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| {{#Wiki_filter:. t | | {{#Wiki_filter:. t NAltRATIVE StANAltY OF OPERATING EXPERIENCE DOCKET NO. 50-263 LNIT hbnticello DATE 3-4-80 CCNPLETED BY A. L. Myrabo TELEPfiONE 612/295-5151 htymi Febnsary 2/1/80 Shutdown to complete primary containment isolation reset logic to modification for NUREG 0578, item 2.1.4 implementation. Outage 2/3/80 extended due to spurious IR\f scram on startup. |
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| NAltRATIVE StANAltY OF OPERATING EXPERIENCE DOCKET NO. 50-263 LNIT hbnticello DATE 3-4-80 CCNPLETED BY A. L. Myrabo TELEPfiONE 612/295-5151 | |
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| htymi Febnsary 2/1/80 Shutdown to complete primary containment isolation reset logic to modification for NUREG 0578, item 2.1.4 implementation. Outage 2/3/80 extended due to spurious IR\f scram on startup. | |
| 2/4/80 . | | 2/4/80 . |
| to Power operation during end-of-cycle coastdown. | | to Power operation during end-of-cycle coastdown. |
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| 2/16/80 Reduced power to 30% to perfom main condenser tube leak inspection. | | 2/16/80 Reduced power to 30% to perfom main condenser tube leak inspection. |
| 2/17/80 to Power operation at 60%. | | 2/17/80 to Power operation at 60%. |
| 2/21/80 | | 2/21/80 2/22/80 to Shutdown for 1980 refueling outage. |
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| 2/22/80 to Shutdown for 1980 refueling outage. | |
| 2/29/80 | | 2/29/80 |
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| MAR 0 7 1980 OPERATING DATA REPORT DOCKET NO. 50-263______ | | MAR 0 7 1980 OPERATING DATA REPORT DOCKET NO. 50-263______ |
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| : 7. Maximum Dependable Capacity (Net MWe): ____536 l__________________________l | | : 7. Maximum Dependable Capacity (Net MWe): ____536 l__________________________l |
| : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: __N/A__________________________________________,.__ | | : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: __N/A__________________________________________,.__ |
| __________________-______-_-__-_---------_-------__--------_---_------__
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| : 9. Power Level Ta Which Restricted, If Any (Net MWe): ___N/A______________.__.._ | | : 9. Power Level Ta Which Restricted, If Any (Net MWe): ___N/A______________.__.._ |
| : 10. Reasons For destrictions, If Any: __N/A________________..____________________ | | : 10. Reasons For destrictions, If Any: __N/A________________..____________________ |
| ________________________-_--___--_---_---_-_----_-----_---_--__--__-_---
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| ____________________________-_--__----__---_------__---__--------___----
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| This Month Yr.-to-Date Cumulative | | This Month Yr.-to-Date Cumulative |
| : 11. Hours In Reporting Period _____696 _____1440 ____ 75985 | | : 11. Hours In Reporting Period _____696 _____1440 ____ 75985 |
| : 12. Number Of Hours Reactor Was Critical ___479.6 ___1223.6 62754.5 | | : 12. Number Of Hours Reactor Was Critical ___479.6 ___1223.6 62754.5 |
| : 13. Reactor Reserve Shutdown Hours | | : 13. Reactor Reserve Shutdown Hours |
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| _____0.0 ______0.0 _____940.7 14 Hours Generator On-Line ___467.1 ___1211.1 __ 61181.2 | | _____0.0 ______0.0 _____940.7 14 Hours Generator On-Line ___467.1 ___1211.1 __ 61181.2 |
| : 15. Unit Reserve Shutdown Hours _____0.0 ______0.0 ____.__0.0 | | : 15. Unit Reserve Shutdown Hours _____0.0 ______0.0 ____.__0.0 |
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| : 22. Unit Capacity Factor (Using DER Net) __ 43.9% ___ 63.3% ____ 72.7% | | : 22. Unit Capacity Factor (Using DER Net) __ 43.9% ___ 63.3% ____ 72.7% |
| : 23. Unit Forced Outage Rate __ i.7% ___ O.7% 6.3% | | : 23. Unit Forced Outage Rate __ i.7% ___ O.7% 6.3% |
