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| issue date = 05/08/1979 | | issue date = 05/08/1979 | ||
| title = Monthly Operating Rept for Apr 1979 | | title = Monthly Operating Rept for Apr 1979 | ||
| author name = | | author name = Depew L | ||
| author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | ||
| addressee name = | | addressee name = | ||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:OPERATING DATA REPORT DOCKET NO.50 244 DATE~ay 8, 1979 COMPLETED BY LEWIS DEP~OPERATING STATUS 1 1.Unit Name: GINNA STATION U 2.Reporting Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross MWe): 5.Design Electrical Rating (Net MWe): 6.Maximum Dependable Capacity (Gross MWe): 7.Maximum Dependable Capacity (Net MWe): | {{#Wiki_filter:OPERATING DATA REPORT DOCKET NO. 50 244 DATE ~ay 8, 1979 COMPLETED BY LEWIS DEP TELEPHONE 1-716-546-27pp | ||
8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: 9.Power Level to Which Restricted, If Any (Net MWe): 10.Reasons For Restrictions, If Any: This Month Yr.-to-Date Cumulative 11.Hours In Reporting Period 12.Number of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Gcncrator On-Line 15.Unit Reserve Shutdown Hours 16.Gross Thermal Energy Generated (MWH)17.Gross Electrical Energy Generated (MWH)18.Net Electrical Energy Generated (MWH)19.Unit Service Factor 20.Unit Availability Factor | ~ OPERATING STATUS Ext. 291-205, at Ginna 1 | ||
~ | : 1. Unit Name: GINNA STATION U Low Power Physics | ||
E f~ri 4 DOCKET NO.Nl Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS COMPLETED BY LEWIS DEPEW REPORT hlONTH TELEPHONE | : 2. Reporting Period: Testing after refueling- | ||
Annual overhaul of"A" Condensate Pump still in progress,"B" Conden-sate'Pump Discharge. | : 3. Licensed Thermal Power (MWt): were completed and Unit | ||
Valve position limited'condensate pressure and feedwater flow.790411 5.5 A EB RELAYX Hain transformer cooling fan relay failure., F: Forced S: Scheduled | : 4. Nameplate Rating (Gross MWe): placed on line 4-3-79 for | ||
: 5. Design Electrical Rating (Net MWe): power physics testing and | |||
: 6. Maximum Dependable Capacity (Gross MWe): | |||
490 continued operation. | |||
: 7. Maximum Dependable Capacity (Net MWe): 470 | |||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: | |||
: 9. Power Level to Which Restricted, If Any (Net MWe): | |||
: 10. Reasons For Restrictions, If Any: | |||
This Month Yr.-to-Date Cumulative 719 2,879 83,033.45 | |||
: 11. Hours In Reporting Period | |||
: 12. Number of Hours Reactor Was Critical 696.09 1,682.17 62,884.59 22.91 22.91 1 569.42 * | |||
: 13. Reactor Reserve Shutdown Hours 656.5 1 617.25 61 195.88 | |||
: 14. Hours Gcncrator On-Line 8.5 * | |||
: 15. Unit Reserve Shutdown Hours | |||
: 16. Gross Thermal Energy Generated (MWH) 856,560 2 263 416 81 193 330 287,845 760 836 26 334 076 | |||
: 17. Gross Electrical Energy Generated (MWH) 272,664 722 230 24 923 268 | |||
: 18. Net Electrical Energy Generated (MWH) 91.3% 56.17% 74.06% | |||
: 19. Unit Service Factor 91.3% 56.17% 74.07% | |||
: 20. Unit Availability Factor Unit Capacity Factor (Using MDC Net) 80.69% 53.37% 66.765% | |||
21. | |||
80.69% 53.37% 66.765% | |||
: 22. Unit Capacity Factor (Using,DER Nct) 0% 0/ 10% | |||
: 23. Unit Forced Outage Rate | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): | |||
None | |||
: 25. If Shut Down At End Of Rcport.Period, Estimated Date of Startup: | |||
: 26. Units In Test Status (Prior to Commercial Operation): ~ Forecast Achieved INITIALCRITICALITY 7 INITIALELECTRICITY COMMERCIAL OPERATION | |||
* Cumulative Data Commencing- January 1, 1975 49 dd (RLVa I/76) 7 V905 aaO Z<7 | |||
0 l() 2 )+ L P>> | |||
AVERAGE DAILY UNIT POWER UNIT DOCKET NO.. 50 244 UNIT N1 @irma Statio DATE Ma 8 1979 COMPLETED BY LEWIS DEPEW TELEPHONE 1-716-546-2700 Ext. 291-205, at Gonna hIONTH P DAY AVERAGE DAILYPOWER LEVEL DAY, AVERAGE DAILY POWER LEVEL (hIWe-Net) (M We-Net) 451 17 18 450 19 450 94 449 20 242 450 21 339 451 22 352 450 23 430 450 24 445 25 450 450 450 10 26 442 452 21 450 452 12 28 13 450 29 451 450 452 14 30 450 15 31 451 16 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.. | |||
Compute to the nearest whole megawatt. | |||
40 87 (RCV, 1/78) | |||
E f ~ | |||
ri | |||
4 DOCKET NO. | |||
Nl Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS COMPLETED BY LEWIS DEPEW REPORT hlONTH TELEPHONE 0 Ext. 291-205, at Ginna CV ec 0 s- c 0 c u Licensee Ew- O u7 c Cause 8 Corrective 0 I 0 0 e No. Date o Event 0 Q u Action to o IA 0 | |||
I- o n~ X e tY ou7 c Report 5 u7 0 Prevent Recurrence (J | |||
