|
---|
Category:MONTHLY OPERATING ANALYSIS 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 ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With ML17313A9201999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With ML17313A8801999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr ML17313A8501999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With ML17313A7381998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6741998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With ML17313A6561998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr ML17313A5301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr ML17313A5001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr ML17313A4211998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3 ML17313A3691998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for PVNGS ML17313A3461998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for PVNGS Units 1,2 & 3.W/980408 Ltr ML17313A2521998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980311 Ltr ML17313A2061998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Palo Verde Nuclear Generating Station,Unit 1,2 & 3.W/980210 Ltr ML17313A1811997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Palo Verde Nuclear Generating Station,Units 1,2 & 3 ML17313A1351997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Palo Verde Nuclear Generating Station,Units 1,2 & 3 ML17313A1821997-11-30030 November 1997 Revised Monthly Operating Rept for Nov 1997 for Palo Verde Nuclear Generating Station,Unit 3 ML17312B7521997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/971112 Ltr ML17312B6641997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for Pvngs,Units 1,2 & 3 ML17313B0621997-07-31031 July 1997 Monthly Operating Repts for July 1997 for Pvngs,Units 1,2 & 3.With 970812 Ltr ML17312B1741996-12-31031 December 1996 Monthly Operating Repts for Dec 1996 for Pvngs,Units 1,2 & 3.W/970109 Ltr ML17312A9981996-09-30030 September 1996 Monthly Operating Repts for Sept 1996 for PVNGS Unit 1,2 & 3 ML17312A9681996-08-31031 August 1996 Monthly Operating Repts for Aug 1996 for Palo Verde Nuclear Generating Station Units 1,2 & 3.W/960911 Ltr ML17312A9181996-07-31031 July 1996 Monthly Operating Repts for July 1996 for Pvngs,Units 1,2 & 3 ML17312A9191996-04-30030 April 1996 Rev to MOR for Apr 1996 for PVNGS Unit 1 ML17312A6881996-03-31031 March 1996 Monthly Operating Repts for Mar 1996 for PVNGS.W/960411 Ltr ML17312B0001996-03-31031 March 1996 Revised Monthly Operating Rept for Mar 1996 for Palo Verde Nuclear Generating Station,Unit 2 ML17312A5371996-01-31031 January 1996 Monthly Operating Rept for Jan 1996 for PVNGS Units 1,2 & 3 ML17311B3121995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for PVNGS Units 1,2 & 3 ML17311B2681995-10-31031 October 1995 Monthly Operating Repts for Oct 1995 for Palo Verde Nuclear Generating Station.W/951108 Ltr ML17311B2221995-09-30030 September 1995 Monthly Operating Repts for Sept 1995 for Palo Verde Nuclear Generating Station ML17311B1821995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Palo Verde Nuclear Generating Station.W/950913 Ltr ML17311B0441995-06-30030 June 1995 Monthly Operating Repts for June 1995 for PVNGS Unit 1,2 & 3 ML17311B0451995-05-31031 May 1995 Revised Page 6 to Monthly Operating Rept for May 1995 for PVNGS Unit 2 ML17311A9471995-04-30030 April 1995 Revised Monthly Operating Rept for Apr 1995 for PVNGS ML17311A8721995-04-30030 April 1995 Monthly Operating Repts for Apr 1995 for PVNGS Units 1-3. W/950509 Ltr ML17311A8061995-03-31031 March 1995 Monthly Operating Repts for Mar 1995 for Palo Verde Nuclear Generating Station ML17311A7101995-02-28028 February 1995 Monthly Operating Repts for Feb 1995 for Palo Verde Nuclear Generating Station ML17311A6601995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Palo Verde Nuclear Generating Station.W/950210 Ltr ML17311A7121994-11-30030 November 1994 Revised Monthly Operating Rept for Nov 1994 for Palo Verde Nuclear Plant Unit 3 ML17311A2691994-08-31031 August 1994 Monthly Operating Repts for Aug 1994 for Palo Verde Nuclear Generating Station ML17310B2811994-04-30030 April 1994 Monthly Operating Repts for Apr 1993 for Palo Verde Nuclear Generating Station.W/940513 Ltr ML17310B2161994-03-31031 March 1994 Monthly Operating Repts for Mar 1994 for PVNGS Units 1,2 & 3 ML17310B1001994-02-28028 February 1994 Monthly Operating Repts for Feb 1994 for Palo Verde Nuclear Generating Station Units 1,2 & 3.W/940314 Ltr 1999-09-30
[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 05000528/LER-1999-002-01, :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. with1999-08-27027 August 1999
- 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
05000528/LER-1996-009, :on 961027,identified That TS Violation May Have Occurred Due to Missed Surveillance Test.Caused by Personnel Error.Setpoint for Limit Switches for Valve 1SIAUV647 Corrected to Achieve 1-inch Stroke Length1999-08-18018 August 1999
- on 961027,identified That TS Violation May Have Occurred Due to Missed Surveillance Test.Caused by Personnel Error.Setpoint for Limit Switches for Valve 1SIAUV647 Corrected to Achieve 1-inch Stroke Length
