ML20078K378: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:}} | {{#Wiki_filter:[ AVERAGE DAILY UNIT POWER LEVEL D / | ||
50-387 r/) =.... 3 DOCKET NO. | |||
L, " ' 2 UNIT One f DATE 09-08-83 hgg gY COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-2181 MONTH August, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 3 1034 g7 1036 1037 1032 2 18 3 958 39 1030 4 1032 20 1013 3 1034 21 1038 6 1036 22 1031 7 1033 23 1033 8 1032 24 1037 9 1010 25 1031 10 1044 26 1032 33 1636 27 1030 32 1042 gg 88 13 1045 29 0 14 1044 30 0 15 1027 33 0 16 1040 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 meswatt. | |||
(9/77) 8310190080 830908 PDR ADOCK 05000387 R PDR | |||
,- y l I o ) $@ | |||
d l Nv Y W /i_ _ _ _l 3 L Cl- RM l OPERATING DATA REPORT DOCKET NO. 50-387 p DATE 09-08-83 h NIC Sif COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-2181 OPERATING STATUS Unit 1 Notes | |||
: 1. Unit Name: Susauchanna Steam Electric Station | |||
* Year to date and cumulative | |||
: 2. Reporting Period: Au;ust, 1983 values for Item 16 adjusted | |||
: 3. Licensed Thermal Power (MWt): | |||
3293 due to availability of better | |||
: 4. Nameplate Rating (Gross MWe): 1152 data for June and July, 1983. | |||
: 5. Design Electrical Rating (Net MWe): 1065 | |||
: 6. Maximum Dependable Capacity (Gross MWe): 1068 | |||
: 7. Maximum Dependable Capacity (Net MWe): 1032 | |||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons: | |||
Items 6 and 7 may vary month-to-month until sufficient operating data has been gathered. | |||
: 9. Power Level To Which Restricted,If Any (Net MWe): None | |||
: 10. Reasons For Restrictions,If Any: None | |||
.t This Month i r.-to.Date Cumulative I1. Hours In Reporting Period 744 2040 2040 | |||
: 12. Number Of Hours Reactor Was Critical 650.5 1664.1 1664.1 | |||
: 13. Reactor Reserve Shutdown Hours 0 156.7 156.7 | |||
: 14. Hours Generator On-Line 650.5 1625.8 1625.8 | |||
: 15. Unit Reserve Shutdown Hours 0 0 0 l 16. Gross Thermal Energy Generated (MWH) 2,100,610 *4,554.685 *4.554.685 | |||
: 17. Cross Electrical Energy Generated (MWH) 693,580 1,469,790 1,469,790 l | |||
: 18. Net Electrical Energy Generated (MWH) 669,973 1,414.965 1;414.965 l | |||
: 19. Unit Service Factor 87.4 79.7 79.7 l | |||
: 20. Unit Availability Factor 87.4 79.7 79.7 l | |||
l 21. Unit Capacity Factor (Using MDC Net) 87.2 67.2 67.2 l 22. Unit Capacity Factor (Using DER Net) 84.6 65.1 65.1 | |||
: 23. Unit Forced Outage Rate 12.6 20.3 20.3 | |||
: 24. Shutdowns Scheduled Over Next 6 Mont'h s (Type. Date.and Duration of Each): | |||
l Unit 1/ Unit 2 Tie-in Outage to commence November 15, 1983. Scheduled to i | |||
last 29 days. | |||
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup: September 2, 1983 | |||
: 26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77 ) | |||
gANN4 yf )g M UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 ef ppg 0 | |||
R UNIT NAME One p DATE 09-08-81 4 | |||
kic N REPORT MONT11 August, 1983 COMPLE D BY T t z i | |||
e. | |||
- E E No. Date p. | |||
.$ E 3g | |||
};; }y5 Y5 Licensee Event 5% | |||
uy % | |||
Q Cause & Corrective Action to F | |||
$E 5 j di y Report # NU V Prevent Recurrence S | |||
W 16 830828 F 93.5 A 3 NA CC INSTRU With the unit at 100% power, scheduled main turbine stop valve testing was being performed. When the last main turbine stop valve opened, an MSIV isolation occurred. A scram followed due to the MSIV's being less than 94% | |||
full open. Spurious actuation of main steam line pressure switches is con-sidered to be the cause of the scram. | |||
One switch was replaced and the switch's operation will be monitored during plant opera t io n . In addition, pulsation dampeners were installed on the sensing lines to the main steam line pressure switches to reduce susceptibility of the switches to pressure oscillations. | |||
