|
---|
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
[Table view] |
Text
N ' l. - ..
- 7. ..
'.s GeorgiaPower b l
' ENCLOSURE. 6 PLANT V0GTLE - UNIT ~1 'l NRC DOCKET 50-424 OPERATING LICENSE NPF-68 ADDENDA TO PREOPERATIONAL INTEGRATED :
LEAK RATE TEST FINAL REPORT !
l The addenda' to the Vogtle Unit 1 Preoperational Integrated Leak Rate Test
[
Final. Report submitted:to the NRC.by. Georgia Power Company letter GN-1225' :1
-dated December 12, 1986 should be. incorporated:as follows: !
Remove Page~ Insert-Pace 1 6' 6 7' 7 8 8 i
i I
-l l
l e
i i
0335m . E-1 06/09/87 SL-2613 , ,. ,
8706180008 8706093:
ADOCK 05000424 .j
.PDR P PDR, i b 70775 '.
[ ,
3 ..
- . .}
Georgia'PowerA.
ENCLOSURE i?
PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF d ADDENDA TO PRE 0PERATIONAL INTEGRATED LEAK RATE TEST FINAL REPORT. -l The addenda ~ to the Vogtle Unit 1 Preoperational Integrated Leak Rat'e . Test.
Final Report submitted to the NRC by Georgia Power Company letter GN-1225 dated December 12, 1986 should be incorporated as follows:
Rgmove Paae Insert Paae 6 6 7 7 8 8 4
i 0335m 06/09/87 SL-2613
- 700776 '
9 .
q i
- 11. Penetrations not in post-LOCA Alignment During ILET Penetration System Leakage Rate l l
Elect. #35 ILPT Pressure Sensing 1.25 SCCM FSA 20.2 68 4.2 86C 20.5 87 5.2 Total 51.35 SCCM i 3.4 Integrated Leakage Rate Measurement S,ystem a i
Instrument Description Data (No. of sensors) l
- 1. Absolute Mensor Range: 0-100 psia !
Pressure Quartz Monometer Accuracy: +0.0154 Read j (2) +0.002*FS Sensitivity: +0.00lpsia Repeatability: +0.00lpsia l l
I
- 2. Drybulb Platinum Range (Calib): 60-120degF Temperature Accuracy: +0.ldegF ;
(30) Sensitivity: +0.0ldegF i Repeatability: +0.OldegF
- 3. Dewpoint Chilled Mirror Range (Calib): 40-100degF ,
Temperature Accuracy: +.54degF l (6) Sensitivity: +0.ldegF Repeatability: +0.OldegF
- 4. Flow Meter Differential Press Range: 0-20 SCFM ;
(1) Accuracy: +0.1%
Repeatability: +0.254 Drybulb and dowpoint temperature sensor locations and volume fractions are provided in Table 1.
3.5 Type B & Type C Leakage Rate Results These results of the various respective tests per procedure (see refer'ence 8) are presented below.
Pene. Meas.SCCM (Max. Path) llA 747 12A 36.6
138 7700
- Indicates an update in the measured leakage.
6
r .
Pene. Measured 1 22 1760
28 940
34 545
50 1092
67.2
]
)'
64A 6 648 6 67A 16860
- 678 11.1 68 4.22 I 69A 22.9 698 1480
- t 70A 4.4 70B 3720 11A 15.58*
718 166.3 72A 63.8 728 6 73A 509 733 6 77 22 78 108.3 79 6 80 175.8*
81 89.5 83 533
86A 5770
87 6 89 2.2*
100 306 Pene. Meas. SCCM Pers. Hatch 970.2*
Escape Lock 125.8*
Equip. Hatch 2.2*
Elec. Pene 27.19* '
Encap. Vessels 148.9 ** ;
Total 47,332.79 SCCM or 1.6715SCFM or .10790La
- Indicates an update in the measured leakage.
- Indicates additional leakage path not originally included.
7-
4.0 ANALYSIS AND INTERPRETATION I
4.1 ILRT Test During the ILRT, five penetrations were not in post-LOCA alignment.
The total leakage rate correction for penetrations not in post-LOCA alignment and water level changes (insignificant - 2cf per. total time period) is 0.00002%/ day. i The calculated. leakage rates during the Type A for LSF and 95% UCL are shown below. Adding the total leakage rate corrections for penetrations not in post-LOCA alignment yields the corrected , leakage t rates as follows: 1 Mass Point Total Time ' !
LSF UCL LSF UCL Calculated 0.02397 0.02487 0.0236 0.02641 j Corrections 0.00002 0.00002 0.00002 0.00002 Corrected 0.02399 0.02489 0.02362 0.02643 l)
Since the corrected 95% upper confidence levels for mass point (and total time) are less than .75La (0.150%/ day), the -test results demonstrate the leakage through. the primary containment and systems is within allowable limi ts. Components penetrating primary containment' do not exceed . maximum leakage rates specified in the Vogtle Nuclear Power Plant Unit 1 FSAR and Technical. Specifications.
4.2 Instrumentation, Data and Calculations ILRT test data were gathered through sensors and a data acquisition system. The data acquisition system' received these inputs and transmitted them into a mini-computer which reduced the raw data to containment 1 (See Appendix A for a software program description. ) .eakage.
4.2.1 Instrumentation The instrumentation was chosen for its stability and.
dependability. The instrumentation used during the- ILRT satisfied all Instrument Selection GuideJ requirements. All' instrumentation performed adequately during the test.
4 8
_