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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
P R.I&R.I "EY'CCEI.ERATED RIDS PROCI'.SSliG REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
LEVINE,J.M.
RECIP.NAME ACCESSION NBR:9505180256 DOC.DATE: RPf9'4/5&
NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION P
Arizona Public Service Co.
(formerly Arizona Nuclear Power Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIPIENT AFFILIATION
SUBJECT:
Mo hl operating repts for Apr 1995 for PVNGS Units 1-3.
W 95050 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs NOTES:STANDARDIZED PLANT Standardized plant.
Standardized plant.
05000528 05000529 I
05000530 RECIPIENT
'D CODE/NAME PD4-2 PD TRAN,L INTERNAL: AC E CENTE 1
'CB EXTERNAL LITCO BRYCE iJ H
NRC PDR COPIES.
LTTR ENCL 1
1 1
1 10 10 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME HOLIAN, B THOMAS,C AEOD/SPD/RRAB NRR/DISP/PIPB RGN4 NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
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u YOTE TO ALL"RIDS" RECIPIEY'TS:
PLEASE ICELP US TO REDUCE iVASTE!COYTACTTHE DOCL:ifEYTCONTROL DESK, ROOXf PI-37 IEXT. 5%-~083 ) TO F Ll Nfl.'4 KTE YOI.'R iAifL FROif DISTRIBUTION, LIS'I S FOR DOC!.'b,fEi'I'S YOI.'Oi "I'EI'.I)!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 22
0
$ Ai k
l
JAMES M. LEVINE VICE PRESIDENT NUCLEARPRODUCTION Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034
~
PHOENIX, ARIZONA85072-2034 182-06068-JML/J LT/JDF May 9, 1995 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)
Units 1,2, and 3 Docket Nos. STN 50-528/529/530 Monthly Operating Reports for April 1995 Enclosed are the Monthly Operating Reports for April 1995, 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 Judy Fulton at (602) 393-5277.
Sincerely, JML/JDF/gez
Enclosures:
March 1995 Monthly Operating Reports (all w/enclosures) cc:
L. J. Callan K. E. Perkins NRC Senior Resident Inspector INPO Records Center UtilityData Institute 9505i80256 950430 PDR ADOCK '05000528 R
PDR
lt l'~
7
'Jga g
NRC Monthly Operating Report Distribution List bcc:
J. A. Bailey R. J. Bouquot B. J. Davis W.
Ferguson B. A. Grabo J. W. Hazelbaker W. E. Ide J. M. Levine V. L. Mehrhof W. W. Montefour W. L. Stewart (7605) (all w/enclosures)
(7996)
(7646)
(9816)
(7636)
(7693)
(7294)
(7602)
(7712)
(7466)
(9082)
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P
I AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.
59-'F25 UNIT NAME DATE 95LQ5LK COMPLETED BY
)LREUHQQ MONTH:April 1995 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 17 18 19 20 21 0
22
'3 8
24 25 10 26 11 12 27 28 13 29 30 15 31 16
II,
)
REFUELING INFORMATION DOCKET NO.
~35 UNIT NAME
~Ugly~
DATE 9555LK COMPLETED BY ~~an Scheduled date for next refueling shutdown.
The 5th refueling outage began on 04/01/95.
Scheduled date for restart following refueling.
~
06/1 0/95.
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.
12/28/94 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.
The fuel assembly will utilize Erbium as a burnable absorber (as was done for Units 2 and 3).
The number of fuel assemblies.
1 Licensed spent fuel storage capacity.
Intended change in spent fuel storage capacity. ~os 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).
I I
l pl
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET'NO.59-525 n
UNIT NAME MHG&i DATE Q5LQ5LK COMPLETED BY ~gite 04/01 0000 04/01
'006 04/01 0635 04/03 1008 04/06 2030 04/12 0034 04/27 0547 04/30 2359 Unit began the month in Mode 1 reducing Rx power to 20% for the 6th refueling outage.
Entered Mode 3. Tripped the Rx for normal shutdown, officiallybeginning 6th refueling outage.
Entered Mode 4.
Entered Mode 5.
Entered Mode 6.
Rx is defueled.
Exited Mode 6.
Entered Mode 6. Core. reload.
Unit ended the month in refueling outage Mode 6.
SHUTDOWNS AND POWER REDUCTIONS April 1995 DOCKET NO UNIT NAME DATE COMPLETED BY TELEPHONE LVVI95-1
~0/0~/
~JuHan No.
Date Outage Method of Duration Shutting Down Type" Hours.
Reason2 Reactor3 LER No.
System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of April, 1995.
1F-Forced S-Scheduled Reason:
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 (NUREG 0161)
Exhibit H-Same Source
)
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.
5%529 UNIT NAME 22HGR2 DATE QGLKLK COMPLETED BY JJ2JKHQQ EILRMZll MONTH: April 1995 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 823 17 1250 883 18 1249 I 3 1222 19 1249 1248 20 1250 1246 21 1251 1246 22 1251 1246 23 1250 1247 24 1251 1248 25 1252 10 1248 26 1250
'80 27 1248 12 460 28 1248 13 1159 29 1246 14 1214 30 1242 15 1248 31 16 1251
REFUELING INFORMATION DOCKET NO.
~29 UNIT NAME DATE 955555 COMPLETED BY ~gJfzl Scheduled date for next refueling shutdown.
The 6th refueling outage is scheduled for 03/16/96.
Scheduled date for restart following refueling.
05/1 0/96.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
a.
Technical Specification change to Note 5 of Table 4.3-1 for the proposed installation of a cycle independent shape annealing matrix.
