|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217N3471999-10-25025 October 1999 Safety Evaluation Supporting Amends 109 & 87 to Licenses NPF-68 & NPF-81,respectively ML20217B6621999-09-30030 September 1999 Safety Evaluation Supporting Amends 108 & 86 to Licenses NPF-68 & NPF-81,respectively ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20206E1261999-03-26026 March 1999 Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-68 & NPF-81,respectively ML20203F6621999-02-0808 February 1999 Safety Evaluation Supporting Amends 106 & 84 to Licenses NPF-68 & NPF-81,respectively ML20202H8521999-01-29029 January 1999 Safety Evaluation Supporting Amends 105 & 83 to Licenses NPF-68 & NPF-83,respectively ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20202B3071999-01-22022 January 1999 Safety Evaluation Supporting Amends 104 & 82 to Licenses NPF-68 & NPF-81,respectively ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20236S2571998-07-21021 July 1998 Safety Evaluation Supporting Amends 103 & 81 to Licenses NPF-68 & NPF-81,respectively ML20236F8961998-06-29029 June 1998 Safety Evaluation Supporting Amends 102 & 80 to Licenses NPF-68 & NPF-81,respectively ML20248H8531998-06-0101 June 1998 Safety Evaluation Supporting Amends 101 & 79 to Licenses NPF-68 & NPF-81,respectively ML20247M7701998-05-20020 May 1998 Safety Evaluation Supporting Amends 100 & 78 to Licenses NPF-68 & NPF-81,respectively ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216B0851998-03-0505 March 1998 SER Approving Exemption from Requirements of 10CFR50.71(e)(4) Updates to Final Safety Analysis Rept for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H6511998-02-20020 February 1998 Safety Evaluation Supporting Amends 99 & 77 to Licenses NPF-68 & NPF-81,respectively ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20198T3621997-10-24024 October 1997 Safety Evaluation Authorizing Supporting Second 10-year Interval ISI Program Requests for Relief RR-17 & RR-25 as Submitted by Southern Nuclear Operating Co on 970529 ML20210R2071997-08-27027 August 1997 Safety Evaluation Accepting Relief Requests for Pump & Valve Inservice Testing Program ML20210R2561997-08-26026 August 1997 Safety Evaluation Supporting Amends 98 & 76 to Licenses NPF-68 & NPF-81,respectively ML20137B2901997-03-17017 March 1997 Safety Evaluation Supporting Amends 97 & 75 to Licenses NPF-68 & NPF-81,respectively ML20128H5621996-09-25025 September 1996 Safety Evaluation Supporting Amends 96 & 74 to Licenses NPF-68 & NPF-81,respectively ML20117E9041996-08-28028 August 1996 Safety Evaluation Supporting Amends 95 & 73 to Licenses NPF-68 & NPF-81 ML20097B7821996-02-0202 February 1996 Safety Evaluation Supporting Amends 93 & 71 to Licenses NPF-68 & NPF-81,respectively ML20094M5221995-11-17017 November 1995 Safety Evaluation Supporting Amends 91 & 69 to Licenses NPF-68 & NPF-81,respectively ML20091R4031995-08-29029 August 1995 Safety Evaluation Supporting Amends 90 & 68 to Licenses NPF-68 & NPF-81,respectively ML20086G9221995-07-0707 July 1995 Safety Evaluation Supporting Amends 89 & 67 to Licenses NPF-68 & NPF-81,respectively ML20086E2451995-07-0303 July 1995 Safety Evaluation Supporting Amends 88 & 66 to Licenses NPF-68 & NPF-81,respectively ML20085F8861995-06-0808 June 1995 Safety Evaluation Supporting Amends 87 & 65 to Licenses NPF-68 & NPF-81,respectively ML20084R7761995-05-31031 May 1995 Safety Evaluation Supporting Amends 86 & 64 to Licenses NPF-68 & NPF-81,respectively ML20083M5951995-05-15015 May 1995 Safety Evaluation Supporting Amends 85 & 63 to Licenses NPF-68 & NPF-81,respectively ML20082S3861995-04-27027 April 1995 Safety Evaluation Supporting Amends 84 & 62 to Licenses NPF-68 & NPF-81,respectively ML20078C9091995-01-23023 January 1995 Safety Evaluation Supporting Amends 83 & 61 to Licenses NPF-68 & NPF-81,respectively ML20078C3781995-01-20020 January 1995 Safety Evaluation Supporting Amends 82 & 60 to Licenses NPF-68 & NPF-81,respectively ML20078C4341995-01-20020 January 1995 Safety Evaluation Supporting Amend 81 to License NPF-68 ML20077S6221995-01-12012 January 1995 Safety Evaluation Supporting Amends 80 & 59 to Licenses NPF-68 & NPF-81,respectively ML20077S6811995-01-11011 January 1995 Safety Evaluation Supporting Amends 79 & 58 to Licenses NPF-68 & NPF-81,respectively ML20077K4361995-01-0505 January 1995 Safety Evaluation Supporting