I 2 3 F: Forced S: Scheduled Reason: Method: 4} Exhibit G -Instructions | |||
~1 A Equipment Failure (Explain) 1 -Manual for Preparation of Data B. Maintenance of Test 2 Manual Scram. Entry Sheets fo Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG- | |||
'D-Regulatory Restriction 4-Ot her (Explain) 0161) | |||
E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il4)ther (Explain) | |||
SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date 09-08-83 Completed by L.A. Kuczynski Telephone (717)542-2181 Challenges to Main Steam Safety Relief Valves SRV 'B' automatically actuated to provide pressure control at 7.5 minutes after the August 28 scram. The SRV was open for approximately 3 minutes, during which RPV pressure decreased from 1078 psig to 913 psig. The valve rescated properly. | |||
Changes to the Offsite Dose Calculation Manual None. | |||
Major Changes to Radioactive Water Treatment Systems None. | |||
i QM Pennsylvania Power & Light Company Two North Ninth Street | |||
* Allentown, PA 18101 | |||
* 215 / 770L5151 Bruce D. Kenyon Vice President-Nucleat Operations 215/770-7502 SEP 121983 Director, Data Autcmation & | |||
Management Information Division Attention: Mr. M. R. Beebe Managenent Information Branch Office of Resource Management U.S. Nuclear Regulatory Ca mission Washington, D.C. 20555 SUSQUEHANNA STEAM ELDCTRIC STATICN NNIHLY OPERATING REPORT - AUGUST 1983 ER 100450 FIIE 841 PIA-1834 Docket No. 50-387 | |||
==Dear Mr. Beebe:== | |||
The August 1983 nonthly operating report for Susquehanna SES Unit 1 is attached. | |||
Very truly yours, | |||
~ | |||
. D. Kenyon Vice President-Nuclear Operations Attachment cc: Dr.Thcmas E. Murley INPO Records Center Regional Administrator-Region I Suite 1500 U.S. Nuclear Regulatory Ccumission 1100 Circle 75 Parkvay 631 Park Avenue Atlanta, Georgia 30339 King of Prussia, PA 19406 Director Mr. Thcmas E. Pollog Office of Inspection and Enforcement Department of Environmental U.S. Nuclear Regulatory Ccnmission Resources Washington, D.C. 20555 Bureau of Radiation Protection Attn: Document Control Desk (12 copies) P.O. Box 2063 Harrisburg, PA 17120 Mr. G. Rhoads - IRC Mr. R. Perch - NRC | |||
<}} |
Revision as of 00:41, 20 May 2020
ML20078K378 | |
Person / Time | |
---|---|
Site: | Susquehanna |
Issue date: | 09/08/1983 |
From: | Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO. |
To: | Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
References | |
PLA-1834, NUDOCS 8310190080 | |
Download: ML20078K378 (5) | |
Text
[ AVERAGE DAILY UNIT POWER LEVEL D /
50-387 r/) =.... 3 DOCKET NO.
L, " ' 2 UNIT One f DATE 09-08-83 hgg gY COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-2181 MONTH August, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 3 1034 g7 1036 1037 1032 2 18 3 958 39 1030 4 1032 20 1013 3 1034 21 1038 6 1036 22 1031 7 1033 23 1033 8 1032 24 1037 9 1010 25 1031 10 1044 26 1032 33 1636 27 1030 32 1042 gg 88 13 1045 29 0 14 1044 30 0 15 1027 33 0 16 1040 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 meswatt.
(9/77) 8310190080 830908 PDR ADOCK 05000387 R PDR
,- y l I o ) $@
d l Nv Y W /i_ _ _ _l 3 L Cl- RM l OPERATING DATA REPORT DOCKET NO. 50-387 p DATE 09-08-83 h NIC Sif COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-2181 OPERATING STATUS Unit 1 Notes
- 1. Unit Name: Susauchanna Steam Electric Station
- Year to date and cumulative
- 2. Reporting Period: Au;ust, 1983 values for Item 16 adjusted
- 3. Licensed Thermal Power (MWt):
3293 due to availability of better
- 4. Nameplate Rating (Gross MWe): 1152 data for June and July, 1983.
- 5. Design Electrical Rating (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 1068
- 7. Maximum Dependable Capacity (Net MWe): 1032
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
Items 6 and 7 may vary month-to-month until sufficient operating data has been gathered.
