **
6.8.1.2 Annual Reports cover ms the activities of the plant as described below q
/ for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year
. following initial criticality.
Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of plant, utility, 4 and other personnel (including contractors) receiving exposures
( greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions * (e.g., reactor operations and
- This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
- A single submittal may be made for Units 1 and 2. The submittal should
{ combine those sections that are common to both units at the plant.
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V0GTLE UNITS - 1 & 2 6-17
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