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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML17313A6701998-11-0404 November 1998
Rev 2 to PVNGS Unit 2 Colr.
ML20151S0861998-08-21021 August 1998
Rev 4 to COLR for PVNGS Unit 1
ML20151S0901998-08-21021 August 1998
Rev 1 to COLR for PVNGS Unit 2
ML20151S0941998-08-21021 August 1998
Rev 6 to COLR for PVNGS Unit 3
ML17313A4521998-06-19019 June 1998
Rev 5 to COLR for Pvngs,Unit 3.
ML17313A4501998-06-19019 June 1998
Rev 4 to COLR for Pvngs,Unit 3.
ML17313A1941998-01-27027 January 1998
Rev 2 to COLR for Pvngs,Unit 1.
ML17312B7211997-10-0303 October 1997
Rev 0 to PVNGS Unit 2,COLR.
ML17312B6011997-07-30030 July 1997
Rev 3 to PVNGS Unit 2 Cycle 7 Colr.
ML17312B6021997-07-30030 July 1997
Rev 3 to Unit 3 PVNGS Colr.
ML17312B6001997-07-30030 July 1997
Rev 2 to PVNGS Unit 2 Cycle 7 Colr.
ML17312B5991997-07-30030 July 1997
Rev 1 to PVNGS Unit 1 Colr.
ML17312B3821997-03-10010 March 1997
COLR PVNGS Unit 3, Rev 0
ML17312B1121996-11-0808 November 1996
Rev 0 to COLR Palo Verde Nuclear Generating Station Unit 1.
ML17312A8301996-06-28028 June 1996
Rev 1 to PVNGS Unit 2 Cycle 7 Colr.
ML17312A5211996-02-0101 February 1996
Rev 2 to COLR PVNGS Unit 3 Cycle 6.
ML17312A5281995-12-14014 December 1995
COLR PVNGS Unit 1 Cycle 6, Rev 1
ML17312A5301995-12-14014 December 1995
COLR PVNGS Unit 3,Cycle 6, Rev 1
ML17312A5291995-12-14014 December 1995
Colr,Pvngs,Unit 2 Cycle 6, Rev 1
ML17311A7961995-04-10010 April 1995
Rev 0 to Core Operating Limits Rept for Pvngs,Unit 2,Cycle 6.
ML17311A5451994-11-0909 November 1994
Revised Pages to Rev 3 of PVNGS Unit 3 Cycle 5 Colr.
ML17311A5411994-11-0909 November 1994
Revised Pages to Rev 3 of PVNGS Unit 1 Cycle 5 Colr.
ML17311A5431994-11-0909 November 1994
Revised Pages to Rev 4 of PVNGS Unit 2 Cycle 5 Colr.
ML17310B3471994-06-0202 June 1994
Rev 1 to COLR PVNGS for Units 1 & 2 Cycle 5.
ML17310B3101994-05-18018 May 1994
COLR PVNGS Unit 3 Cycle 5, Rev 1
ML17310B1601994-03-25025 March 1994
PVNGS Rev 1 to Unit 2,Cycle 5 Core Operating Limits Rept.
ML17310A7521993-10-29029 October 1993
Rev 0 to COLR for Pvngs,Unit 1 Cycle 5.
ML20091A4971992-03-19019 March 1992
Core Operating Limits Rept,Palo Verde Nuclear Station,Unit 1,Cycle 3
ML17305B3761991-02-21021 February 1991
Reload Analysis Rept for Palo Verde Nuclear Generating Station,Unit 3,Cycle 3.
ML17305A6911990-04-16016 April 1990
Revised Reload Analysis Rept,Unit 2,Cycle 3 Consisting of Changes to Sections 1,2 & 3,Pages 1-1,2-1,3-1,3-2,3-4,3-5 & 5-1
ML17305A4921990-01-25025 January 1990
Rev to Section 3 of Reload Analysis Rept
ML17305A3491989-10-24024 October 1989
Cycle 3 Reload Analysis Rept.
ML17304B1831989-05-11011 May 1989
Revised Pages to Final Reload Analysis Rept for Facility Cycle 2
ML17304A9771989-01-18018 January 1989
Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 1 Cycle 3.
ML17303A7221987-12-0303 December 1987
Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 2,Cycle 2.
ML17300A9561987-06-29029 June 1987
Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 1 Cycle 2.
1998-08-21
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr
ML17300B3271999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3
ML17313B0751999-08-27027 August 1999
LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr
ML17313B0611999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr
ML17313B0191999-07-16016 July 1999
LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure
ML17300B3151999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr
ML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A9731999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr
ML17313A9281999-05-0707 May 1999
LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs
ML17313A9201999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr
ML17313A8951999-04-14014 April 1999
LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked
ML17313A8921999-04-13013 April 1999
LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc
ML17313A8891999-04-0909 April 1999
LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr
ML17300B3071999-03-31031 March 1999
Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee.
ML17313A8801999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207H7471999-03-10010 March 1999
1999 Emergency Preparedness Exercise 99-E-AEV-03003
ML17313A8361999-03-0101 March 1999
LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr
ML17313A8501999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr
ML17313A7791999-02-0505 February 1999
Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies
ML17313A8061999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr
ML17313A7701999-01-15015 January 1999
LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised
ML17313A7381998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr
ML20206H2101998-12-31031 December 1998
SCE 1998 Annual Rept
ML17313A7031998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr
ML17313A6701998-11-0404 November 1998
Rev 2 to PVNGS Unit 2 Colr.
