ML20024F066

Monthly Operating Rept for Jul 1983.W/830815 Ltr

ML20024F066
Person / Time
Site:	Susquehanna
Issue date:	08/08/1983
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-1787, NUDOCS 8309080175
Download: ML20024F066 (7)

Text

I A 1 s ,

@ Pennsylvania Power & Light Company -

Two North Ninth Street

• Allentown, PA 18101

• 215 / 770 5151 Bruce D. Kenyon .

Vice President-Nucleat Operations 215/770 7502 s

AUG 151983 Director, Data Automation &

Management Information Division Attention: Mr. M. R. Leebe Management Information Branch-Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORT - JULY 1983 ER 100450 FILE 841 PLA-1787 Docket No._ 50-387

Dear Mr. Beebe:

=

The July 1983 monthly operating report for Susquchanna SES Unit 1 is attached. '

This report includes information,on refueling.

Very truly yours,  :

I i

Wf B. D. Kenyon Vice President-Nuclear Operations 1 Attachment -

INPO Records Center cc: .Dr. Thomas E. Murley Suite 1500 .

Regional' Administrator-Region I 1100 Circle 75 Parkway U.S. Nuclear Regulatory Commission Atlanta, Georgia 30339 631 Park Avenue ,

King of Prussia, PA 19406 ,

Director Mr. Thomas E. Pollog ,

Office of Inspection and Enforcement Department of Environmental s 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. G. Rhoads - NRC '

Mr. R. Perch - NRC 8309000175 830eos PDR ADOCK 05000387 R

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- ANN 4 AVERAGE DAILY UNIT POWER LEVEL b

Cf) i E DOCKET NO. 50-387 1.... ,

L' '"% UNIT One O DATE 08-08-83

[g COMPLETED BY I..A. Kuczynski

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TELEPHONE (717)542-2181

- MOVili July. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 0 561 1 '37 2 75 18 574 3 630 19 556 4 847 20 588 5

544- 583

, 21 0 549 6 22 7 297 23 544 8 563 561 L -

24

! 9 622 25 756 10 652 26 743

11 428- 27 865 12

'155 874

, 23 13 _,

463 29 861

^~ 531 827

, 34 30 15 578 31 1022 16 491 j

INSTRUCTIONS On this format, list the avenge daily unit power level in MWe. Net for each day in the reporting month. Compute to i

12x marnt whole megawart.

l (9/77) i

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L I't L-- HIDM J OPERATING DATA REPORT EB

• DOCKET NO. 50-387 s

08-08-83

%(0.NICS 7 Tf DATE COMPLETED BY L. A. Kuczynski TELEPHONE (717)S42-2181 OPERATihG STATUS Unit 1 Notes

1. Unit Name: Susouchann, Stenn Electric station

2. Reporting Period: July. 1983

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gmss MWe): 1072

7. Maximum Dependable Capac!!y (Net MWe). 1016

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

None Approx. 85% from 7/25 to 7/29

9. Power Level To Which Restricted,If Any (Net MWe): Approx. 65% from 7/8 to 7/25

10. Reasons For Restrictions,If Any: V31untary power level restrictions in ef feet from July 8 through 29, 1983, due to problems with spiking to three times normal on the main steamline radiation mon.itors.

This Month Yr..to-Date Cumulative

11. Hours In Reporting Period 744 _ 1,296 _ 1.296 662 1,013.6 1,013.6

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0 156.7 156.7

14. Hours Generator On-Line 641 975.'l 975.3 0 0 0

15. Unit Reserve Shutdown Hours 1.402,028 2,452,028 2,452,028

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 434,450 776.210 776.210

18. Net Electrical Energy 6enerated (MWH) 415.082 744,992 744,992

19. Unit Service Factor 86.2 75.2 75.2

20. Unit Availability Factor 86.2_ 75.2 75.2

21. Unit Capacity Factor (Using MDC Net) 53.8 55.5 55.5

22. Unit Capacity Factor (Using DER Net) 52.4_ 54 54

23. Unit Forced Outage Rate 13.8 24.7 24.7

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

Unit 1/ Unit 2 Tie-in Outane te commente November 15. 1983. Scheduled to last 29 days. _

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

26. Units In Test Status (Prior to Commercial Operation). Forecast Achieved INiTIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77 )

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. p DOCKET NO. 50-387 L UNIT SHUTDOWNS AND POWER REDUCTIONS U UNIT NAME One kf G DATE 08-08-83 COMPLETED BY T.A. Kuczynski NIC M REPORT MONTH July _ 1981 TELEPHONE (717)S42-2181 e.

E E No. Date g

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,s5 Licensee Event E-r,

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Cause & Corrective Action to H

$ :_ 5 j di g Report a mO g' Prevent Recurrence a

13 062483 F 42.5 A 3 83-092/03L EA TRANSF A startup transformer failed in ser-vice. This caused a reactor scram and main turbine trip on RPV high level.

Present replacement transformer will be replaced with transformer having automatic load tap changing.

14 070583 F 39.2 11 3 NA HC DEMINX The scram was due to chemistry tran-sients associated with placing conden-sate demins.in service causing spikes it. main steam line radiation. ,

15 071183 F 21.3 11 3 NA IA CKTBRK The scram was caused by an incorrect fuse type installed in the power sup-ply to one of the scram valve pilot solenoid groups. The fuse was blown at the same time the I6C group was con-ducting surveillance testing which, by procedure, caused a half scram.

This combination of events resulted in (cont.)

I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A-Equipment Failure (Explain) I 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 (NURI G.

D-Regulatory Restriction 4-Ot her ( Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) Il-Other (E xplain)

(

e UNIT SHUTDOWNS AND POWER REDUCTIONS JULY, 1983 Cause & Corrective Action to Prevent Recurrence: (Continued) the insertion of one-quarter of all the control roda (48) . The resulting power decrease caused a rapid RPV level decrease which yielded a full scram.

A new procedure was issued that is expected to prevent recurrence.

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W SUSQUEHANNA STEAM ELECTRIC STATION

, Docket Number 50-387 Date 08-08-83 i Completed by L.A. Kuczynski Telephone (717)542-2181 Cua11enges to Main Steam Safety Relief Valves SRV's 'A' and 'B' were manually actuated for pressure control at 5 min, and 21 min, respectively, after the July 5 scram. SRV 'A' was opened for approximately 3.3 min; RPV pressure decreased from 1030 psig to 860 psig. SRV 'B' was opened for approximately 4.1 min.; RP pressure i decreased from 1050 psig to 860 psig. Both valves reseated properly.

Changes to the Offsite Dose Calculation Manual None.

i Major Changes to Radioactive Water Treatment Systems None.

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' DATE: 5/18/83 - -

• REFUELfNC INFORMATTON

1. Name of facility. Susquehanna SES - Unit 1

2. Scheduled date for next refueling shutdown. 9/1/84

3. Scheduled date for restart following refueling. 12/15/84

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?

Yes; first insertion of Exxon Nuclear Co. Fuel bundles, will require NRC review, may change tech specs for MCPR; must change T.S. for MAPLHGR (new ENC fuel bundle) 5

5. Scheduled date(s) for submitting proposed licensing action and supporting information, 9/1/84

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

New fuel supplier (same basic conceptual design - 8x8C. 2 unene vnd).

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 764 b) 0

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

present 2840 increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: 1997*

• based on 2840 - 1/2 X 764 = 2458 available capacity