ML20073F491

Monthly Operating Rept for Feb 1983

ML20073F491
Person / Time
Site:	Susquehanna
Issue date:	03/09/1983
From:	Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML20073F462	List: ML20073F491 PLA-1565, Forwards Monthly Operating Rept for Feb 1983
References
NUDOCS 8304150497
Download: ML20073F491 (4)

Text

O

' l ANN 4 AVERAGE DAILY UNIT POWER LEVEL 4>4 D i Z '

---i DOCKET NO. 50-387 L- A4 UNIT nnn PPat

1. DATE 3-9-83 L.A. Kuczynski '

NIC 6W COMPLETED BY TELEPHONE (717)542-2181 February, 1983 l MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I 922 17 0' 2 958 g 0 3

978 0 9

4 882 20 0 5 892 21 0 6 1037 n 0 7

1039 0 3

8 1032 24 0 9 1036 25 0 10 892 184 26 11 1009 27 562 12 1053 28 896 0

13 9 0

14 30 15 0 3, 16 0

INS 1RUC110NS On this format, list the average daily unit power level in MWe-Net foi cach day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 8304150497 830309 PDR ADOCK 05000387 PDR R

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g L71 J- mnr* J OPERATING DATA REPORT O DOCKET NO. 50-387 h NIC g1 M DATE COMPLETED BY 1-4-R3 T. A - knnzynski TELEPHONE f7171542-2181 OPERATING STATUS

1. Unit Name: R"c""nhnnnn C +- o n m r' l o c + +- 4 " C + n +- i on r c o er a 17

2. Reporting Period: February 1981 on February 4, 1983

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1280 x 0.9 = 1152

5. Design Electrical Rating (Net MWe): 1152 - 41 = 1111

• MDC to be determined

6. Maximum Dependable Capacity (Gross MWe): ** Revised

7. Maximum Dependable Capacity (Net MWe):

8. If Chenges Occur in Capacity Ratings (!tems Number 3 Through 7) Since Last Report, Give Reasons:

Ronalen1ntinn of n y i n t- i n a cla t n

9. Power Level To Which Restricted,if Any (Net MWe): Nonn

10. Reasons For Restrictions,if Any: None This Month Yr.-to.Date Cumulative I1. Hours in Reporting Period 672 1416 2508.5

12. Number Of Hours Reactor Was Critical 383.3 1029.2 1959.2 _

13. Reactor Reserve Shutdown Hours 15 66_1 110_9

14. Hours Generator On Line 357.5 938.6 1791.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 988.690 2148.959** 3.443.424**

17. Gross Electrical Energy Generated (MWH) 332.590 71 R __7 2 0 1.063.140

18. Net Electrical Energy Generat:d (MWH) 316.633 681.500 1.002.805

19. Unit Service Factor N/A

20. Unit Availah;hty Factor N/A

21. Unit Capacity Factor (Using MDC Net) N/A

22. Unit Capacity Factor (Using DER Net) N/A

23. Unit Forced Outage Rate N/A

24. Shutdowns Scheduled Over Next 6 Months (Type Date,and Duration of Eacht:

None.

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY 0 7-A2 4-1n-82 INITIAL ELECTRICITY 11-19-82 11-16-82

( COMMERCIAL OPER ATION 5-15-83 (4/77)

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DOCfST NO ' EB 7 -

/- E f UNik SHUTDOWNS AND FOWER REDUCTIONS UNil NAME ~ -%

DATE 7 o 07 4 ' ,

L.A. Kuczvnski klC @p

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REPORT MONTH Februarv , lh83 ' ,; ',COMPLETTD BY

- TELEPHONE f717)542-2181

- B E

, .3 ? jY5 Licensee E r, yn. Cause & Corrective No. Date c. gg g .g g 5 Event gg Action to H

$5 5 j -ji y d

Report a mV

[ Prevent Recurrence 5 830212 S 314.5 B 3 N/A ZZ ZZZZZZ As part of scheduled startup testing, generator sync breaker was opened to simulate a load rejection. This caused a reactor scram on turbine control valve fast closure. A planned outage commenced at 1500 on 2-13-83.

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual 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 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) Il-Othes (Explain)

SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date 3-9-83 Completed By: L.A. Kuczynski Telephone (717)542-2181 February, 1983 Challanges to Main Steam Safety Relief Valves During the first four minutes of the scheduled High Power Generator Load Rejection Startup Test, main steam safety relief valves (SRV)

D, E and H lifted and re-seated. SRV E automatically opened a second time and re-seated. SRV A was opened manually to provide pressure control and was properly re-seated.

4 j

j Changes to Offsite Dose Calculation Manual None.

Major Changes to Radioactive Waste Treatment Systems None.

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