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| issue date = 06/30/1989 | | issue date = 06/30/1989 | ||
| title = Monthly Operating Rept for June 1989 for Re Ginna Nuclear Power Plant.W/890724 Ltr | | title = Monthly Operating Rept for June 1989 for Re Ginna Nuclear Power Plant.W/890724 Ltr | ||
| author name = | | author name = Dodge R, Mecredy R | ||
| author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | ||
| addressee name = | | addressee name = | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:A. | {{#Wiki_filter:A.C CElZ RATED Dl BU'EON DE M ONSTR TIO.'i SYSTEM 4 | ||
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS) | |||
ACCESSION NBR:8908030214 DOC.DATE: 89/06/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION DODGE,R.E. Rochester Gas & Electric Corp. | |||
MECREDY,R.C. Rochester Gas & Electric Corp. | |||
RECIP.NAME RECIPIENT AFFILIATION | |||
==SUBJECT:== | ==SUBJECT:== | ||
Monthly operating rept for June 1989 for RE Ginna Nuclear Power Plant.W/890724 ltr. D DISTRIBUTION CODE: IE24D COPIES RECEIWED:LTR ENCL SIZE: | |||
TITLE: Monthly Operating Report (per Tech Specs) | |||
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPIES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 3 3 PD1-3 PD 1 1 D JOHNSON,A 1 1 D | |||
INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 XRM TECH ADV 2 2 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/JEEP/RPB 10 1 1 NUDOCS-ABSTRACT 1 1 EG 01 1 1 RGN1 1 1 EXTERNAL EG&G S IMPSON I F 1 1 LPDR 1 1 NRC PDR 1 1 NSXC 1 1 NOTE 'IO ALL "RIBS" MKXPZEPIS S | |||
PLEASE HELP US 'IO REDUCE HASTE! CONI'ACZ 'IHE DOCXJMKI'XWZROL DESK ROCN Pl-37 (EXT. 20079) IO EIaIMZNATE KRR NAME HEM DISI%GH7ZXCN LISTS FOR DOCUKRPIS YOU DGN~T NEED! | |||
TOTAL NUMBER OF COPXES REQUIRED: LTTR 19 ENCL 19 | |||
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, 0 t Eel (Al~ *A ROCHESTER GAS AND ELECTRIC CORPORATION o 69 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE | |||
*ma* coos 7ia 546.2700 GINNA STATION July 24, 1989 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | |||
==Subject:== | ==Subject:== | ||
Monthly Report for June, 1989 Operating Status Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 r | |||
==Dear Sir:== | |||
Pursuant to our Technical Specification 6.9.1, attached herewith is the monthly operating status report for Ginna Station for the month of June, 1989. | |||
Very truly yours, Robert C. Me re General Manager Nuclear Production RCM/eeh Attachments cc: Mr. William T. Russell NRC (1) aqppp3pg]4 +90&3 PDR PDQCK p~~. | |||
R | |||
OPERAT(NG DATA REPORT DOCKET NO. 50 244 l 24, 1989 COMPLETED BY Robert E. Dodg TELFPHONE 315-524-4446 x-396 OPERATING STATUS Ginna Station I ~ Unit Name: R.E. 6INNA NUCLEAR POWER PLANT Notes | |||
: 2. Reporting Period: June, 1989 | |||
: 3. Licensed Thermal Power (MWt): 1520 The unit operated at approx. | |||
: 4. Nameplate Rating (Gross MWe): 490 100% power for the majority | |||
: 5. Design Electrical Rating (Nct MWe): 470 of the report period, with a few exceptions detailed | |||
: 6. Maximum Dependable Capacity (Gross MWe)t 490 on page 4 of the report. | |||
: 7. Maximum Dependable Capacity (Net MWe): 470 | |||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Rcport, Give Reasons: | |||
: 9. Power Level to Which Restricted, If Any (Nct MWc): | |||
: 10. Reasons For Restrictions, If Any: | |||
This Month Yr.-to-Date Cumulative | |||
: 11. Hours In Reporting Period 720 4,343 172,169.45 | |||
: 12. Number of Hours Reactor Was Critical 636.74:~ 2,514.23 134,211.84 | |||
: 13. Reactor Reserve Shutdown Hours 1,687.55* | |||
: 14. Hours Gcncrator On-Line 630.5 2,455.75 131,727.63 | |||
: 15. Unit Reserve Shutdown Hours 0 8.5* | |||
: 16. Gross Thermal Energy Generated (MWH) 878, 174 3,517,368 185,487,782 | |||
: 17. Gross Electrical Energy Generated (MWH) 294, 833 1,187,058 60,986,387 | |||
: 18. Nct Flectrical Energy Gencratcd (MWH) 1,127,294 57,871,752 | |||