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 05000529/LER-1999-005, :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 Procedure1999-07-16016 July 1999
- 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
ML17300B2991999-07-0808 July 1999 SER Accepting Exemption from Updated Final Safety Analysis Report for Plant,Units 1,2 & 3 ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 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 05000529/LER-1999-004, :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 Labs1999-05-0707 May 1999
- 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 ML17313A9001999-04-26026 April 1999 SER Accepting Licensee Proposed Relief Requests 11 & 12 for Second 10-year Inservice Insp Interval for Palo Verde Nuclear Generating Station,Units 1,2 & 3 05000528/LER-1999-003, :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 Checked1999-04-14014 April 1999
- 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
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 05000530/LER-1998-003-02, :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 Svc1999-04-13013 April 1999
- 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 05000528/LER-1999-001-02, :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. with1999-04-0909 April 1999
- 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
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 ML17313A8441999-03-0808 March 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Replacement Requirements of Section III of ASME Code 05000529/LER-1999-001-01, :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.With1999-03-0101 March 1999
- 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
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 ML17313A7951999-02-0404 February 1999 Safety Evaluation Accepting Licensing Actions Associated with GL 92-08, Thermo-Lag 330-1 Fire Barriers ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 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 05000528/LER-1996-008, :on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised1999-01-15015 January 1999
- 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 ML17313A7251998-12-23023 December 1998 Safety Evaluation Supporting Amends 119 & 119 to Licenses NPF-41 & NPF-51,respectively ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6911998-11-25025 November 1998 Corrected Safety Evaluation Pp 13 & 50 to Plant Units 1,2 & 3,respectively.Change to Pp 13 Corrects Discussion in Paragraph L2.Change in Pp 50 Corrects Discussion Under ITS 3.5.2 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 05000528/LER-1998-008, :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 Requirements1998-10-24024 October 1998
- 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
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 ML20154N2751998-10-19019 October 1998 Safety Evaluation Supporting Amend 119 to License NPF-74 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 05000530/LER-1998-002-02, :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-wired1998-09-14014 September 1998
- 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 05000529/LER-1998-003, :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 Transmitters1998-09-0808 September 1998
- 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 1999-09-30
[Table view] |
Text
ACCELERATED DISTRIBUTION DEMONSTlTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
FACIL:STN-50-528 Palo Verde Nuclear Station, STN-50-529 Palo Verde Nuclear Station, STN-50-530 Palo Verde Nuclear Station, AUTH.NAME AUTHOR AFFILIATION ECKLUND,B.S.
Arizona Public Service Co.
RECXP.NAME RECIPIENT AFFILIATION NOTARIZED:
NO DOCKET Unit 1, Arizona Publi 05000528 Unit 2, Arizona Publi 05000529 Unit 3, Arizona Publi 05000530 (formerly Arizona Nuclear Power
SUBJECT:
Monthly operating rept pr 1993 for Palo Verde Nuclear Generating Station.
513 tr.
DISTRIBUTION CODE IE24D COPIES RECEIVED'LTR f ENCL i SIZE TITLE: Monthly Operating Report (per Tech Specs)
NOTES:STANDARDIZED PLANT Standardized plant.
Standardized plant.
D
/
05000528 05000529 A 05000530 D
RECIPIENT ID CODE/NAME PDIV-3 PD TRAN,L XNTERNAL: ACRS AEOD/DSP/TPAB NRR/DRXL/RPEB RGN4 EXTERNAL: EG&G BRYCE,J.H NSIC COPIES LTTR ENCL 1
1 1
1 10 10 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME HOLXAN, B AEOD/DOA
/BORS/OEAB REG F
01 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 D
D NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 22
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034
~
PHOENIX. ARIZONA85072-2034 417-00227-BSE/F HD May 13, 1994 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units1,2, and 3 Docket Nos. STN 50-628/529/630 Monthly Operating Reports forApril 1994 4'
-2 Enclosed are the Monthly Operating Reports for April 1994, prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the PVNGS Units 1, 2, and 3 Operating Licenses.
By copy of this letter, Arizona Public Service Company is also forwarding the Monthly Operating Reports to the Regional Administrator, NRC Region IV.