Amends 77 & 78 to License NPF-68 & Amends 56 & 57 to License NPF-81,respectively ML20149G1801994-09-22022 September 1994 Safety Evaluation Supporting Issuance of Amends 76 & 55 to Licenses NPF-68 & NPF-81,respectively ML20073G4111994-09-21021 September 1994 Safety Evaluation Supporting Amends 75 & 54 to Licenses NPF-68 & NPF-81,respectively ML20069J3541994-06-0101 June 1994 Safety Evaluation Supporting Amends 74 & 53 to Licenses NPF-68 & NPF-81,respectively ML20069H1141994-06-0101 June 1994 Safety Evaluation Supporting Amends 73 & 52 to Licenses NPF-68 & NPF-81,respectively ML20069J3811994-05-31031 May 1994 Safety Evaluation Supporting Amends 72 & 51 to Licenses NPF-68 & NPF-81,respectively ML20070N9441994-05-0202 May 1994 Safety Evaluation Supporting Amends 71 & 50 to Licenses NPF-68 & NPF-81,respectively NUREG-1216, Safety Evaluation Accepting Tdi Engine Operation at Authorized Loads Under Normal NRC Regulatory Oversight Procedures for EDGs1994-03-17017 March 1994 Safety Evaluation Accepting Tdi Engine Operation at Authorized Loads Under Normal NRC Regulatory Oversight Procedures for EDGs ML20058A3041993-11-19019 November 1993 Safety Evaluation Re Accumulator Pressure & Vol Instrumentation of Reg Guide 1.97 Environ Qualification Requirements,Per Generic Ltr 82-33.Category 3 Qualification of Instrumentation Acceptable ML20062J8641993-11-10010 November 1993 Safety Evaluation Denying Licensee 920617 Request for Amends to License Changing TS 3/4.6.1.7 & 4.6.1.2f for Plant ML20059J0061993-11-0303 November 1993 Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3471999-10-25025 October 1999 Safety Evaluation Supporting Amends 109 & 87 to Licenses NPF-68 & NPF-81,respectively 05000424/LER-1999-003-02, :on 990922,CR Door Painting Resulted in Loss of Positive Pressure Boundary.Caused by Inadequate pre-job Briefing.Doors Were Closed Upon Discovery by CR Personnel. with1999-10-22022 October 1999
- on 990922,CR Door Painting Resulted in Loss of Positive Pressure Boundary.Caused by Inadequate pre-job Briefing.Doors Were Closed Upon Discovery by CR Personnel. with
ML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217B6621999-09-30030 September 1999 Safety Evaluation Supporting Amends 108 & 86 to Licenses NPF-68 & NPF-81,respectively ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With 05000424/LER-1999-002-03, :on 990630,high-energy Line Break Instrument Channels Were Inadequately Calibrated.Caused by Inadequate Surveillance Testing Procedures.Procedure Revs to Add Relay Testing in Progress.With1999-07-30030 July 1999
- on 990630,high-energy Line Break Instrument Channels Were Inadequately Calibrated.Caused by Inadequate Surveillance Testing Procedures.Procedure Revs to Add Relay Testing in Progress.With
ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr 05000425/LER-1999-001-03, :on 990302,reactor Trip Occurred When Personnel Were Installing Clearances in Wrong Unit.Caused by Inappropriate Work Practices.Various C/As Addressing Human Performance Are Being Implemented.With1999-03-31031 March 1999
- on 990302,reactor Trip Occurred When Personnel Were Installing Clearances in Wrong Unit.Caused by Inappropriate Work Practices.Various C/As Addressing Human Performance Are Being Implemented.With
ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20206E1261999-03-26026 March 1999 Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-68 & NPF-81,respectively ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20203F6621999-02-0808 February 1999 Safety Evaluation Supporting Amends 106 & 84 to Licenses NPF-68 & NPF-81,respectively ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20202H8521999-01-29029 January 1999 Safety Evaluation Supporting Amends 105 & 83 to Licenses NPF-68 & NPF-83,respectively 05000424/LER-1998-009-01, :on 981229,improper Testing Method Resulted in Inadequate Surveillances.Caused by Inadequate Tps.Revised Procedures 14825-1/2 to Instruct Operators to Utilize Position Indicators When Testing Valves1999-01-27027 January 1999
- on 981229,improper Testing Method Resulted in Inadequate Surveillances.Caused by Inadequate Tps.Revised Procedures 14825-1/2 to Instruct Operators to Utilize Position Indicators When Testing Valves