: 19. Unit Service Factor 87.57 56.55 76.69 | |||
: 20. Unit Availability Factor 87.57 56.55 76.69 | |||
: 21. Unit Capacity Factor (Using MDC Nct) 82.58 55. 23 73.05 | |||
: 22. Unit Capacity Factor (UsingDER Net) 82.58 55.23 73.05 | |||
: 23. Unit Forced Outage Rate 12.43 4.31 6.34 | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): | |||
: 25. If Shut Down A't End Of Report. Period, Estimated Dace of Startup: | |||
: 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMFRCIAL OPERATION | |||
*Cumnulative total comnencing January 1, 1975 Atv. 44$ 49 88 | |||
>v AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant DATE Jul COMPLETED BY 4 | |||
Robert E. | |||
989 r D ge TELEPHONE 1 315 524-4446 Ext. 396 at Ginna MONTH June 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 101 17. 485 2 ~ 18 485 | |||
'9 3 ~ 363 ~ 474 4 ~ 430 20. 485 | |||
: 5. 459 21. 445 | |||
: 6. 482 22 | |||
'3 7 ~ 486 | |||
: 8. 482 | |||
'4. | |||
-14 9 ~ 481 25. 160 | |||
: 10. 482 26. 475 486 27 477 | |||
: 12. 486 | |||
'8. | |||
477 13 ~ 486 29 475 14. | |||
'0. | |||
486 475 15 485 31. | |||
'6. | |||
484 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. | |||
DOCKI:.T NO. SO 244 liNITNAME. R E- GINNA NUCLEAR POWER PLANT UNIT SHUTDOWN AND POWER REDUCTIONS DATE | |||
(:OhIPLETED BY Robert E. | |||
REPORT MONTH JULY 1989 TELEPIIONE 315-524-4446 x-396 sana a ion C Pl c ~ cn>>0 c C o au4 Licensee Ew OIA co Cause L Corrective 0 | |||
Ho. Dote 0 o P 0 o>>> 4 Event 0 5 Q Action to Q | |||
o&~ o cd Eo n.'l c Report 0 EA 0 | |||
(J E o Prevent Recurrence | |||
'U 0 | |||
CL 89-3 6-1-89 17 H 89-"004 IE Reactor trip was due to a turbine trip with reactor power greater than 509, due to an AMSAC actuation. | |||
Corrective Action: affected procedures were changed to ensure ANSAC is reset. | |||
89-4* 6-22-89 476 H 89-007 SF SF SI pump design flaw delivery con-cerns. Incorrect original calibration data. | |||
Corrective Action: correct calibra-tion data was confirmed for each orifice/flow transmitter combination 1 | |||
3 F: Forced Reason: hlethod: Fxhibit G - Instructions S: Scheduled A-Equipmcnt Failure (Explain) 1-hlanual for Preparation of Data B-Maintenance or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction'-Operator 4-Other (Explain) 0161) | |||
Training gc License Examination F-Administrative G-Operational Error (Explain) | |||
REV. 4/85 4949 H-Ocher (Explain) Exhibit 1 - Same Source "Yearly Outage Number | |||
'o tt V | |||
t( | |||
NARRATIVE | |||
== | ==SUMMARY== | ||
OF OPERATING EXPERIENCE DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant DATE Jul 2 19 9 COMPLETED BY obert E. Dod e TELEPHONE 1 315 524-4446 EXT. 396 at Ginna MONTH June 1989 The unit operated at 100% reactor power level for the majority of the report period, with some exceptions, detailed below. | |||
On June 1, 1989 at 1332 EDST, with the reactor at approximately 534 power, a turbine trip with subsequent reactor trip occurred due to a ATNS Mitigation System Actuation Circuitry (AMSAC). | |||
On June 19, 1989 at 1440 EDST with the reactor at approximately 994 full power the "B" and "C" Safety Injection (SI) pumps were declared inoperable due to assessed design flow delivery concerns. | |||
On June 21, 1989 at 1401 a similar problem occurred with the "B" and "C" SI pumps and plant management decided to shut the plant down until the SI pump flow concerns were resolved. The plant was shutdown and subsecpxently cooled down to less than 350oF}} | |||
Latest revision as of 04:32, 4 February 2020
ML17309A429 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 06/30/1989 |
From: | Dodge R, Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 8908030214 | |
Download: ML17309A429 (7) | |
Text
A.C CElZ RATED Dl BU'EON DE M ONSTR TIO.'i SYSTEM 4
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)
ACCESSION NBR:8908030214 DOC.DATE: 89/06/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION DODGE,R.E. Rochester Gas & Electric Corp.
MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Monthly operating rept for June 1989 for RE Ginna Nuclear Power Plant.W/890724 ltr. D DISTRIBUTION CODE: IE24D COPIES RECEIWED:LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPIES RECIPIENT COPXES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 3 3 PD1-3 PD 1 1 D JOHNSON,A 1 1 D
INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 XRM TECH ADV 2 2 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/JEEP/RPB 10 1 1 NUDOCS-ABSTRACT 1 1 EG 01 1 1 RGN1 1 1 EXTERNAL EG&G S IMPSON I F 1 1 LPDR 1 1 NRC PDR 1 1 NSXC 1 1 NOTE 'IO ALL "RIBS" MKXPZEPIS S
PLEASE HELP US 'IO REDUCE HASTE! CONI'ACZ 'IHE DOCXJMKI'XWZROL DESK ROCN Pl-37 (EXT. 20079) IO EIaIMZNATE KRR NAME HEM DISI%GH7ZXCN LISTS FOR DOCUKRPIS YOU DGN~T NEED!
TOTAL NUMBER OF COPXES REQUIRED: LTTR 19 ENCL 19
~
~'vzz uze uiI"iI
@au
, 0 t Eel (Al~ *A ROCHESTER GAS AND ELECTRIC CORPORATION o 69 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE
- ma* coos 7ia 546.2700 GINNA STATION July 24, 1989 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Monthly Report for June, 1989 Operating Status Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 r
Dear Sir:
Pursuant to our Technical Specification 6.9.1, attached herewith is the monthly operating status report for Ginna Station for the month of June, 1989.
Very truly yours, Robert C. Me re General Manager Nuclear Production RCM/eeh Attachments cc: Mr. William T. Russell NRC (1) aqppp3pg]4 +90&3 PDR PDQCK p~~.
R
OPERAT(NG DATA REPORT DOCKET NO. 50 244 l 24, 1989 COMPLETED BY Robert E. Dodg TELFPHONE 315-524-4446 x-396 OPERATING STATUS Ginna Station I ~ Unit Name: R.E. 6INNA NUCLEAR POWER PLANT Notes
- 2. Reporting Period: June, 1989
- 3. Licensed Thermal Power (MWt): 1520 The unit operated at approx.
- 4. Nameplate Rating (Gross MWe): 490 100% power for the majority
- 5. Design Electrical Rating (Nct MWe): 470 of the report period, with a few exceptions detailed
- 6. Maximum Dependable Capacity (Gross MWe)t 490 on page 4 of the report.