n0 790210 S 62.5 Low power, physics testing was completed after refueling, unit placed on the line on 4-3-'79 for continued physics testing and power operation. | |||
790409 =512 A-B HH, VALVEX Annual overhaul of "A" Condensate Pump still in progress, "B" Conden-sate 'Pump Discharge. Valve position limited 'condensate pressure and feedwater flow. | |||
790411 5.5 A EB RELAYX Hain transformer cooling fan relay failure., | |||
4 F: Forced Reason: hlethod: Fxhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-hlanual for Preparation of Data B-hlaintenancc or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161) | |||
E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 49.89 tRKV 8/78) H-Other (Explain) Exhibit 1 - Same Source | |||
4 NARRATIVE | 4 NARRATIVE | ||
==SUMMARY== | ==SUMMARY== | ||
OF OPERATING EXPERIENCE DOCKET NO.0-2 UNIT Ginna Station Unit b'1 DATE COMPLETED BY LEWIS DEP | OF OPERATING EXPERIENCE DOCKET NO. 0-2 UNIT Ginna Station Unit b'1 DATE COMPLETED BY LEWIS DEP TELEPHONE 1-716-546-2700 Ext. 291-205, at Ginna MONTH A ril 1979 Low power physics testing were completed and unit was placed on the line on April 3. Turbine tests and physics testing were completed as power was escalated. At 98% power, the condensate bypass valve opened, power was reduced to 92%. The low condensate pressure was due to the "A" condensate pump still undergoing annual overhaul and the discharge valve of the "B" condensate pump was not in the full open position due to a faulty position indicator. On,Apiil 11, a relay on the main transformer fan coolers failed, load reduction was started and terminated when the fan coolers were reinstalled. | ||
At 98%power, the condensate bypass valve opened, power was reduced to 92%.The low condensate pressure was due to the"A" condensate pump still undergoing annual overhaul and the discharge valve of the"B" condensate pump was not in the full open position due to a faulty position indicator. | Operation at 92% continued due to condensate pump maintenance. | ||
On,Apiil 11, a relay on the main transformer fan coolers failed, load reduction was started and terminated when the fan coolers were reinstalled. | 49 I'23 0/78) | ||
Operation at 92%continued due to condensate pump maintenance. | |||
49 I'23 0/78) | '4 s | ||
'4 s 0 GINNA STATION MAINTENANCE REPORT FOR APRIL, 1979 During April, normal inspection and minor maintenance was performed. | |||
Major safety related maintenance included: 1.Replacement of a faulty bistable on Overpressure Protection Channel 452.2.Replacement of a bad batch board on Boric Acid Flow Channel 110.3.Replacement of a damaged valve diaphragm on the containment radiogas/particulate monitor pump return to containment. | 0 GINNA STATION MAINTENANCE REPORT FOR APRIL, 1979 During April, normal inspection and minor maintenance was performed. | ||
4.Repair to the flow control valve FCV llOA for the normal flow path from the Boric Acid Tanks to the Reactor Coolant System.5.Replacement of a leaking 3 1/2" long piece of pipe adjacent to FCV llOA.In addition, the check valve next to this piece of pipe was also replaced as a preventive measure. | Major safety related maintenance included: | ||
4~r}} | : 1. Replacement of a faulty bistable on Overpressure Protection Channel 452. | ||
: 2. Replacement of a bad batch board on Boric Acid Flow Channel 110. | |||
: 3. Replacement of a damaged valve diaphragm on the containment radiogas/particulate monitor pump return to containment. | |||
: 4. Repair to the flow control valve FCV llOA for the normal flow path from the Boric Acid Tanks to the Reactor Coolant System. | |||
: 5. Replacement of a leaking 3 1/2" long piece of pipe adjacent to FCV llOA. In addition, the check valve next to this piece of pipe was also replaced as a preventive measure. | |||
4 | |||
~ r}} |
Latest revision as of 12:52, 4 February 2020
ML17244A521 | |
Person / Time | |
---|---|
Site: | Ginna |
Issue date: | 05/08/1979 |
From: | Depew L ROCHESTER GAS & ELECTRIC CORP. |
To: | |
Shared Package | |
ML17244A520 | List: |
References | |
MOR-790430, NUDOCS 7905220227 | |
Download: ML17244A521 (10) | |
Text
OPERATING DATA REPORT DOCKET NO. 50 244 DATE ~ay 8, 1979 COMPLETED BY LEWIS DEP TELEPHONE 1-716-546-27pp
~ OPERATING STATUS Ext. 291-205, at Ginna 1
- 1. Unit Name: GINNA STATION U Low Power Physics
- 2. Reporting Period: Testing after refueling-
- 3. Licensed Thermal Power (MWt): were completed and Unit
- 4. Nameplate Rating (Gross MWe): placed on line 4-3-79 for
- 5. Design Electrical Rating (Net MWe): power physics testing and
- 6. Maximum Dependable Capacity (Gross MWe):
490 continued operation.