ML20202B3071999-01-22022 January 1999 Safety Evaluation Supporting Amends 104 & 82 to Licenses NPF-68 & NPF-81,respectively ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage 05000424/LER-1998-007-03, :on 981215,inadequate Surveillances Were Found. Caused by Wiring Error & Improperly Performed Response Time Testing.Wiring Error Corrected & Procedures Changed to Allow Online Testing1999-01-13013 January 1999
- on 981215,inadequate Surveillances Were Found. Caused by Wiring Error & Improperly Performed Response Time Testing.Wiring Error Corrected & Procedures Changed to Allow Online Testing
05000425/LER-1998-010, :on 981209,reactor Overpower Event Following Instrument Calibration Was Noted.Caused by Cognitive Personnel Error.Technician & Assistant Team Leader Involved Have Been Counseled on Procedure Compliance.With1999-01-0707 January 1999
- on 981209,reactor Overpower Event Following Instrument Calibration Was Noted.Caused by Cognitive Personnel Error.Technician & Assistant Team Leader Involved Have Been Counseled on Procedure Compliance.With
ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 05000424/LER-1998-006, :on 981008,MCC Breaker Buckets Were Not Seismically Qualified.Caused by Inadequate Procedural Guidance & Lack of Awareness Re Seismic Restraints.Buckets Were Restored to Acceptable Condition.With1998-12-11011 December 1998
- on 981008,MCC Breaker Buckets Were Not Seismically Qualified.Caused by Inadequate Procedural Guidance & Lack of Awareness Re Seismic Restraints.Buckets Were Restored to Acceptable Condition.With
ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With 05000425/LER-1998-009, :on 981021,trouble Alarm Was Received for Train B ESFAS Sequencer Due to Inoperability.Caused by Inability to Interpret Initial Conditions.Sequencer Was down-powered to Replace Field Buffer Card.With1998-11-18018 November 1998
- on 981021,trouble Alarm Was Received for Train B ESFAS Sequencer Due to Inoperability.Caused by Inability to Interpret Initial Conditions.Sequencer Was down-powered to Replace Field Buffer Card.With
05000424/LER-1998-006-02, :on 981008,auxiliary FW Train B Breaker Buckets Were Not Seismically Qualified.Caused by Personnel Error. Seismic Clips Were Secured & Event Will Be Addressed in Electricians Training.With1998-11-0606 November 1998
- on 981008,auxiliary FW Train B Breaker Buckets Were Not Seismically Qualified.Caused by Personnel Error. Seismic Clips Were Secured & Event Will Be Addressed in Electricians Training.With
ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20154E7241998-09-30030 September 1998 Rev 0 to WCAP-15069, Evaluation of Pressurized Thermal Shock for Vogtle Electric Generating Plant Unit 1 ML20154E7071998-09-30030 September 1998 Rev 0 to WCAP-15067, Analysis of Capsule V from Southern Nuclear Vogtle Electric Generating Plant Unit 1 Reactor Vessel Radiation Surveillance Program 05000425/LER-1998-008, :on 980904,slave Relay Testing Led to Trips of Main FW Pumps & Reactor.Caused by Inherent Design Weakness.Will Modify Test Circuits to Prevent FW Pump Tripping Due to Simultaneous Lamp Testing.With1998-09-28028 September 1998
- on 980904,slave Relay Testing Led to Trips of Main FW Pumps & Reactor.Caused by Inherent Design Weakness.Will Modify Test Circuits to Prevent FW Pump Tripping Due to Simultaneous Lamp Testing.With
05000425/LER-1998-007, :on 980824,loss of FW Flow Led to Manual Reactor Trip.Caused by Consecutive Failures of Primary & Backup Power Supplies to Process Control Rack 3.Repaired Inverter & Replaced Process Control Rack 3.With1998-09-21021 September 1998
- on 980824,loss of FW Flow Led to Manual Reactor Trip.Caused by Consecutive Failures of Primary & Backup Power Supplies to Process Control Rack 3.Repaired Inverter & Replaced Process Control Rack 3.With
05000424/LER-1998-005-02, :on 980824,surveillance Was Not Performed When DG Was Rendered Inoperable.Caused by Failure to Control Amount of Debris at DG Exhaust.Expectations for Controlling Work on SR Sys Were re-emphasized.With1998-09-21021 September 1998
- on 980824,surveillance Was Not Performed When DG Was Rendered Inoperable.Caused by Failure to Control Amount of Debris at DG Exhaust.Expectations for Controlling Work on SR Sys Were re-emphasized.With
ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236S2571998-07-21021 July 1998 Safety Evaluation Supporting Amends 103 & 81 to Licenses NPF-68 & NPF-81,respectively 1999-09-30
[Table view] |
Text
,
a EllCLOSURE SUPPLEllENTAL SAFETY EVALUATION REPORT FOR THE V0GTLE UNIf ?
