ML20097A284

Monthly Operating Repts for Jul 1984

ML20097A284
Person / Time
Site:	Susquehanna
Issue date:	07/31/1984
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2273, NUDOCS 8409130229
Download: ML20097A284 (10)

Text

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[ AVERAGE DAILY UNIT POWER LEVEL l D \

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3 DOCKET NO. 50-387 L

m,^' One UNIT 30 DATE Auoust 9, 1984 0 7g cgth COMPLETED BY L. A. Kuczynski TELEPHONE .(717)542-3759 MOM July, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I 962 g7 -0 2 1035 ig 21 3 607 39 142 4 0 662 20 s 0 814 21 6 0 1019 22 7 0 1027 23 8 0 1020 24 9 167 25 1025 10 601 9bb 26 11 724 27 1023 12 964 28 1021 13 1030 29 966 14 1030 30 1022 15 385 31 1021 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 rnegawatt.

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(9/77) l 8409130229 840731 DR ADOCK 05000 -d If(

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h D \v 7 W . .. 3 L  ! Emb OPERATWG DATA REPORT Q DOCKET NO. 50-387 1 M

.", DATE August 9, 1984 C gT COMPLETED BY L. A. Kuczynski TELEPHONE (717)542-3759 OPERATING STATUS Unit 1 Notes

1. Unit Name: Sosquehanna Steam Electric Station

2. Reporting Period: Julv. 1984

3. Licensed Thermal Power (MWt): 3293

4. I ameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe):

1068

7. Maximum Dependable Capacity (Net MWe): 1012

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 i1. Hours In Reporting Period 744 5,111 10,080

12. Number Of Hours Reactor Was Critical 563.4 3,151.4 6,996.7

13. Reactor Reserve Shutdown Hours 220.1 249.1 405.8

14. Hours Generator On.Line 523.9 3,026.7 6,795

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,491,021 9,074,830 20,336,491

17. Gross Electrical Energy Generated (MWH) 481.250 2,965,470 6,632,020

18. Net Electrical Energy Generated (MWH) 461,555 2,853,780 6,390,153

19. Unit Service Factor 70.4 59.2 67.4

20. Unit Availability Factor 70.4 59.2 67.4

21. Unit Capacity Factor (Using MDC Net) 60.1 __ __

54.1 61.4

22. Umt Capacity Factor (Using DER Net) 58.2 52.4 59.5

23. Unit Forced Outage Rate 29.6 21.2 16.3

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

None

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

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

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME One

$ Pral C[ DATE Auoust 9. 1984 k Ric 9# REPORT MONTli July. 1984 COMPLETED BY L.A. Ku czvnski TELEPHONE (71719fs7 ~4744 w.

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, .! E 3ij $ Y3 Licensee h h Cause & Corrective No. Date g 3g jj$ Event g? g3 Action to H

$E 5 j iji g Report a mO g' Prevent Recurrence d

6 840703 F 134.6 H 3 84-029 CI: INSTRU The unit scrammed on low vessel level '

caused by a momentary loss of signal to feedwater and reactor recirculation circuitry following a lightning strike to a transmission line which supplies the station. Extensive post scram test-ing' of the feedwater system could not reproduce the response that occurred (see attached page) 7 840715 F 30.4 H 3 84-034 EA ELECON The unit scrammed on turbine control valve fast closure as a result of a phase-to phase faul t on the 230KV trans-vission line. The tree which had grown (see attached page) 8 840716 F 26.4 A 3 84-033 HC VALVEX The unit scrammed on turbine control valve fast closure by loss of condenser (see attached page) 9 840718 F 28.7 G 3 84-035 HC VALVEX The uni t scrammed due to loss of con-denser vacuum. The loss of vacuum was (see attached oaoe) 1 2 3 4 F: Forced Reason: M-thod: Exhibit G . Instructions S: Scheduled A-Equipment Failure (Explain) 1-Idanual 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-OperaConal Error (Explain) Exhibit I - Same Source (9/77) II-Other (Explain) i

-UNIT SHUTDOWNS AND POWER' REDUCTIONS (continued):

NO.- 6 :

following the momentary loss of signal . A modification was completed to prevent the -reactor recirculation system from receiving a false runback

- signal flf the same circums' .ces were to occur.

NO. 7:

tall enough to cause the phase-to-phase arc has been trimmed.

1NO. 8 :

vacuum due to a operator inadvertently opening the LP condenser vacuum--

breaker.

NO.9:

caused by an incorrect valve lineup established'due to an unclear valve number on a piping diagram. The discrepancy was resolved.

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' UNIT-1 SUSQUEHANNA STEAM ELECTRIC. STATION Docket Number. 50-387 .Date 8/9/84 Completed by L.A. Kuczynski Telephone (717)S42-2181 Challenges to Main Steam Safety Relief Valves .

~ During the scram.of July' 3,- 1984, safety relief valve ' B' was manua'. ly actuated for RPV pressure control . It was closed af ter 7 minutes,

20 seconds, during which time -reactor pressure went from approximately 1075 psig to approximately 880 pounds.

During the scram of July 15,1984, safety relief val ves 'B', 'E', and

'H actuated.- SRV 'H' closed after. two seconds, 'E' after 10 seconds, and 'B' after 11 seconds. Reactor pressure went from 1081 psig to

~975 psig during the 12 seconds.

Changes to the Offsite Dose Calculation Manual None.

Major Changes to Radioactive Waste Treatment Systems None.

