PLA-2349, Monthly Operating Repts for Oct 1984

Monthly Operating Repts for Oct 1984

ML20099H459
Person / Time
Site:	Susquehanna
Issue date:	10/31/1984
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2349, NUDOCS 8411280154
Download: ML20099H459 (9)

Text

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, AVERAGE DAILY UNIT POWER LEVEL hM a (%$

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N -L \ DOCKET NO. 50-387 L' UNIT One 11-08-84

<p 30 DATE Jggg 3 COMPLETED BY L, A. Kuczynji TELEPHONE (717 M42-3759 MOM October, 1984 DAY A.VERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL s

(MWe-Net) (MWe-Net) 1033 37 54 2 994 18 432 3 962 g, o _

4 1047 :o o 5 1040 0 21 6 626 139 22 7 593 23 569 _

s 835 24 786 9 1007 25 1029 10 1000 1005 26 964 27 694 12 736 28 821 13 22 980 29 0

14 30 942 15 0 3g 1042 16 0 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.

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l LN+ ECri J OPERATING DATA REPORT PPat hO DOCKET NO. 50-387 DATE 11-08-84 COMPLETED BY L.A. Kuczynski IC SY TELEPHONE (717)542-3759 OPERATING STATUS Unit 1 Notes

1. Unit Name: Susauehanna Steam Electric Station

2. Reporting Period: October, 1984

3. Licensed Thermal Power (MWt): 3293

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 h; 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.lf Any: None This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 745 7,320 12,289

12. Number Of Hours Reactor Was Critical 586.8 5,200.3 9,045.6

13. Reactor Reserve Shutdown Hours 65.6 314.7 471.4

14. Hours Generator On-Line 554.8 5.043.7 8,812

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1.487.312 1s.161.312 26.422.937

17. Gross Electrical Energy Generated (MWH) 485,360 4.919.090 8,605,640

18. Net Electrical Energy Generated (MWH) 465,231 4,754,056 8.290.429

19. Unit Service Factor 74.s 68.9 71.7

20. Unit Availability Factor 74.5 68.9 71.7

21. Unit Capacity Factor (Using MDC Net) 60.5 62.9 65.4

22. Unit Capacity Factor (Using DER Net) 58.6 61 63.3

23. Unit Forced Outage Rate 25.5 16.7 14.7

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

Refueling Outage: February 9, 1985; 15 weeks.

25. If Shut Down As End Of Report Period. Estimated Date of Startup: NA j 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i

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L UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 i UNIT NAME One

$f Prat O DATE 11-nR-84 COMPLETED BY L.A. Kuczyn sk i

1. RIC 6I REPORT MONT110c tobe r. 1984 TELEPHONE (717)542-3759 n.

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, 3? 3 }o [g 5Ii Licensee 5% $% Cause & Corrective No. Date g 5g s Event gg Action to H

fI $ j gjj g Repint et mO g{ Prevent Recurrence 14 841006 S 0 H 5 NA RC FUELXX Scheduled power reduction to optimize fuel use until refuel ing ou*tage. Con-trol rod scram timing tests were also performed.

15* 841012 F 0 A 5 NA RB VALVEX Controlled power reduction begun in anticipation of Unit shutdown required to replace , disc holder assemblies in scram pilot solenoid valves.

16 841013 F 105.2 A 2 NA RB VALVEX Reactor scram to shutdown unit during replacement of disc holder assemblies in scram pilot solenoid valves.

17' 841018 F 85 B 2 84-045 RB VALVEX Reactor scram required to perform 18-month' surveillance of scram discharge

• volume vent and drain valves. Surveil-1ance failed on first attempt. Valves were replaced and s'urveillance success-fully. rerun on 10-21-84.

18 841027 S 0 H. 5 NA RC FUELXX Scheduled power reduction to optimize fuel use until refueling outage.

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 Continuation 0161)

E-Operator Training & License Examination from previous month F-Administrative 5-Reduction 5 G-Operational Error (Explain) Exhibit 1 Same Source (9/77) Il-Other (Explain) 9-Other -

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' UNIT 1 SUSQUEHANNA' STEAM ELECTRIC STATION Docket No. 50-387 Date 11-08-84 Completed by L. A. Kuczynski Telephone : (717)S42-3759 Challenges to Main Steam Safety Relief Valves None.

Changes to the Offsite Dose Calculation Manual None.

Major Changes to Radioactive Waste Treatment Systems None.

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4 AVERAGE DAILY UNIT POWER LEVEL D l (f) _ _ _ _ , 3 DOCKET NO. 50-388 L, C% UNIT Two

1. < E O DATE 11-08-84 O? h COMPLEED BY L.A. kczyr.sM l TELEPHONE (717)S42-3759 MONTH October, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 0 37 2 0 gg 0 3 346 g, 201 _

4 801 552 20 5 963 21 549 6 1017 22 560 7

1004 ,g 728 _

s 1001 950 24 9 995 25 1054 10 759 26 1053 11 961 3 l 27 12 762 0 23 13 40 29 -

14 0 0 30 15 0 0 33 16 0 l

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.