- 9. Power Level To Which Restricted,If Any (Net MWe): None
- 10. Reasons For Restrictions,If Any: None
.t This Month i r.-to.Date Cumulative I1. Hours In Reporting Period 744 2040 2040
- 12. Number Of Hours Reactor Was Critical 650.5 1664.1 1664.1
- 13. Reactor Reserve Shutdown Hours 0 156.7 156.7
- 14. Hours Generator On-Line 650.5 1625.8 1625.8
- 15. Unit Reserve Shutdown Hours 0 0 0 l 16. Gross Thermal Energy Generated (MWH) 2,100,610 *4,554.685 *4.554.685
- 17. Cross Electrical Energy Generated (MWH) 693,580 1,469,790 1,469,790 l
- 18. Net Electrical Energy Generated (MWH) 669,973 1,414.965 1;414.965 l
- 19. Unit Service Factor 87.4 79.7 79.7 l
- 20. Unit Availability Factor 87.4 79.7 79.7 l
l 21. Unit Capacity Factor (Using MDC Net) 87.2 67.2 67.2 l 22. Unit Capacity Factor (Using DER Net) 84.6 65.1 65.1
- 23. Unit Forced Outage Rate 12.6 20.3 20.3
- 24. Shutdowns Scheduled Over Next 6 Mont'h s (Type. Date.and Duration of Each):
l Unit 1/ Unit 2 Tie-in Outage to commence November 15, 1983. Scheduled to i
last 29 days.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: September 2, 1983
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77 )
gANN4 yf )g M UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 ef ppg 0
R UNIT NAME One p DATE 09-08-81 4
kic N REPORT MONT11 August, 1983 COMPLE D BY T t z i
e.
- E E No. Date p.
.$ E 3g
};; }y5 Y5 Licensee Event 5%
uy %
Q Cause & Corrective Action to F
$E 5 j di y Report # NU V Prevent Recurrence S
W 16 830828 F 93.5 A 3 NA CC INSTRU With the unit at 100% power, scheduled main turbine stop valve testing was being performed. When the last main turbine stop valve opened, an MSIV isolation occurred. A scram followed due to the MSIV's being less than 94%
full open. Spurious actuation of main steam line pressure switches is con-sidered to be the cause of the scram.
One switch was replaced and the switch's operation will be monitored during plant opera t io n . In addition, pulsation dampeners were installed on the sensing lines to the main steam line pressure switches to reduce susceptibility of the switches to pressure oscillations.
I 2 3 F: Forced S: Scheduled Reason: Method: 4} Exhibit G -Instructions
~1 A Equipment Failure (Explain) 1 -Manual for Preparation of Data B. Maintenance of Test 2 Manual Scram. Entry Sheets fo Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-
'D-Regulatory Restriction 4-Ot her (Explain) 0161)
E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il4)ther (Explain)
SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date 09-08-83 Completed by L.A. Kuczynski Telephone (717)542-2181 Challenges to Main Steam Safety Relief Valves SRV 'B' automatically actuated to provide pressure control at 7.5 minutes after the August 28 scram. The SRV was open for approximately 3 minutes, during which RPV pressure decreased from 1078 psig to 913 psig. The valve rescated properly.
Changes to the Offsite Dose Calculation Manual None.
Major Changes to Radioactive Water Treatment Systems None.
i QM Pennsylvania Power & Light Company Two North Ninth Street
- Allentown, PA 18101
- 215 / 770L5151 Bruce D. Kenyon Vice President-Nucleat Operations 215/770-7502 SEP 121983 Director, Data Autcmation &
Management Information Division Attention: Mr. M. R. Beebe Managenent Information Branch Office of Resource Management U.S. Nuclear Regulatory Ca mission Washington, D.C. 20555 SUSQUEHANNA STEAM ELDCTRIC STATICN NNIHLY OPERATING REPORT - AUGUST 1983 ER 100450 FIIE 841 PIA-1834 Docket No. 50-387
Dear Mr. Beebe:
The August 1983 nonthly operating report for Susquehanna SES Unit 1 is attached.
Very truly yours,
~
. D. Kenyon Vice President-Nuclear Operations Attachment cc: Dr.Thcmas E. Murley INPO Records Center Regional Administrator-Region I Suite 1500 U.S. Nuclear Regulatory Ccumission 1100 Circle 75 Parkvay 631 Park Avenue Atlanta, Georgia 30339 King of Prussia, PA 19406 Director Mr. Thcmas E. Pollog Office of Inspection and Enforcement Department of Environmental U.S. Nuclear Regulatory Ccnmission Resources Washington, D.C. 20555 Bureau of Radiation Protection Attn: Document Control Desk (12 copies) P.O. Box 2063 Harrisburg, PA 17120 Mr. G. Rhoads - IRC Mr. R. Perch - NRC
<