Scheduled date for submitting proposed licensing action and supporting information.
12/08/95.
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.
Stretch Power to 102%.
The number of fuel assemblies.
e) tn the core.~
b) In the spent fuel storage pool.
Licensed spent fuel storage capacity. ~29 Intended change in spent fuel storage capacity. ~g 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).
J n
'f,ll g h
'L
)
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
RL529 UNIT NAME MHGR2 DATE 95LQ5LK COMPLETED BY ~UltQQ 04/01 0000 04/01 0345 04/02 1649 04/03 0100 04/03 0235 04/03 1500 04/11 1435 04/11 1750 04/12 2101 04/13 0300 04/13 0435 04/13 0620 04/13 0840 04/1 3 1042 04/15 0015 04/15 0115 Unit began the month in power ascension to 70%.
Rx power stabilized at 69% JSCALOR for testing.
Commenced Rx power increase from 69% to 100% after completion of the 70% power plateau physics testing.
Stabilized Rx power at 90% for surveillance testing.
Commenced Rx power ascension to 100% after completion of surveillance testing.
Stopped power ascension, Rx stabilized at 100% power.
Indication of CW leak from AB loop to 2C hotwell. Commenced Rx power decrease to 40% to isolate CWAB loop.
Rx power stabilized at 40% for CW leak on AB loop.
Commenced Rx power increase to 100%.
Stopped Rx power increase at 96% due to SG¹1 and SG¹2 sulfates.
Exited Action Level 1 for sulfates on SG¹1 and SG¹2.
RX power increase stopped at 95% for FWP suction pressure condensate discharge pressure limitdue to condensate pump out of service.
Commenced RX power increase to 100%.
Stopped Rx power increase at 97% due to Main feed pump suction pressure limitations.
Commenced Rx power increase to 100%.
Rx power stabilized at 100%.
Maintaining MFWP suction pressure,>300 psig.
CD pump remains out of service.
04/15 0945 04/15 1115 04/20 0924 04/22 0216 04/22 0330 04/30 2359 Rx power decreased to 99% for Hi Rate B/Ds.
Rx power increased to 100%.
Placed cond. demin. vessel C in service.,
Rx power decrease to 99% for Hi Rate B/Ds.
Rx power increased to 100%.
Unit ended the month in Mode 1 at 100% power.
SHUTDOWNS AND POWER REDUCTIONS April 1995 DOCKET NO UNITNAME
@VVI~
DATE
- QGMGLK COMPLETED BY ~Dye~
No.
Date Type" Outage Duration Hours Method of Shutting Down Reason2 Reactor3 LER No.
'- System Component Code4 Code5 Cause and Corrective Action to Prevent Occurrence 95-02 04/11/95 82.7 N/A N/A N/A Rx power reduced to 40% due to CW leak and condensate pump failure.
"F-Forced S-Scheduled Reason:
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 (NUREG 0161)
Exhibit H-Same Source J
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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.
UNIT NAME 22b!GR2 DATE QZQRK COMPLETED BY sLQ~IHQQ MONTH: April 1995 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1255 17 1259 1255 18 1258 l254 19 1257 1256 20 1257 1256 21 1258 1255 22 1254 1256 23 1256 8
1253 24 1256 1256 25 1258 10 1259 26 1256 1258 27 1254 12 1257 28 1255 13 1256 29 1251 14 1256 30 1248 15 1255 31 16 1257
14
REFUELING INFORMATION DOCKET NO.
%=539 UNIT NAME EEK~
DATE 95L95LK COMPLETED BY JJ2JhlfQQ Scheduled date for next refueling shutdown.
The 5th refueling outage is scheduled to begin 10/14/95.
Scheduled date for restart following refueling.
12/23/95.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment7 Technical Specification change to Note 5 of Table 4.3-1 for the proposed installation of a'cycle independent shape annealing matrix. (submitted 12/7/94 to NRC).
Scheduled date for submitting proposed licensing action and supporting information.
Submittal is planned for June 1995 to revise the list of analytical methods in Technical Specification 6.9.1.10.
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.
None.
The number of fuel assemblies.
b) In the spent fuel storage pool.
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).,
I
~ '
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE lHL5Z EK~K2 9292K dJ)~Iten 04/01 0000 04/08 0253 04/08 2213 04/16 0026 Unit began the month in Mode 1 at 100% power.
Rx power decreased to 99% for Hi Rate B/ds.
Rx power increased to 100%.
Rx power decreased to 99% for Hi Rate B/ds.
04/16 0237 Rx powerincreased to100%.
04/22 1009 04/22 1236 04/23 0050 04/23 0202 04/26 2149 04/26 2230 04/30 0139 04/30 0331 04/30 2359 Rx power decreased to 99% for ADVtesting.
Rx power increased to 100%.
Rx power decreased to 99% for Hi Rate B/ds.
Rx power increased to 100%.
Rx power decreased to 97% for control valve testing.
Rx power'increased to 100%.
Rx power decreased to 99% for Hi Rate B/ds.
Rx power increased to 100%.
Unit ended the month in Mode 1 at 100% power.
r
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SHUTDOWNS AND POWER REDUCTIONS April 1995 DOCKET NO
~39 UNITNAME
/VVI~~
DATE
~05 ~5/
COMPLETED BY
~Ji~i~o Date Type" Outage Method of Duration Shutting Down Hours Reason2 Reactor3 LER No.
System Code4 Component Cause and Corrective Action Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of April, 1995 "F-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 (NUREG 0161)
Exhibit H-Same Source 0
1 I
0 43-h t
1