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| : 24. Shutdowns Scheduled Over Next 12 Months (Type, Date, and Duration of | | : 24. Shutdowns Scheduled Over Next 12 Months (Type, Date, and Duration of |
| __None_______________________________________________________ _______ | | __None_______________________________________________________ _______ |
| ______-______________--_--__--_----__---_---_---__---------------------_
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| : 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:__03-28-80__ | | : 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:__03-28-80__ |
| : 26. Units In Test Status (Prior to Commerc ia L Opera t ion)- N/A Forecast Achieved INITIAL CRITICALITY ..______. ________ | | : 26. Units In Test Status (Prior to Commerc ia L Opera t ion)- N/A Forecast Achieved INITIAL CRITICALITY ..______. ________ |
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| COMMERCIAL OPERATION .____..__ ________ | | COMMERCIAL OPERATION .____..__ ________ |
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| AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-263______ | | AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-263______ |
| UNIT Monticello__ | | UNIT Monticello__ |
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| DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWe-Net) (MWe-Net) i __________204____________ 17 __________333____________ | | DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWe-Net) (MWe-Net) i __________204____________ 17 __________333____________ |
| 2 -4____________ 18 | | 2 -4____________ 18 |
| __________
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| __________326_______.__.._ | | __________326_______.__.._ |
| 3 13____________ 19 | | 3 13____________ 19 |
| __________
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| __________326____________ | | __________326____________ |
| 4 __________349____________ 20 __________324____________ | | 4 __________349____________ 20 __________324____________ |
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| 13 __________402____________ 29 ______..___ -3________.___ | | 13 __________402____________ 29 ______..___ -3________.___ |
| 14 __________352____________ 30 _________________________ | | 14 __________352____________ 30 _________________________ |
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| 15 __________335____________ 31 _________________.._______ | | 15 __________335____________ 31 _________________.._______ |
| 16 __________236____________ | | 16 __________236____________ |
| INSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. | | INSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. |
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| a | | a UNIT SilUIDOWNS %ND POhER REDUCTIONS DOCKET NO. 50-263 , |
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| UNIT SilUIDOWNS %ND POhER REDUCTIONS DOCKET NO. 50-263 , | |
| UNIT N AME Monticello DATE 3-4-80 REPOR T MON Til February COMPLETED BY A. L Mvrnhn TELEPilONE 612/295- 151 | | UNIT N AME Monticello DATE 3-4-80 REPOR T MON Til February COMPLETED BY A. L Mvrnhn TELEPilONE 612/295- 151 |
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20141C2841997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Monticello Nuclear Generating Plant ML20137W2621997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Monticello Nuclear Generating Plant ML20136H1671997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Monticello Nuclear Generating Plant ML20134M7071997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Monticello Nuclear Generating Plant ML20133J1401996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Monticello Nuclear Generating Plant ML20132A8771996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Monticello Nuclear Generating Plant ML20134L2761996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Monticello Nuclear Generating