- 7. Maximum Dependable Capacity (Net MWe): 470
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Rcport, Give Reasons:
- 9. Power Level to Which Restricted, If Any (Nct MWc):
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 720 4,343 172,169.45
- 12. Number of Hours Reactor Was Critical 636.74:~ 2,514.23 134,211.84
- 13. Reactor Reserve Shutdown Hours 1,687.55*
- 14. Hours Gcncrator On-Line 630.5 2,455.75 131,727.63
- 15. Unit Reserve Shutdown Hours 0 8.5*
- 16. Gross Thermal Energy Generated (MWH) 878, 174 3,517,368 185,487,782
- 17. Gross Electrical Energy Generated (MWH) 294, 833 1,187,058 60,986,387
- 18. Nct Flectrical Energy Gencratcd (MWH) 1,127,294 57,871,752
- 19. Unit Service Factor 87.57 56.55 76.69
- 20. Unit Availability Factor 87.57 56.55 76.69
- 21. Unit Capacity Factor (Using MDC Nct) 82.58 55. 23 73.05
- 22. Unit Capacity Factor (UsingDER Net) 82.58 55.23 73.05
- 23. Unit Forced Outage Rate 12.43 4.31 6.34
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
- 25. If Shut Down A't End Of Report. Period, Estimated Dace of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMFRCIAL OPERATION
- Cumnulative total comnencing January 1, 1975 Atv. 44$ 49 88
>v AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant DATE Jul COMPLETED BY 4
Robert E.
989 r D ge TELEPHONE 1 315 524-4446 Ext. 396 at Ginna MONTH June 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 101 17. 485 2 ~ 18 485
'9 3 ~ 363 ~ 474 4 ~ 430 20. 485
- 5. 459 21. 445
- 6. 482 22
'3 7 ~ 486
- 8. 482
'4.
-14 9 ~ 481 25. 160
- 10. 482 26. 475 486 27 477
- 12. 486
'8.
477 13 ~ 486 29 475 14.
'0.
486 475 15 485 31.
'6.
484 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.
DOCKI:.T NO. SO 244 liNITNAME. R E- GINNA NUCLEAR POWER PLANT UNIT SHUTDOWN AND POWER REDUCTIONS DATE
(:OhIPLETED BY Robert E.
REPORT MONTH JULY 1989 TELEPIIONE 315-524-4446 x-396 sana a ion C Pl c ~ cn>>0 c C o au4 Licensee Ew OIA co Cause L Corrective 0
Ho. Dote 0 o P 0 o>>> 4 Event 0 5 Q Action to Q
o&~ o cd Eo n.'l c Report 0 EA 0
(J E o Prevent Recurrence
'U 0
CL 89-3 6-1-89 17 H 89-"004 IE Reactor trip was due to a turbine trip with reactor power greater than 509, due to an AMSAC actuation.
Corrective Action: affected procedures were changed to ensure ANSAC is reset.
89-4* 6-22-89 476 H 89-007 SF SF SI pump design flaw delivery con-cerns. Incorrect original calibration data.
Corrective Action: correct calibra-tion data was confirmed for each orifice/flow transmitter combination 1
3 F: Forced Reason: hlethod: Fxhibit G - Instructions S: Scheduled A-Equipmcnt Failure (Explain) 1-hlanual for Preparation of Data B-Maintenance or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction'-Operator 4-Other (Explain) 0161)
Training gc License Examination F-Administrative G-Operational Error (Explain)
REV. 4/85 4949 H-Ocher (Explain) Exhibit 1 - Same Source "Yearly Outage Number
'o tt V
t(
NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant DATE Jul 2 19 9 COMPLETED BY obert E. Dod e TELEPHONE 1 315 524-4446 EXT. 396 at Ginna MONTH June 1989 The unit operated at 100% reactor power level for the majority of the report period, with some exceptions, detailed below.
On June 1, 1989 at 1332 EDST, with the reactor at approximately 534 power, a turbine trip with subsequent reactor trip occurred due to a ATNS Mitigation System Actuation Circuitry (AMSAC).
On June 19, 1989 at 1440 EDST with the reactor at approximately 994 full power the "B" and "C" Safety Injection (SI) pumps were declared inoperable due to assessed design flow delivery concerns.
On June 21, 1989 at 1401 a similar problem occurred with the "B" and "C" SI pumps and plant management decided to shut the plant down until the SI pump flow concerns were resolved. The plant was shutdown and subsecpxently cooled down to less than 350oF