Ifyou have any questions, please contact me at (602) 340-4068.
Sincerely, BSE/FHD/gez Enclosures (all w/enclosures) cc:
L. J. Callan K. E. Perkins A. H. Gutterman NRC Senior Resident Inspector INPO Records Center UtilityData Institute g napa~
q4Q5 f8o552, 94045528 PDR AOOCK,05000
I P
I
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o p I
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.
54525 UNIT NAME ELHGR1 DATE Q5L15K COMPLETED BY
~~Gktl03$l IKQIMdm MONTH:April 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1076 17 1079 1077 18 1080 1079 19 1080 1079 20 1079 1082 21 1077 1083 22 1074 1082 23 1078 1082 24 1081 1083 25 1080 10 942 26 1080 1068 27 1081 12 1081 28 1082 13 1082 29 1081 14 1079 30 1078 15 1079 31 16 1078
REFUELING INFORMATION DOCKET NO.
~25 UNITNAME Mbl&&1 DATE 95L1QLK COMPLETED BY MMA!ill Scheduled date for next refueling shutdown.
The 5th refueling outage is tentatively scheduled for 04/02/95.
Scheduled date for restart following refueling.
06/21/95.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
No.
Scheduled date for submitting proposed licensing action and supporting Information.
N/A.
Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis
- methods, significant changes in fuel design, and new operating procedures.
N/A.
The number of fuel assemblies.
b) In the spent fuel storage pool.
'V.~
Intended change in spent fuel storage capacity. ~~
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
SLAG UNIT NAME MHGM DATE 95L1QEC COMPLETED BY MMGklQKl 04/01 0000 04/10 1203 04/10 1249 04/10 1810 04/11 0355 04/30 2400 Unit began the month in Mode 1, 86% RX power Commenced plant downpower due to a control rod slip (CEA 36). COLSS declared inoperable.
Stopped power decrease at 62%.
Commenced RX power increase to 86% from 62% at 3% per hour following restoration of CEA 36.
Stabilized RX power at 86%.
Ended the month in Mode 1, 86% RX power.
SHUTDOWNS AND POWER REDUCTIONS April 1994 DOCKET NO UNITNAME DATE 95LElR4 COMPLETED BY ~~g~
IEQIHHM No.
Outage Method of Duration Shutting Down Date Type" Hours Reason2 Reactor3 LER No.
System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-02 04/10/94 F
N/A A
N/A N/A N/A Reduction of RX power to 62%
due to a control rod slip.
1F Forced S-Scheduled 2Reason.
A-Equipment Failure(Explain) 8-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error H-Other (Explain) 3Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 9-Other-(Explain) 4Exhibit F - Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG0161)
Exhibit H-Same Source
NRC MONTHLYOPERATING REPORT DOCKET NO.
59-'j29 UNIT NAME DATE 95Li9lK COMPLETED BY ELRZMIUQd 1.
Unit Name:
Palo Verde Nuclear Generating Station, Unit 2 2.
Reporting Period:
April 1994 3.
Licensed Thermal Power(MWt):
3800 4.
Nameplate Rating (Gross MWe):
1403 5.
Design Electrical Rating (Net MWe):
1270 6.
Maximum Dependable Capacity (Gross MWe):
1303 7.
Maximum Dependable Capacity (Net MWe):
1221 8.
IfChanges Occur In Capacity Ratings (Item Numbers 3 Through 7)
Since Last Report, Give Reasons:
N/A 9.
Power Level to Which Restricted, IfAny (Net MWe):
None 10.
Reasons For Restrictions, IfAny:
N/A 12 13 14 15 16 17 18 19 20 21 22 23 Ha'i'irs')n",.Repi'itfii9::.P Re'a'ctcir, NitgBf iinit'::A'vaI!
Unit'::Ca'p'i'c'ftj!'Fact'a'r'l(Usiiig'.IN9Q,'Ne't)':,::;)h<)(,.3j,".:.');:;:::::::-:'=:,-:~.'",::,":;:
Unjt:Ca'paiity",:,Factor::,:(Usiiig',DER':,Ni:t Uriit::::.Force'd;:.0'utagh: Rati:;,'{t~)jg'::;,';:;::jjjQ.,":::-,:'i;:..;::,:::':.::::,~>jj<~ij,:-'.;".;
720 720.0 0.0 720.0 0.0 2,333,826 821,400 765,969 100 0%
100 0%
87.1%
83 8%
0.0%
2,880 1,120.6 0.0 1,075.7 0.0 3,280,459 1,142,300 1,044,173 37.4%
37 4%
29.7%
28 5%
2.7%
($4:gjXig.:V"..",.ggjwgiV,';:,;:.;:.@@
- ,',
- ;::>Cii'r'i'jiilitive'.:~:.':,.'.:j 66,744 45,669.1 0.0 44,755.6 0.0 163,114,704 56,805,270 53,164,207 67 1%
67 1%
65 2%
62 7o/o 6.0%
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
scheduled to begin 9/17/94 with a 40 day duration.