- 7. Maximum Dependable Capacity (Net MWe): 470
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 719 2,879 83,033.45
- 11. Hours In Reporting Period
- 12. Number of Hours Reactor Was Critical 696.09 1,682.17 62,884.59 22.91 22.91 1 569.42 *
- 13. Reactor Reserve Shutdown Hours 656.5 1 617.25 61 195.88
- 14. Hours Gcncrator On-Line 8.5 *
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 856,560 2 263 416 81 193 330 287,845 760 836 26 334 076
- 17. Gross Electrical Energy Generated (MWH) 272,664 722 230 24 923 268
- 18. Net Electrical Energy Generated (MWH) 91.3% 56.17% 74.06%
- 19. Unit Service Factor 91.3% 56.17% 74.07%
- 20. Unit Availability Factor Unit Capacity Factor (Using MDC Net) 80.69% 53.37% 66.765%
21.
80.69% 53.37% 66.765%
- 22. Unit Capacity Factor (Using,DER Nct) 0% 0/ 10%
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
None
- 25. If Shut Down At End Of Rcport.Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): ~ Forecast Achieved INITIALCRITICALITY 7 INITIALELECTRICITY COMMERCIAL OPERATION
- Cumulative Data Commencing- January 1, 1975 49 dd (RLVa I/76) 7 V905 aaO Z<7
0 l() 2 )+ L P>>
AVERAGE DAILY UNIT POWER UNIT DOCKET NO.. 50 244 UNIT N1 @irma Statio DATE Ma 8 1979 COMPLETED BY LEWIS DEPEW TELEPHONE 1-716-546-2700 Ext. 291-205, at Gonna hIONTH P DAY AVERAGE DAILYPOWER LEVEL DAY, AVERAGE DAILY POWER LEVEL (hIWe-Net) (M We-Net) 451 17 18 450 19 450 94 449 20 242 450 21 339 451 22 352 450 23 430 450 24 445 25 450 450 450 10 26 442 452 21 450 452 12 28 13 450 29 451 450 452 14 30 450 15 31 451 16 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month..
Compute to the nearest whole megawatt.
40 87 (RCV, 1/78)
E f ~
ri
4 DOCKET NO.
Nl Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS COMPLETED BY LEWIS DEPEW REPORT hlONTH TELEPHONE 0 Ext. 291-205, at Ginna CV ec 0 s- c 0 c u Licensee Ew- O u7 c Cause 8 Corrective 0 I 0 0 e No. Date o Event 0 Q u Action to o IA 0
I- o n~ X e tY ou7 c Report 5 u7 0 Prevent Recurrence (J
n0 790210 S 62.5 Low power, physics testing was completed after refueling, unit placed on the line on 4-3-'79 for continued physics testing and power operation.
790409 =512 A-B HH, VALVEX Annual overhaul of "A" Condensate Pump still in progress, "B" Conden-sate 'Pump Discharge. Valve position limited 'condensate pressure and feedwater flow.
790411 5.5 A EB RELAYX Hain transformer cooling fan relay failure.,
4 F: Forced Reason: hlethod: Fxhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-hlanual for Preparation of Data B-hlaintenancc or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 49.89 tRKV 8/78) H-Other (Explain) Exhibit 1 - Same Source
4 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO. 0-2 UNIT Ginna Station Unit b'1 DATE COMPLETED BY LEWIS DEP TELEPHONE 1-716-546-2700 Ext. 291-205, at Ginna MONTH A ril 1979 Low power physics testing were completed and unit was placed on the line on April 3. Turbine tests and physics testing were completed as power was escalated. At 98% power, the condensate bypass valve opened, power was reduced to 92%. The low condensate pressure was due to the "A" condensate pump still undergoing annual overhaul and the discharge valve of the "B" condensate pump was not in the full open position due to a faulty position indicator. On,Apiil 11, a relay on the main transformer fan coolers failed, load reduction was started and terminated when the fan coolers were reinstalled.
Operation at 92% continued due to condensate pump maintenance.
49 I'23 0/78)
'4 s
0 GINNA STATION MAINTENANCE REPORT FOR APRIL, 1979 During April, normal inspection and minor maintenance was performed.
Major safety related maintenance included:
- 1. Replacement of a faulty bistable on Overpressure Protection Channel 452.
- 2. Replacement of a bad batch board on Boric Acid Flow Channel 110.
- 3. Replacement of a damaged valve diaphragm on the containment radiogas/particulate monitor pump return to containment.
- 4. Repair to the flow control valve FCV llOA for the normal flow path from the Boric Acid Tanks to the Reactor Coolant System.
- 5. Replacement of a leaking 3 1/2" long piece of pipe adjacent to FCV llOA. In addition, the check valve next to this piece of pipe was also replaced as a preventive measure.
4
~ r