Plant ML20128Q7831996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Monticello Nuclear Generating Plant ML20117M8161996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Monticello Nuclear Generating Plant ML20116M2991996-07-31031 July 1996 Monthly Operating Rept for July 1996 for Monticello Nuclear Generating Plant ML20115H5651996-06-30030 June 1996 Monthly Operating Rept for June 1996 for Monticello Nuclear Generating Plant ML20112J1921996-05-31031 May 1996 Monthly Operating Rept for May 1996 for Monticello Nuclear Generating Plant ML20112A3121996-04-30030 April 1996 Monthly Operating Rept for Apr 1996 for Monticello Nuclear Generating Plant ML20107E9831996-03-31031 March 1996 Monthly Operating Rept for Mar 1996 for Monticello Nuclear Generating Plant ML20106H0591996-02-29029 February 1996 Monthly Operating Rept for Feb 1996 for Monticello Nuclear Generating Plant ML20100G5031996-01-31031 January 1996 Monthly Operating Rept for Jan 1996 for Monticello Nuclear Generating Plant ML20096C8061995-12-31031 December 1995 Monthly Operating Rept for Dec 1995 for Monticello Nuclear Plant ML20095G0231995-11-30030 November 1995 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20094L1921995-10-31031 October 1995 Monthly Operating Rept for Oct 1995 for Monticello Nuclear Generating Plant ML20093E6241995-09-30030 September 1995 Monthly Operating Rept for Sept 1995 for Monticello Nuclear Generating Plant ML20092F4121995-08-31031 August 1995 Monthly Operating Rept for Aug 1995 for Monticello Nuclear Generating Plant ML20087H3011995-07-31031 July 1995 Monthly Operating Rept for Jul 1995 for Monticello Nuclear Generating Plant ML20086K1731995-06-30030 June 1995 Monthly Operating Rept for June 1995 for Monticello Nuclear Generating Station 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2061999-10-12012 October 1999 Safety Evaluation Supporting Amend 106 to License DPR-22 ML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With 05000263/LER-1999-007, :on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With1999-07-0909 July 1999
- on 990610,HPCI Test Return Valve Was Unable to Close Against Max Expected Differential Pressure.Caused by Failure to Accurately Predict Valve Performance.Procedure Revised.With
05000263/LER-1999-006-01, :on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With1999-07-0202 July 1999
- on 990602,during Quarterly Surveillance Hcpi Was Declared Inoperable.Caused by Drain Pot Alarm.Revised HPCI Surveillance Test Procedure.With
ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With 05000263/LER-1999-005, :on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With1999-06-0707 June 1999
- on 990508,personnel Inserted Manual Scram When Pressure Transient Closed Air Ejector Suction Isolation Valves & Tripped off-gas Sys.Caused by Recombiner Catalyst Migration.Catalyst Was Removed.With
ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With 05000263/LER-1999-004-01, :on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With1999-05-24024 May 1999
- on 990422,low Reactor Water Level Scram,Group 2 & 3 Isolations & Subsequent HPCI Became Inoperable.Caused by Feedwater Controller Power Supply Failure.Three Power Supplies Replaced & Connections Cleaned.With
05000263/LER-1999-003-01, :on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With1999-05-12012 May 1999
- on 990412,HPCI & Division 1 ECCS Equipment Were Declared Inoperable Due to Svc Water Pump Failure.Pump Shaft Was Mechanically Freed,Check Valve Was Repaired & Pump Was Successfully Tested.With
05000263/LER-1999-002-01, :on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With1999-05-11011 May 1999
- on 990329,event Sequence That Results in Available ECCS Being Reduced to Less than That Assumed in Current Safety Analysis.Caused by Failure of Edg.Plant Operating Procedures Revised.With
ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20205C1651999-03-19019 March 1999 Safety Evaluation Supporting Amend 105 to License DPR-22 ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 05000263/LER-1999-001-02, :on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With1999-03-17017 March 1999
- on 990215,HPCI High Steam Flow Isolation During Quarterly Surveillance Test Was Noted.Caused by Inadequate Surveillance Procedure.Revised Surveillance Procedure.With
ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198M8221998-12-24024 December 1998 Safety Evaluation Supporting Amend 104 to License DPR-22 ML20198M6901998-12-23023 December 1998 Safety Evaluation Supporting Amend 103 to License DPR-22 ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv 05000263/LER-1998-005-01, :on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve1998-10-21021 October 1998
- on 980921,HPCI Was Removed from Service to Repair Steam Leak in Drain Trap by Pass.Caused by Localized Erosion of Valve Body.Valve Was Declared Inoperable & Was Replaced with Manual Valve
05000263/LER-1998-004-02, :on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked1998-10-0909 October 1998
- on 980909,manual Scram Was Inserted Following Pressure Transient Closed Air Ejector Suction Isolation Valves & Trips Offgas Recombiners,Occurred.Caused by Seat Leakage.Leaking Valve Seat Was Reworked
ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20151T0981998-08-28028 August 1998 Safety Evaluation Supporting Amend 101 to License DPR-22 ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant 05000263/LER-1998-003-01, :on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced1998-05-14014 May 1998
- on 980417,transgranular Stress Corrosion Cracking Was Identified in Control Rod Drive Lines.Caused by chloride-induced Transgranular stress-corrosion Cracking. Affected Sections of Two Lines Replaced
05000263/LER-1998-002-02, :on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed1998-05-14014 May 1998
- on 980415,main Steam Isolation Valve Position Setpoint Outside Allowed Range,Was Found.Caused by Previous Testing Technique & Use of Particular Switch Model.Eight New Position Switches W/Less Deadband Installed
ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant 05000263/LER-1998-001-02, :on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment1998-04-22022 April 1998
- on 980323,discovered Containment Isolation Valve Leakage Exceeded TS Limit.Caused by Foreign Matl Found on Valve Seat.Repaired Subject Valves & Developed Process to Ensure Cleanliness of Testing Equipment
ML20217E9611998-04-20020 April 1998 Safety Evaluation Supporting Amend 100 to License DPR-22 ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant 1999-09-30
[Table view] |
Text
. t NAltRATIVE StANAltY OF OPERATING EXPERIENCE DOCKET NO. 50-263 LNIT hbnticello DATE 3-4-80 CCNPLETED BY A. L. Myrabo TELEPfiONE 612/295-5151 htymi Febnsary 2/1/80 Shutdown to complete primary containment isolation reset logic to modification for NUREG 0578, item 2.1.4 implementation. Outage 2/3/80 extended due to spurious IR\f scram on startup.
2/4/80 .
to Power operation during end-of-cycle coastdown.
2/13/80 2/14/80 Reduced power to 60% after one feedwater pump removed from service due to bearing failure.
2/16/80 Reduced power to 30% to perfom main condenser tube leak inspection.
2/17/80 to Power operation at 60%.
2/21/80 2/22/80 to Shutdown for 1980 refueling outage.
2/29/80
- ~
MAR 0 7 1980 OPERATING DATA REPORT DOCKET NO. 50-263______
DATE 3- 4-80_..__
COMPLETED BY A. L. Myrabo TELEPHONE 612/295-5151 CPERATING STATUS ____________________________
INotes i
- 1. J1it Name ________________________Monticelto l l
- 2. Peporting period: ___________________ FEBRUARY l (
- 3. Licensed Thermal Power (MWt) _______..____1670 l l 4 Nameplate Rating (Gross MWe): ______.______569 l [
- 5. Design Electrical Rating (Net MWe): _____545.4 I i
- 6. Maximum Dependable Capacity (Gross MWe) __564 l l
- 7. Maximum Dependable Capacity (Net MWe): ____536 l__________________________l
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: __N/A__________________________________________,.__