Mid'leoutage 25.
IfShutdown At End of Report Period, Estimated Date of Start-up:
N/A INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Forecast QZK 96lK 12K Achieved ML16lK
AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
54529 UNIT NAME E~iR2 DATE 95L19lK COMPLETED BY MMQklllQd IHRIBSBM MONTH: April 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1076 17 1073 1072 18 1075 1072 19 1074 1075 20 1072 1076 21 1069 6
1074 22 1071 1071 23 1079 1069 24 1081 1075 25 1080 10 1074 26 1080 1071 27 1080 12 1075 28 1078 13 1077 29 1077 14 1076 30 894 15 1075
'1 16 1072
t
REFUELING INFORMATION DOCKET NO.
$452R UNITNAME MHG.R2 DATE QGQQLR4 COMPLETED BY jLh'MGkllllKl IHRIBSBM Scheduled date for next refueling shutdown.
The 5th refueling outage is scheduled for 02/01/95.
Scheduled date for restart following refueling.
04/22/95.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
A change ~ be required to Technical Specification 3.9.6 to raise the overload cutoff limit to accommodate the new fuel assembly modification. Also, Technical Specification Section 6.9.1.10 willbe modified to add the new Inlet Flow Distribution methodology.
Scheduled date for submitting proposed licensing action and supporting information.
10/27/94.
Important Licensing considerations associated with refueling, e.gnew or different fuel design or supplier, unreviewed design or performance analysis
- methods, significant changes in fuel design, and new operating procedures.
The fuel assembly will consist of a denser fuel pellet, Erbium burnable absorber and guardian grid.
A primary temperature drop of 10' is currently planned.
The number of fuel assemblies.
a) Inrhe cere.~
b) In the spent fuel storage pool. ~~
Licensed spent fuel storage capacity." ~29 Intended change in spent fuel storage capacity. ~Op Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
QL529 UNIT NAME 22HGR2 DATE GOLEM COMPLETED BY EL'MQkllEKl IEKBRBH hgriL1994 04/01 0000 04/30 0600 04/30 1030 04/30 1335 04/30 1802 04/30 2400 Unit began the month in Mode 1, 86/o RX power.
Commenced RX power reduction for SG chemical hideout test.
Stabilized RX power at 51 /o.
Commenced increasing RX power to 85/o.
Stabilized RX power at 86 lo.
Ended the month in Mode 1, 86/o RX power.
SHUTDOWNS AND POWER REDUCTIONS April 1994 DOCKETNO UNITNAME DATE 95L19LK COMPLETED BY 9 l~~g Outage Method of Duration Shutting Down Date Type" Hours Reason2 Reactor3 LER No.
System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-03 04/30/94 N/A N/A N/A N/A RX power reduction for SG chemical hideout test.
1F Forced S-Scheduled 2Reason:
A-Equipment Failure(Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain) 3Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 9-Other-(Explain) 4Exhibit F - Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG0161)
Exhibit H-Same Source NRC MONTHLYOPERATING REPORT DOCKET NO.
tHH39 UNIT NAME MbEiR2 DATE QGQER4 COMPLETED BY 1.
Unit Name:
Palo Verde Nuclear Generating Station, Unit 3 2.
Reporting Period:
April 1994 3.
LicensedThermalPower(MWt):
3800 4.
Nameplate Rating (Gross MWe):
1403 5.
Design Electrical Rating (Net MWe):
1270 6.
MaximumDependable Capacity(Gross MWe):
1303 7.
Maximum Dependable Capacity (Net MWe):
1221 8.
IfChanges Occur In Capacity Ratings (Item Numbers 3 Through 7)
Since Last Report, Give Reasons:
N/A 9.
Power Level to Which Restricted, IfAny (Net MWe):
None 10.
Reasons For Restrictions, IfAny:
N/A 11.
HaurslnrrRiip~o'ittiijj,:Perio'd. 'r'~::I:
720 2,880
- ",.-.
