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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
rom OI EmxINC uMnS azI oar PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT S CVCLE 6 Revision 1 9b02150113 9b0119 PDR ADOCK 05000528 P PDR
Revision 1 CORK OPERATING LIMITS REPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 1 CYCLE 6 REVISION HISTORY Revision Date ~Pa es 4/24/95 Issue for Use (23 Total Pages) 12/14/95 Replace pages 1,3,4,6,7,8,9.
(23 Total Pages)
Page 3 of 23
j Revision 1 CORE OPERATING LIMITSREPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)
UNIT 1 CYCLE 6 This Core Operating Limits Report for PVNGS Unit 1 Cycle 6 has been prepared in accordance with the requirements of Technical Specification 6.9.1. The core operating limits have been developed using the NRC approved methodologies specified in Section 6.9.1.10 of the Palo Verde Unit 1 Technical Specifications.
AI I'E TED PV TE HNI AL PE IFI ATI N
- 1) 3.1.1.2 Shutdown Margin - Reactor Trip Breakers Closed
- 2) 3.1.1.3 Moderator Temperature Coefficient
- 3) 3.1.2.7 Boron Dilution Alarms
- 4) 3.1.3.1 Movable Control Assemblies - CEA Position
- 5) 3.1.3.6 Regulating CEA Insertion Limits
- 6) 3.1.3.7 Part Length CEA Insertion Limits
- 7) 3.2.1 Linear Heat Rate
- 8) 3.2.3 Azimuthal Power Tilt - Tq
- 9) 3.2.4 DNBR Margin
- 10) 3.2.7 Axial Shape Index
- 11) 3.9.1 Boron Concentration RE PER TI v I.IVIITS The cycle-specific operating limits for the specifications listed are presented below.
3.1.1.2 - Shutdown Mar 'n - Reactor Tri Breakers losed The Shutdown Margin shall be greater than or equal to that shown in Figure 1.
.1. - Moderator Tem erature Coefficient The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown on Figure 2.
Page 4 of 23
1 1 PVNGS UNIT 1 CYCLE 6 CORE OPERATING LIMITSREPORT Revision 1 RE PERATIN LI IT - NTIN ED 3.2.4- DNBR Mar 'n COLSS IN SERVICE and Both CEAC's INOPERABLE - Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 8.
COLSS OUT OF SERVICE and Either One or Both CEAC's are OPERABLE - Operating within the region of acceptable operation of Figure 9 using any operable CPC channel.
COLSS OUT OF SERVICE and CEAC's INOPERABLE - Operating within the region of acceptable operation of Figure 10 using any'operable CPC channel.
3.2.7- Axial Sha e Index The core average ALGALSHAPE INDEX (ASI) shall be maintained within the following limits:
COLSS OPERABLE
-0.28 < ASI < 0.26 COLSS OUT OF SERVICE (CPC)
-0.20 < ASI < 0.20 3.9. - Boron oncentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform
,concentration greater than or equal to 2350 ppm.
Page 6 of 23
l ~
Revision 1 PVNGS UNIT 1 CYCLE 6 CORE OPERATXNG LIMITSREPORT r~rY rWr aa
- 1. Shutdown Margin Versus Cold Leg Temperature, Reactor Trip Breakers Closed )
1
- 2. MTC Acceptable Operation, Modes 1 and 2.
- 3. Core Power LimitAfter CEA Deviation.
- 4. CEA Insertion Limits Versus Thermal Power (COLSS In Service).
- 5. CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)
- 6. Part Length CEA Insertion LimitVersus Thermal Power.
- 7. Azimuthal Power Tilt LimitVersus Thermal Power (COLSS In Service).
- 8. COLSS DNBR Power Operating LimitAllowance for Both CEACs Inoperable.
- 9. DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEACs Operable) 10.DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEACs Inoperable)
Page 7 of 23
l~
I')
Revision I I
PVNGS UNIT 1 CYCLE 6'CORE OPERATING LIMITSREPORT FIGURE 1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE Reactor Trip Breakers Closed (500, 6.5 5
ACCEPTABLE A 4 (350 4.0)
~C) z Q
'1 2
z REGI N OF 0
A OPE TION D 2 100 200 300 400 500 600 COLD LEG TEMPERATURE ( F)
Page 8 of 23
J lt
0.5 ech. Spec. 3.1.1.3 aximum Upper imit (100%, 0.0)
(0%, 0.3) p (20%, 0.1)
(50%, 0.0) -R Q
o p 5 (100%, -0.5) R Beginning of Cycle limit g
R j
0U MTC AREA OF 6 0
a". ACCEPTABLE A
OPERATION
-2 0 0 P5 g -2.5 0 R Q
C4 R 0 3 (0%, -3.1) End of Cycle limit 0 g
Cl 0 -3.5 (100%, -3.8) 0
-4.0 I
~
I I I I I 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,% OF RATED THERMALPOWER
r 1
l II