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, AVERAGE DAILY UNIT POWER LEVEL

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3 DOCKET NO. 50-388 L. J UNIT Two

< s0 DATE Auoust 9, 1984 O

?g gib COMPLETED 8Y L. A. Kuczynski TELEPHONE (717)542-3759 MON 111 July, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWEk LEVEL (MWe-Net) (MWe-Net) 1 0 0 37 2 0 is 275 3 03 19 314 4 114 326 20 5 0 340 21 6 0 337 22 7 0 358 23 g 16 344 24 9 111 349 25 10 279 26 1 11 310 27 0 12 336 28 0 13 337 29 0 14 296 30 0 15 113 0 3

16 0 INSTRUCTIONS On this format. list the average dai'y unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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D \v \ Y W J. _ _ _l' 3 L t' L - IIIlN J OPERATING DATA REPORT 30 DOCKETNO. 50-388 DATE Aucust 9. 198h

'OpRI CS if COMPLETED BY L. A. Kuczynski 1ELEPHONE (717)542-3759 OPERATING STATUS Unit 2 Notes

1. Unit Name: Susauehanna Steam Electric Station

2. Reporting Period: July, 1984 initial generator sync. at

3. Licens1d Thermal Power (MWt):

3293 0230 on 7/3/84.

1152 initial electrical produc-

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1065 tion at 1300 on 7/3/84.

6. Maximum Dependable Capacity (Gross MWe):

• .To be determ.ined.

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:

None None

9. Power Level To Which Restricted,If Any (Net MWe): Zero. f rom 7/27 - 31/84.

10. Reasons For Restrictions,If Any: NRC issued Confirmatory Order, dated July 27, 1984 to prevent restart of the unit pending investigation of events of 7/26/84.

Unit restart approved July 31, 1984.

This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 683 683 683

12. Number Of Hours Reactor Was Critical 458.7 458.7 __

458 .7

13. Reactor Reserve Shutdown Hours 180.3 180.3 180.3

14. Hours Generator On-Line 392 9 392.9 392.9

15. Unit Reserve Shutdown Hours 142.4 142.4 142.4

16. Gross Thermal Energy Generated (MWH) 474,034 _ 474.034 474.03h

17. Gross Electrical Energy Generated (MWH) 121.330 121,330 121.330

18. Net Electrical Energy Generated (MWH) 110,281 110,281 110.281

19. Unit Service Factor NA NA NA

20. Unit Availability Factor NA _

NA NA

21. Unit Capacity Factor (Using 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 Schedulco Over Next 6 Months (Tyne. Date.and Duration of Each):

Maintenance Outage 10/27/84, 7 weeks

25. If Shut Down At End Of Report Period. Estimated Date of 5tartup: 8/1/84

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 05/09/84 05/08/84 INITIAL ELECTRICITY 06/28/84 07/03/84 COMMERCIAL OPER ATION 12/31/84 (9/77) 1

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• h UNIT SHUTDOW'dS AND POWER REDUCTIONS DOCKET NO. 50-388

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[ UNIT NAME Two DATE Auaust 9. 1984 L.A. Kuczynsk i klC @[ REPORT MONTH

.uly, 1984 COMPLETED BY TELEPHONE (717)542-3759 e.

, .$ E };; Y Licensee Eg 'o Cause & Corrective N i. Date o- 3g ,c g 5 Event p o8 Action to N $5 5 j ;5 g Repor # mO

[U Prevent Recurrerice 8

1 860705 S 85.6 B 2 NA ZZ ZZZZZZ Reactor scram for scheduled startup '

testing.

2 840715 F 60.2 A 3 84-034 HC RECOMB Reactor scram due to turbine trip (Unit #1 LER caused by low condenser vacuum.

Number) 3 840726 S 142.4 8 3 84-013 ZZ ZZZZZZ Reactor scram for scheduled startup testing. Due to an incorrectly com-pleted electrical lineup, the diesel generators were prevented from start-ing and an Unusual Event was decla red.

The startup test was subsequently re-peated and completed successfully.

NOTE  : 1) Genera tor removed from service or 1.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on 7/3/84 and 0.3 hours on 7/9/84 for startup testing.

2) Add LE R Nunuer 84-039 to Unit Shutdown of June 11, 1 984. .

t 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance ci 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) 11-01her (Explain)

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Unit 2 SUSQUEHANNA STEAM ELECTRIC STATION Docket Number. 50-388 Date 8/9/84

- Completed By L. A. Kuczynski Telephone (717)S42-3759 Challenges to Main Steam Safety Relief Valves Following the scram of July 26, 1984, SRV ' l' lif ted eight times at approx-Imately. five munute intervals to Ilmit the reactor vessel pressure increase caused by decay heat. The relief pressure setpoint of the 'J' SRV was checked and found to be low. The setpoint was adjusted to its proper value.

All other SRV relief setpoints were checked. Three additional setpoints were found cut of tolerance and recalibrated.

Changes to the Offsite Dose Calculation Manual None.

Major Changes to Radioactive Waste Treatment Systems None, i

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PPaL Pennsylvania Power & Light Company

Two North Ninth St.eet

• Allentown, PA 18101

• 215 / 770 5151 Bruce D. Kenyon '

Vice President-Nuclear Operations 215/770-7502 AUG 14 W4 Director Data Automation & ,

Management-Information Division Attention: Mr. M. R. Beebe Management 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-2273 50-388/NPF-22

Dear Mr. Beebe:

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

Vr trul urs, i

E'.

Sg D. Kenyon F 4% Vice President-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 Commitsion 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

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