ML17313A6741998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr
ML17313A6611998-10-24024 October 1998
LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements
ML17313A6561998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr
ML17313A5961998-09-14014 September 1998
LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired
ML17313A5761998-09-0808 September 1998
LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters
ML17313A5591998-08-28028 August 1998
LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr
ML20151S0941998-08-21021 August 1998
Rev 6 to COLR for PVNGS Unit 3
ML20151S0861998-08-21021 August 1998
Rev 4 to COLR for PVNGS Unit 1
ML20151S0901998-08-21021 August 1998
Rev 1 to COLR for PVNGS Unit 2
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A5301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr
ML17313A5201998-07-30030 July 1998
LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr
ML17313A5791998-07-0707 July 1998
to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998.
ML17313A5001998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr
ML17313A4671998-06-19019 June 1998
LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced
ML17313A4521998-06-19019 June 1998
Rev 5 to COLR for Pvngs,Unit 3.
ML17313A4501998-06-19019 June 1998
Rev 4 to COLR for Pvngs,Unit 3.
ML17313A4131998-06-0505 June 1998
LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria
ML17313A4211998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr
ML17313A3951998-05-26026 May 1998
LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation
ML17313A3691998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr
ML17313A3251998-04-0101 April 1998
LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
1999-09-30
[Table view] |
Text
Revision 2 Pages Unit 2 COLR 9708050254 9'70730 PDR ADQCK 05000528
'DR P
CORE OI EmxING uMnS RZI ORr PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 2 CYCLE 7 Revision 2 Page 1 of 23
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t PVNGS UNIT 2 CYCLE 7 CORK OPERATING LIMITSREPORT Table of Contents l Revision 2
~Descri tion Revision ¹ ~Pa e Cover Page Table of Contents Affected Technical Specifications CORE Operating Limits 3.1.1.1 Shutdown Margin - Reactor Trip Breakers Open 3.1.1.2 Shutdown Margin - Reactor Trip Breakers Closed 3.1.1.3 Moderator Temperature Coefficient 3.1.2.7 Boron Dilution Alarms 3.1.3.1 Movable Control Assemblies - CEA Position 3.1.3.6 Regulating CEA Insertion Limits 3.1.3.7 Part Length CEA Insertion Limits 3.2.1 Linear Heat Rate 3.2.3 Azimuthal Power Tilt - Tq 3.2.4 DNBR Margin 3.2.7 Axial Shape Index 3.9.1 Boron Concentration (Mode 6)
List of Figures Figure 3.1.1.1-1 Shutdown Margin Versus Cold Leg Temperature 7a Reactor Trip Breakers Open Figure 3.1.1.2-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed Figure 3.1.1.3-1 MTC Acceptable Operation, Modes 1 and 2 Figure 3.1.3.1-1 Core Power Limit After CEA Deviation 10 Figure 3.1.3.6-1 CEA Insertion Limits Versus Thermal Power (COLSS in Service)
Figure 3.1.3.6-2 CEA Insertion Limits Versus Thermal Power 12 (COLSS Out of Service)
Figure 3.1.3.7-1 Part Length CEA Insertion Limits Versus Thermal Power 0 13 Page 2 of 23
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t PVNGS UNIT 2 CYCLE 7 CORE OPERATING LIMITS RE<PORT Table of Contents (Continued) t Revision 2
~Deecri <ion Revision 0 ~Pa e Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 14 (COLSS in Service)
Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 15 CEAC's Inoperable Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 16 Protection Calculators (COLSS Out of Service, CEAC's Operable)
Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 17 Protection Calculators (COLSS Out of Service, CEAC's Inoperable)
List of Tables Table 3.1.2.7-1 Required Monitoring Frequencies for Backup Boron 19 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.1.2.7-2 Required Monitoring Frequencies for Backup Boron 20 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.1.2.7-3 Required Monitoring Frequencies for Backup Boron 21 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Table 3.1.2.7-4 Required Monitoring Frequencies for Backup Boron 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Table 3.1.2.7-5 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps
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and Plant Operational Modes for Keff 0.95 Page 3 of 23
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Revision 2 PVNGS UNIT 2 CYCLE 7 CORE OPERATING LIMITS REPORT RK PERATIN I IMIT, - TIN KD 3.1.1.3 - Moderator Tem erature CoefFicient The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.1.3-1.
8.1.2.7 - Boron Dilution Alarms With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.1.2.7-1 through 3.1.2.7-5.
3.1.3.1 - Movable ntrol Assemblies - CEA Position With one or more full-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.3.1-1.
3.1.3.6 - Re atin EA Insertion Limits One or more CEAC's OPERABLE: With COLSS IN SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 3.1.3.6-1; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 3.1.3.6-2.
8.1.3.7- Part Len h EA Insertion Limits One or more CEAC's OPERABLE: The part length CEA groups shall be limited to the insertion limits shown in Figure 3.1.3.7-1.
8.2.1 - Linear Heat Rate The linear heat rate limit of 18.3 kW/ft shall be maintained.
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