- 9. Power Level Ta Which Restricted, If Any (Net MWe): ___N/A______________.__.._
- 10. Reasons For destrictions, If Any: __N/A________________..____________________
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period _____696 _____1440 ____ 75985
- 12. Number Of Hours Reactor Was Critical ___479.6 ___1223.6 62754.5
- 13. Reactor Reserve Shutdown Hours
_____0.0 ______0.0 _____940.7 14 Hours Generator On-Line ___467.1 ___1211.1 __ 61181.2
- 15. Unit Reserve Shutdown Hours _____0.0 ______0.0 ____.__0.0
- 16. Gross Thermal Energy Generated (MWH) _ 530513 _ 1553878 _100496740
- 17. Gross Electrical Energy Generated (MWH) __175800 __ 521150 __31499210
- 18. Net Electrical Energy Genera ~ted (MWH) __i66768 __ 497094 __30129290
- 19. Unit Service Factor __ 67.1 % ___ 84.1% ___. 80.5%
- 20. Unit Availability Factor __ 67.1% ___ 84.1%
- 21. Unit Capacity Factor (Using MDC Net)
____ 80.5%
__ 44.7% ___ 64.4% ____ 74.0%
- 22. Unit Capacity Factor (Using DER Net) __ 43.9% ___ 63.3% ____ 72.7%
- 23. Unit Forced Outage Rate __ i.7% ___ O.7% 6.3%
- 24. Shutdowns Scheduled Over Next 12 Months (Type, Date, and Duration of
__None_______________________________________________________ _______
- 25. If Shut Down At End Of Report Period, Estimated Date Of Startup:__03-28-80__
- 26. Units In Test Status (Prior to Commerc ia L Opera t ion)- N/A Forecast Achieved INITIAL CRITICALITY ..______. ________
INITIAL ELECTRICITY ________ ________
COMMERCIAL OPERATION .____..__ ________
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-263______
UNIT Monticello__
DATE 3- 4-80..___
COMPLETED BY A. L. Myrabo TELEPHONE 612/295-5151 MONTH ______ FEBRUARY _______
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWe-Net) (MWe-Net) i __________204____________ 17 __________333____________
2 -4____________ 18
__________326_______.__.._
3 13____________ 19
__________326____________
4 __________349____________ 20 __________324____________
5 __________434____________ 21 __________322____________
6 __________411____________ 22 __________167____.._______
7 __________409____________ 23 __________ -4____________
8 __________410____________ 24 __________ -4____________
9 __________410____________ 25 __________ -4_____..______
10 __________408____________ 26 __________ -3_______..____
11 __________405____________ 27 __________ -3_.____ _____
12 __________405____________ 28 __________ -3____________
13 __________402____________ 29 ______..___ -3________.___
14 __________352____________ 30 _________________________
15 __________335____________ 31 _________________.._______
16 __________236____________
INSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
a UNIT SilUIDOWNS %ND POhER REDUCTIONS DOCKET NO. 50-263 ,
UNIT N AME Monticello DATE 3-4-80 REPOR T MON Til February COMPLETED BY A. L Mvrnhn TELEPilONE 612/295- 151
\" Date
-, .5 2 5?
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thesace 8 4., % Cause & Correstise i 4 Esem s? [> Asimn to H
$5 5 5ig Report = AL ,5 '-' Preseni Recurrense
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- i 1 2-1-80 S 45.3 D 1 N/A SD INSilU-X Primary Containment Isolation Reset Logic Modification. NUREG 0578, Itmi 2.1.4 implementation.
2 2-3-80 F 8.2 A 3 N/A IA INSTRU-E Full IRM scram occurred from a spur-ious upscale spike on IRM channel 14.
Earlier trip on "B" RPS channel was not fully reset.
3 2-16-80 S 0 B 4 N/A FC FilHOI Reduced power to 30% to perform conder -
e ser tube leak test.
4 2-22-80 S 175.4 C 1 N/A ZZ ZZZZZZ End of cycle 7 refueling ontage.
i : 3 4 F- Forced Reason . Method:
S. Scheduled Edubit G Instructions A. Equipment Failure (Esplain) l-Manual for Preparation of Data B-Maintenance or Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automaine Strain- Esent Report (LER) Fi!c iNUREG-D-Regulatory Restriction 4-Other (Explain i 0161) l EOperator Training A Li, ens: Eumination F-Administrati.e 5 G Overational Ereor (Esplam E dubit I - Same Source (9/77) 11 Other ( E splau;)