PLA-1745, Monthly Operating Rept for June 1983

Monthly Operating Rept for June 1983

ML20077H623
Person / Time
Site:	Susquehanna
Issue date:	07/11/1983
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-1745, NUDOCS 8308110143
Download: ML20077H623 (7)

Text

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[ AVERAGE DAILY UNIT POWER LEVEL D I rf) .... 3 DOCKET NO. 50-387 Le 0"*

UNIT DATE duly 11, 1983

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g COMPLETED BY d..A. Kuzcynski TELEPHONE 1 717)S42-2181 MONTH Jun , 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1020 g7 638 2

1030 18 3 1046 39 903 4 1042 20 1017 5 1044 21 1036 6 1043 1042 22 7 987 23 1041

• g 1048 24 484 9 1053 25 0 10 1050 26 0 gg 1045 0 27 12 1041 0 28 13 1039 29 0 14 4I4 30 0 15 0 3g 16 0 INSTRUC110NS 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.

• Unit was declared commercial at 0001 on June 8,1983.

(9/77) l 8308110143 830711 l PDR ADOCK 05000 t R L

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OPERATING DATA REPORT l

0 DOCKET NO. 50-387 O 4s DATE July 11, 1983 COMPLETED BY L.A. Kuczynski NfC SY TELEPHONE (717)542-2181 ]

OPERATING STATUS Unit 1 Notes

1. Unit Name: Su saueh anna Steam Electric Station

2. Reporting Period: June, 1983

• Unit was declared commercia:.

3293 at 0001 on June 8, 1983

3. Licensed Thermal Fower (MWt):

1152

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe):

1072

7. Maximum Dependable Capacity (Net MWe). 1036

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

Items 6 and 7 will varv month-to-month until sufficient operating data has been gathered.

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 552 552 552

12. Number Of Hours Reactor Was Critical 351.6 351.6 351.6

13. Reactor Reserve Shutdown Haurs 156.7 156.7 156.7

14. Hours Generator On-Line 334.3 334,3 334.3

15. Unit Reserve Shutdown Hours 0- 0 0

16. Gross Thermal Energy Gener ated (MWH) 1,050,000 1,050,000 1,050,000

17. Gross Electrical Energy Gencated (MWH) 341,760 341,760 341,760

18. Net Electrical Energy Generated (MWH) 329,910 329,910 329,910

19. Unit Service Factor 60.6 60.6 60.6

20. Unit Availability Factor 60.6 60.6 60.6

21. Unit Capacity Factor (Using MDC Net) 57.7 57.7 57.7

22. Unit Capacity Factor (Using DER Net) 56.1 56.1 56.1

23. Unit Forced Outage Rate 39.4 39.4 39.4

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

Unit 1/ Unit 2 Tie-in Outage to Commence November 7,1983. Scheduled to last 29 days.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: 3 July 1983

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

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$ $A Q ' .

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• UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 '

kD E NIC S f[ REPORT MONTH June. 1983 UNIT NAME One COMPLETED BY DATE July 11. 1983 TELEPflONE (717)542-2181 L.A. Kuczynski

% B E 50 "E *Y3 Licensee En Eg Cause & Corrective No. Date h j$ $ 3g5 Event N hV Action to H

$= 5 j ;5 g Repor # mo g Prevent Recurrence 8

12 061483 F 61 A 3 N/A CC VALVEX Scram caused by a momentary three '

times normal main steam line radiation level. High rad. level caused by an air slug passed through the core.

The air slug originated from a conden-sate demineralizer which had its vent line blocked by some gasket-type mater ial which prevented proper venting.

Investigation into action to prevent recurrence is still under investigation 13 062483 F 156.7 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.

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 & Ucense Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

m SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date July 11, 1983 Completed by L.A. Kuczynski Telephone (717)542-2181 Challenges to Main Steam Safety Relief Valves Five minutes after the scram on June 15, 1983, reactor pressure reached 1080 psig and safety relief valve "E" automatically opened to relieve the pressure.

It reseated properly.

Changes to the Offsite Dose Calculation Manual See attachment.

Major Changes to Radioactive Water Treatment Systems None.

e w - ____- -_.

l ATTACHMENT TO June, 1983, Monthly Operating Report Changes to the Offsite Dose Calculation Manual O

t 1

1

These revised pages were made effective on April 27, 1983 upon signature by the Manager-Nuclear Support.

Changes have been denoted by revision bars in the right margin. The reasons for the changes are as follows:

To reflect the current text of the applicable Technical Specifications where they are quoted (Pages 7, 8, 9, 14, 15, 16, 21, 25, 26, 30, 32, 34, 39a, 40, 48) .

t To clarify the fact that dose rate calculations are performed monthly ,

as well as "when necessary" (vent monitor alarm) (Page 3).

To include applicable 10CFR20 dose rate standards in the table of radiological effluent objectives and standards (Page 6) .

To clarify the fact that Table 3 meteorological data is for sample purposes only. For dose calculations for the Semi-annual Radio-active Effluent Release Report, actual meteorological data from the report period is used (Pages 17, 18, 19, 25, 27).

To change the dose parameters for radionuclides other than noble gases via the ground plane pathway. The former values, which were based on total body dose factors for standing on contaminated ground, were less conservative than the current values, which are based on skin dose from standing on contaminated ground (Page 20) .

To include the statement that, when calculating doses to gauge com-pliance with Specification 3.11.2.5, the ventilation exhaust treatment system operability specification, only doses from I-131, tritium, and particulates with half-lifes greater than eight days shall be included. This is because, by definition in Tech. Spec. Definition 1.47, the ventilation exhaust treatment system is not considered to have any effect on noble gas effluents (Page 34) .

To add Appendix D, which presents site specific values used in the LADTAP II code to calculate doses from liquid effluents (Pages D-1, ,

D-2, D-3).

9

PPaL( Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 + 215 / 770-5151 i

Bruce D. Kenyon Vice President-Nuclear Operations ,

215/770-7502 l

July 14, 1983 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 SUSPUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORT - JUNE 1983 ER 100450 FILE 841 PLA-1745 Docket No. 50-387

Dear Mr. Beebe:

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

The Unit was declared commercial at 0001 on June 8, 1983.

Very truly yours, s

B. D. Kenyca

[ 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. '.homas E. Pollog I 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. G. Rhoads - NRC Mr. R. Perch - NRC llg