(9/77)

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3 L N J -- C'* J OPERATING DATA REPORT N Q d QOpNIC S [s 0 DOCKET NO. 50-388 DATE 11-08-84 L. A. Kuczynski T COMPLETED BY TELEPHONE (717)S42-3759 OPERATING STATUS Unit 2 Susquehanna Steam Electric Station Notes

1. Unit Name:

2. Reporting Period: October, 1984

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

• .

• To be determined. .

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 745 2,892 2.892

12. Number Of Hours Reactor Was Critical 492.5 2,145.9 2,145.9

13. Reactor Reserve Shutdown Hours 0 495 495

14. Hours Generator On-Line 435.6 1,769 3 1,769.3

15. Unit Reserve Shutdown Hours 0 142.4 142.4

16. Gross Thermal Energy Generated (MWH) 1.099.651 3.227.193 3,227,193

17. Gross Electrical Energy Generated (MWH) 359,970 989,040 989,040

18. Net Electrical Energy Generated (MWH) 344,563 932.026 932,026 NA NA NA

19. Unit Service Factor

20. Unit Availability Factor NA NA NA

21. Unit Capacity Factor IUsing MDC Net) NA NA NA

22. Unit Capacity Factor (Using DER Net) NA NA NA

23. Unit Forced Outage Rate NA NA NA

24. Shutdowns Scheduled 05er Next 6 Months (Type. Date.and Duration of Each):

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: December 26. 1984

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved l INITIA L CRITICALITY 05/09/84 05/08/84 INITIAL ELECTRICITY 06/28/84 07/03/84 COMMERCIAL OPERATION 01/31/85 (9/77)

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UNIT SHUTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-388 UNIT NAME Two E o DATE 11-08-84 k+ COMPLETED BY L,A. Kuczynski IRIC 6@D REPORT MONTII October, 1984 TELEPHONE (717)542-3759 c

-, E_ g 3 $5 Licensee Eg ga'L Cause & Corrective No. Date g 3g s .c s 5 Event g? g3 Action to H y= 5 j gjj c Repori2r mV V Prevent Recurrence b

13 840930 F 46 A 3 84-021 CC INSTRU Reactor scram due to turbine trip on high level in moisture separator drain tank. Hodifications to the moisture separator drain tank level control sys-tem are planned and 'will prevent recu r-rence.

14 841010 S 0 B 5 NA NA NA Power reduction for scheduled startup testing.

15 841013 F 144.2 B 2 NA RB VALVEX Reactor scram to shutdown Unit during replacement of disc holder assemblies in scram pilot solenoid valves.

16 841027 5 119 2 B 3 NA NA NA Reactor scram as part of scheduled startup testing. Pre-commercial outage commenced.

I 2 3 4

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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 Continuation 0161)

. E-Operator Training & License Examination from previous month F-Administrative 5-Reduction 5 G-Operational Error (Explain) Exhibii I - Same Source (9/77) llother (Explain) 9-Other

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UNIT 2 .

SUSQUEHANNA-STEAMj ELECTRIC STATION n 1

Docket No.

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50-388 Date 11-08-84 l- Completed by L.A. Kuczynski Telephone (717) 542-3759 5

' Challenges to Main Steam Safety Relief Valves Following the' scram'of October 27, 1984, SRVE' actuated.twice. 'For the

.first actuation, the SRV opened automatically and was' closed manually. The.

second actuation was entirely manual.

RX PRESSURE (psig) RX PRESSURE _(psig)

OPEN- CLOSED AT SRV OPEN AT SRV CLOSED i-l 01:52:59 01:58:49 1073 829-l 02:03:07 02:04:43 1074 904

[ On October 28, 1984,- SRVS' was manually actuated to reduce rea'ctor pressure l- to aid reactor cooldown at the start of the Pre-Commercial Outage.

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! 02:39:49 03:20:20 160 71

Changes to the Offsite Dose Calculation Manual None Major Changes to Radioactive Waste Treatment Systems None

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PP&L Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215 1 770 5151 Bruce D. Kenyon Vice President-Nuclear Operations 215/770-7502 NOV- 151384 Director, Data Automation &

Management Information Division Attention: Mr. M. R. Beebe Mcnagement Information Branch Office of Resource Management U.S. Nuclear Regulatory Commission

' Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORTS ER 100450 FILE 841 Docket Nos. 50-387/NPF-14 PLA-2349 50-388/NPF-22

Dear Mr. Beebe:

The October 1984 monthly operating reports for Susquehanna SES Units 1 and 2 are attached.

Very trul yours, wB. D. Kenyo Vice Presiden -Nuclear Operations Attachment cc: Dr. Thomas E. Murley INPO Records Center Regional Administrator-Region I Suite 1500 U.S. Nuclear Regulatory Commission 1100 circle 75 Parkway 631 Park Avenue Atlanta, Georgia 30339 King of Prussia, PA 19406 Director Mr. Thomas E. Pollog Office of Inspection and Enforcement Department of Environmental U.S. Nuclear Regulatory Commission Resources Washington, D.C. 20555 Bureau of Radiation Protection Attn: Document Control Desk (12 copies) P.O. Box 2063 Harrisburg, PA 17120 Mr. R. H. Jacobs - NRC Mr. R. L. Perch - NRC j h,

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