- l,';:KCumUlatljj'.>%-',.':
55,320 12 13 14 H'aiirs,."Reicta'r,',w'as'::,::C'rltlcaI,::".,"'j';:;~~!'":.':>'::i'.::>PI'"."I R'ea'chr,:,'Res'e'ivi';8'h'utdc'iw'ii: H'ai'i'res~~!:.j!.:.-'!ll ~"li".:'.-'r'.",".!:.'::,'.:;'"N Haiirs.,'6'ii'n'erarta'res;:Oiilb'I'neil:;.',j:,:'1:,""I.".."ajN:: I,',:: INyp<g g::,',::;;i 0.0 0.0 0.0 1,848.6 0.0 1,848.6 40,864.5 0.0 40,272.7 15.
Uiiit'.:Referl'rd':;8fiMt 0.0 0.0 0.0 17 Gjo's's'gl'e'cd)i'a);::8'I%'erg'y';,QerIe'rate'0:'::,(lNWH)~,:".:;;.)j~~'
0 5,995,571 2,120,500 146,666,831 51,342,400 19 20 Uriitm8e'rvlc'e;:Fictai.',g/o) ~%"'i':4</'i:::::::::~'l::::::::
'"'-"'ig%~m":"':-"'i'1.
Uiijt'C'ijiicitjj,":,Farct'ar,.'(UsingIMDQ;,:;,Net)'::I',:,'::::::::::::>0;=
22.
Uiiit::;:C'a'pacitj;::,Facfa'r,':(tjiing:,:,
23 18.
Met EIe'n3rtneIEn'erjy:,':;:Geiierereedi(ININH),:,";:::;:,':,::ii~p 0
0.0%
0.0%
p.p p.p pp 1,976,048 64.2%
64.2%
56.2%
54 P%
p.p 48,274,269 72.8%
72.8%
71 5%
68.7%
6.6%
24 25.
Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
4th Refueling outage began March 19, 1994.
80 days duration.
IfShutdown At End of Report Period, Estimated Date of Start-up:
06/07/94 INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Forecast QZLQZ QZIGZ QBLCZ Achieved iGL226Z I-
I i
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.
59-'539 UNIT NAME MHGR2 DATE 95L10LK4 COMPLETED BY fLG~R!lHEl MONTH: April 1994 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 17 18 19 20 21 22 23 25 10 26 27 12 28 13 29 14 30 15 31 16
REFUELING INFORMATION DOCKET NO. ~}
UNIT NAME MbtGR2 DATE QGL1EK4 COMPLETED BY MM&lllQd IHRIaadM Scheduled date for next refueling shutdown.
03/19/94, 4th refueling.
Scheduled date for restart following refueling.
06/07/94.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
At present, four Tech. Spec. changes are in process.
One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30w/o. The other is to change the DNBR setpoint limitfrom 1.24 to 1.30. These are generic Tech. Spec. changes, and willbe implemented on a Unit by Unit basis, beginning with U3C5.
Also, there are two other Tech. Spec. changes that will allow U3C5 to operate at 100% power due to the steam generator issues.
Scheduled date forsubmitting proposed licensing action and supporting information.
The fuel enrichment change was submitted in October 1993 and the DNBR setpoint change was submitted in January 1994.
Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis
- methods, significant changes in fuel design, and new operating procedures.
U3C5 will incorporate a new higher maximum enrichment level of 4.30w/o U235 and will also utilize a new integral burnable absorber, Erbium.
The NRC granted a license amendment (No. 35) which allows the use of 80 fuel rods clad with advanced zirconium based alloys (other than Zircaloy4) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation.
Date of issuance was July 20, 1992.
The number of fuel assemblies.
b) In the spent fuel storage pool.
iV.~
Intended change in spent fuel storage capacity.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2005 (18 Month reloads and full core discharge capability).
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
59-'QQ UNIT NAME
~HG.M DATE Q5L1QLK4 COMPLETED BY MME!DEKE IRUShllU hariL1996 04/01 0000 04/02 0328 04/30 0545 04/30 2400 Unit began the month in Mode 6, refueling outage in progress and fuel-offload in progress.
Core off-load complete, exited Mode 6.
Commenced core re-load, entered Mode 6.
Unit ended the month in Mode 6, refueling outage in progress and fuel re-load continuing.
SHUTDOWNS AND POWER REDUCTIONS April 1994 DOCKET NO UNIT NAME DATE Q~/i&4 COMPLETED BY
~Bg~l fEIIRhKH Outage Method of Duration Shutting Down Date Type" Hours Reason2 Reactor3 LER No.
System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-01 03/19/94 S
720.0 N/A N/A N/A Continuation of4th refueling outage from previous month.
1F Forced S-Scheduled 2Reason:
A-Equipment Failure(Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error H-Other (Explain) 3Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 9-Other-(Explain) 4Exhibit F - Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG0161)
Exhibit H-Same Source