PLA-1986, Monthly Operating Rept for Nov 1983

Monthly Operating Rept for Nov 1983

ML20086G646
Person / Time
Site:	Susquehanna
Issue date:	11/30/1983
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-1986, NUDOCS 8401120327
Download: ML20086G646 (6)

Text

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~. AVERAGE DAILY UNIT POWER LEVEL Q }

Y ft) .._. 3 DOCKET NO. 50-387 L '

UNIT one

<p 30 DAir 12/07/83 ggg g COMPLETED BY L.A. Kuczynski TELEPHONE (717)S42-2181 MONTH November, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I 1055 1026 17 2 456 13 1058 3 0 19 1055 4 176 20 1049 _

5 385 21 1054 6 596 22 1054 7 763 1039 23 g 844 790 24 9 289 25 886 Io 140 26 1052 11 744 27 1052 12 718 1057 28 13 981 1057 29 14 1058 30 1057 15 1055 3g 16 1044 l

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to i the nearest whole megawatt.

l (9/77) 8401120327 831130 PDR ADOCK 05000387 R PDR i

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LD  ! *% OPERATING DATA REPORT 30 DOCKET NO. 50-387 4 DATE 12/07/83 7

0 'NIC STf COMPLETED BY L.A. Kuczynski TELEPHONE (7171542-2181 OPERATING STATUS Unit 1 Notes

1. Unit Name: Susauehanna Steam Electric station

2. Reporting Period: Novmber, 1983 3293

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 1152

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:

None

9. Power Level To Which Restricted,If Any (Net MWe): None

10. Reasons For Restrictions,If Any: None This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 720 4,225 4.225

12. Number Of Hours Reactor Was Critical 670.1 3,793.5 3,793.5

13. Reactor Reserve Shutdown Hours 0 156.7 . 156.7

14. Hours Generator On.Line 653.6 3,716.5 3,716.5 0 0 0

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1,863,922 11,087,858 11,087,858

17. Gross Electrical Energy Generated (MWH) 612,120 3,613,650 3,613,650

18. Net Electrical Energy Generated (MWH) 590,195 3,485,616 3;485,616

19. Unit Service Factor 90.8 88 88

20. Unit Availability Factor 90.8 88 88

21. Unit Capacity Factor (Using MDC Net) 79.4 79.9 79.9

22. Unit Capacity Factor (Using DER Net) 77 77.5 77.5

23. Unit Forced Outage Rate 9.2 12.0 12.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):

Unit 1 - Unit 2 Tie-in Outage to ommence December 3,1983. Scheduled to last 36 days.

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERATION (4/77 )

Sy 9' kf\ v, 2

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 UNIT NAME One kf PPat M OATE 17-07 -M COMPLETED BY L. A. Kuczynski

&lC N REPORT MONTH November, 1983 TELEPHONE (717)542-2181 n.

- B E No. Date g

.!E 3g

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,s5 Licensee Event p E t. $"',

c'8 Cause & Corrective Action to F

$E $ j ;5 g Report a mO $U Prevent Recurrence 17 831102 F 37.4 :1 3 NA HG DEMINX The scram was caused by momentary

• greater than three times normal radia-tion in the Main Steam lines. Deminer-alizer resin fines entered the reactor coolant system and caused a short-term increase in radioactive nitrogen in the main steam.

18 831109 F 29.0 A 3 NA Cll INSTRU The feedwater level feedback signal failed low, causing the feedwater level controller to increase to 100%. This yielded a main turbine trip on high RPV level with a subsequent reactor scram on turbine control valve fast closure. The vessel level /feedflow/

steam flow summer was replaced and addit-ional monitoring of other input signals from the feedwater level con-trol system has been instituted.

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 of 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 i . Same Source (9/77) II-Other (Explain) h

gANN4

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DOCKET NO. 50-387 UNIT SHUTDOWNS AND POWER REDUCTIONS kf E RIC N f[ REPORT MONTH November, 1983 UNIT NAME One COMPLETED BY DAR TELEPff0NE 12-07-83 L. A. Kuczynski (717) 542-2181 e.

, .$ ? }g .$h Licensee E-s, wt Cause & Corrective No. Date g 3g ,j$ Event g? o. Action to H

$. 5 j gg g a

Report # mV

[3 U Prevent Recurrence 19 831124 F 0 B 4 NA CH HTEXCH Power reduction for maintenance on feedwater heaters. Extended administrative 1y to place condensate demineralizer in service.

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 of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Peport (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

EOperator Training & Uce.w Examination F-Administ rative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) 110ther (Explain) i

'y.

SUSQUEHANtB STEAM ELECIRIC S'IATION Docket Ntaber 50-387- Date 1247-83

- Otmpleted by L.A. Kuczynski Telephone (717)S42-2181 Challanges to Main Steam Safety Relief Valves

SRV A' was manually actuated to provide pressure control 7 minutes after the Novmber 3,1983 scram. . h SRV was open for 5 minutes during which tine RPV

. pressure decreased frca 1061 psig to 850 psig. h valve reseated properly.

-SRV's 'B', 'C' and 'D' were also manually actuated during the scram recovery process.. SRV 'B' was opened twice, for a total open time of 6.8 minutes;

.SRC.'C' w u opened once for 3.6 minutes; SRV 'D' was also opened for 4.7 minutes. All valves reseated properly. '1he SRV's were opened in alpha-betical order as directed by the scram recovery procedure. '1his assures even distribution of heat addition to the Suppression Pool.

Changes to the Offsite Dose Calculation Manual None i Major Changes to Radioactive Waste Treatment Syst e s None 1

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. i PP&L Pennsylvania Power & Light Company 1 Two North Ninth Street

• Allentown, PA 18101 = 215 / 770 5151 '

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Bruce D. Kenyon Vice President-Nuclear Operations 215/770-7502 DEC 151983 Director, Data Automatien &

Management Information Division Attention: Mr. M. R. Beebe Management Information Branch Office of Resource Managment U.S. Nuclear Rec.11atory Cmmission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECI'RIC STATION MCNIHLY OPERATING REPORT - NOVENBER 1983 ER 100450 FIIE 841 PIA-1986 Docket No. 50-387

Dear Mr. Beebe:

The November 1983 monthly operating report for Susquehanna SES Unit 1 is attached.

Very truly yours, I

W n

. D. I Vice President-Nuclear Operations Attachment cc: Dr. 'Ihmas E. Murley INPO Records Center Regional Administrator-Region I Suite 1500 U.S. Nuclear Regulatory Comnission 1100 Circle 75 Parkway 631 Park Avenue Atlanta, Georgia 30339 King of Prussia, PA 19406 Director Mr. Thmas E. Pollog Office of Inspection and Enforcement Department of Environmental U.S. Nuclear Regulatory Ca mission 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 - NRC Mr. R. Perch - NRC

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