ELECTRICAL SEPARATION CRITERIA BACKGROUND Vogtle Units 1 and 2 met the standard electrical separation criteria as outlined in IEEE 384-1974 with a few exceptions.
To establish separation distances which deviate from the standard separation distances specified in IEEE 384-1974, (reduced minimum separation) Georgia Power Company (GPC) performed a series of tests and analyses to establish reduced separation distances. This is permitted by IEEE 384-1974 and NRC Regulatory Guide 1.75 -(R.G.1.75).
Vogtle Final Safety Analysis Report (FSAR) Table 8.3.1-4 is the tabulation of alternate reduced minimum separation distances at V'
,e.
In Supplement No. 4 to NUREG-1137, "Safety Evaluation Report rclatei che operation cf Vogtle Electric Generating Plant, Units 1 and 2," (SSER 4) dated December 1986, the NRC staff approved the electrical cable separation criteria util1 zed in the design of Vogtle Units 1 and 2.
Subsequent to the reduced separation testing conducted in 1986, additional j
cable and raceway configurations were identified.
DISCUSSION To establish reduced separation distances for cable and raceway configurations not previously tested or analyzed, GPC through Wyle Laboratories performed a series of testing and analysis.
Ti.ese tests were conducted in accordance with criteria approved by the NRC staff for Vogtle in SSER 4.
In the tests, Yogtle cable configurations were used in the lab to replicate as much as possible the octual field installations.
8807250341 880718 PDR ADOCK 05000425 R
PNU
i
. The test method consisted of setting up cable configurations in which a cable selected on the basis of most severe ignition and fault terrperaturc, is designated as the fault cable. A fault (short circuiting) was applied to this cable until it opened the short circuit.
The effects of this short circuit on cable (desig-noted as target cables) in free air, adjacent trays, or conduits are monitored with thermocouples while energized with conservative values of voltage and current.
In addition the target cable during the tests were monitored for continuity.
After the test the cables were inspected and given an insulation and high potential test. The acceptance criterion for the target cables was the satisfactory comple-6 tion of the insulation resistance (greater than 16 x 10 ohms) and high potential tests (no evidence of insulation breakdown or flashover) with a potential of 7200 VDC applied for 60 seconds and a satisfactory demonstration of the capability of the target cables to conduct 100% of their rated currents before, during, and after the overcurrent test.
The results of the tests are documented in Wyle Laboratories Test Report No. 17959-02 dated December 1987 which was forwarded by GPC to NRC in a letter dated March 14, 1988 (Ref. 1).
GPC submitted in a letter dated June 16, 1988 (Ref. 2) answers and clarifications to the staff questions related to the worst case orientation of the cables, t" peak temperatures measured and insulation resistance tests.
The questions were raised and discussed in a telephone conference between the staff and GPC repre-sentatives on May 25, 1988.
l t
CONCLUSION 1
All the cable tested met the acceptance criteria.
For one configuration (Test 1/2), the 2/C No. 14 AWG cable jacket was blistered for 4" near the end of the rigid conduit. No cracks or openings were observed and the cable passed the ar.ceptance criteria.
i
. The NRC staff has reviewed the test results and clarifications submitted by GPC and find that_ they provide a satisfactory basis for minimun separation distances for ccbles and raceways specified in the revised FSAR Table 8.3.1-4 for Vogtle Unit 2.
As stated in the NRC staff. letter to GPC, dated April 22, 1988 (Ref. 3), the application of these electrical separation criteria to Vogtle Unit 1 is subject to the requirements of 10 CFR 50.59.
Principal Contributors:
S. N. Saba, Electrical Systems Branch J. B. Hopkins, Project Directorate II-3 REFERENCES 1.
Letter to Document Centrol Desk, USNRC from J. A. Bailey, Project Licensing Manager, Georgia Power Company, "Plant Vogtle Units 1 and 2, NRC Docket 50-424, 50-425, Operating License ITF-68, Construction Permit CPPR-109, Electrical Separation Criteria", dated March 14, 1988, 2.
Letter to Document Control Desk, USNRC from J. A. Bailey, Project Licensing Manager, Georgia Power Company, "Plant Vogtle - Units 1 and 2, NRC Dockets 50-424, 50-425, Operating License NPF-68, Construction Permit CPPR-109 Electrical Separation Criteria", dated June 16, 1988.
3.
Letter to George F. Head, GPC from Jon B. Hopkins, NRC, dated April 22, 1988.
1 i