PLA-2122, Monthly Operating Rept for Feb 1984

Monthly Operating Rept for Feb 1984

ML20087M661
Person / Time
Site:	Susquehanna
Issue date:	02/29/1984
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2122, NUDOCS 8403300147
Download: ML20087M661 (6)

Text

'.

f M AVERAGE DAILY UNIT POWER LEVEL

.3 ( ] Y tt)  ;...., 3 DOCKET NO.

50-387 L

' "% UNIT One 0 3-9-84

<p DATE L.A. Kuczynski RIC gT COMPLEED BY TELEPHONE (717)542-3759 MONDI Februarv, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe. Net) 1 0 g7 0 2 0 ,3 0 3

0 g9 0 4 0 0 20 5 0 0 21 6

0 99 22 7 0 125 23 8 0 550 24 0

9 25 415 IO O 0 26 11 0 0 27 12 0 13

-- 28 13 0 485 29 14 0 -

30 0

15 3, 16 0 i

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.

T (9/77)

C.

8403300147 840229 f7 '

PDR ADOCK 05000387 R PDR

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}- \Y (J) f L f' i M kj OPERATING DATA REPORT DOCKET NO. 50-387 O DATE 3-9-84 blC SY COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-3759 OPERATING STATUS '

Unit ' ,

Notes

1. Unit Name: Suscuehanna Steam Electric Station l

2. Reporting Period: February, 1984

3. Licenseo 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 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 696 1,440 6.409

12. Number Of Hours Reactor Was Critical 159.9 159.9 4,005.2

13. Reactor Reserve Shutdown Hours 0 0 156.7

14. Hours Generator On-Line 98.2 98.2 3,866.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 163.201 163,201 11,415,019

17. Gross Electrical Energy Generated (MWH) 43,470 43,470 3,710,020

18. Net Electrical Energy Generated (MWH) 40,180 40,180 3,576,553

19. Unit Service Factor 14.1 6.8 60.3

20. Unit Availabihty Factor 14.1 6.8 60.3

21. Unit Capacity Factor (Using MDC Net) 5.6 2.7 54.1

22. Unit Cepacity Factor (Using DER Net) 5.4 2.6 52.4

23. Unit Forced Outage Rate 43.0 43.0 13.1

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

None l

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 1

INITIAL CRITICALITY INITIAL ELECTRICITY 1 COMMERCIAL OPERATION t

1 (9/77) l l

gANN4 "

a j'4@lh$

9 sw DOCKET NO. 50-387 UNIT SHUTDOWNS AND POWER REDUCTIONS PP*L g UNIT NAME One (D o DATE 3-9-84 6 COMPLETED BY L.A. Kuczynski NIC S REPORT MONTil February, 1984 TELEPHONE (717)542-3759 m

- E c No. Date o.

.E. E 3g

}g }Y5

,c g 5 Licensee Event E t, {% Cause & Corrective Action to g'i?

F fE 5 jgg Report # mO g{ Prevent Recurrence d

(1983) 20 831203 S 511.5 H 2 NA ZZ ZZZZZZ Manual scram from 33% reactor power to cminence Unit 1-Unit 2 Tie-in Outage. No action required to prevent recurrence; this was a scheduled event.

(1984)

N " "

1 840225 F 74.1 A 2 84-010 SF VALVOP Manual scram frcm 54% power due to a safety relief valve (SRV) failure to close during testing. Unit responded to scram as designed. One SRV solenoid valve was replaced, successfully re-tested and the system returned to ser-vice.

NOTE: Generator removec from gr id foc 12.2 Irs. on Feb. 2 2-23, J 984, due t o generator 'C' phase output discon-nect breaker switch imprcper closure :ausing breake r overl eating. 9his does not qualify as either a unit shut-down (reactcr remaired av tilable throughout the event ) or powe2 reduction (greater than 20% reduction in avg. ' daily pc5 er leveJ for Jreceed i_ng 24 hr.).

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 ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E4)perator Training & Ucense Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) II-Other (Explain)

t SUSQUEHANNA STEAM ELECIRIC STATION s

Docket Ntrober 50-387 Date 3-9-84 Cm pleted by L.A. Kuczynski Telephone (717)S42-2181 Challenges to Main Stean Safety Relief Valves.

None, however, during testing performed February 25, 1984, SRV 'M' stuck open due to a faulty solenoid valve. '1he unit had been operating at approximately 54% power with steam done pressure at 946 psig. '1he reactor was manually

- sw.cmued when the stuck open valve was unable to be closed within 2 minutes, which is a provision of Technical Specification 3.4.2 action (b) . 'Ihe faulty solenoid was replaced, and the SRV successfully re-tested. ,

1 dianges to the Offsite Dose Calculation Manual.

None.

Major Changes to Radioactive Waste' Treatment Systems.

None.

Diesel-Generator Unit Failures.

Air Start Valve Stuck Open'"C" Diesel Generator Following shutdown of the "C" Diesel, it was discovered that the ~ Diesel Air Receiver could not be repressurized due to an air ' start valve _ stuck.in the open position. '1he valve was disasserbled; the valves ' piston was found stuck in -

the open position due to rust'in the piston ' area. '1he valve'was cleaned, tested and the diesel was returned to service approximately 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> following .

the failure.-

'1he test was classified as non valid-in accordance with Regulatory Guide 1.108 in that the diesel start was terminated intentionally _without loading.

"A" Diesel Generator Slow Acceleration '- P200 Testing While performing the " Unit 2_ Cold Functional Test" P200 during the Unit:2.

LTie-in Outage, Diesel Generator A' failed. to accelerate to 600 rpn in less

~

~

than 10 seconds following receipt of a start signal. . Investigations revealed' that the slow start was'due to theLincorrect wiring of the generator field = -

flash unit fran the Unitf 2 power. supply.- Similar' wiring.'on the remaining diesel generators: (B,C,D,) was verified to be: correct. . Diesel Generator _'A's

Lgenerator field flash unit wiring frcm the' Unit 2 power supply was rewired-

-' 1he diesel was returned to, service for P200 testingLin awmaimately eight-hours. Unit 1wasshutdownforthetie-inoutagelwithUnit2whentheevent

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occurred. " '

_____.._Ja__e -__ ' '__b'__m,

The test was classified as non valid in accordance with Regulatory Guide 1.108 in that the Diesel Start was terminated intentionally without loading.

'D' Diesel Generator Breaker Failed to Open Following P200 " Unit 2 Cold Functional" testing, breaker 1A20404 failed to open causing the 'D' Diesel Generator to be connected to the 4KV bus while it was energized by the off site power source. The breaker had to be opened locally and racked out in order to secure the diesel. Investigation revealed that the breaker's failure was attributed to a contact in the truck operated cell (TOC) switch which remained open with the breaker racked into the operate position. The 1A20404 TOC switch contacts were re-aligned such that the con-tacts close when the breaker is fully racked in. All other Unit 1 4KV breakers were inspected; no similar mis-alignments were found. Both the 'D' Diesel and its generator were inspected for damage. The 'D' Diesel Generator was run loaded and proper operation was verified approximately six hours following the event.

The test was classified as non-valid in accordance with Regulatory Guide 1.108.

'C' Diesel Generator Trip on Over-Excitation Durig the performance of surveillance testing , Diesel Generator 'C' tripped due to a generator over excitation alarm / trip. The cause of the trip was determined to be related to Startup Transformer Tap changes that increased plant voltage during the test. A followup diesel surveillance test was con-ducted after the trip; the test was classified as non-valid in accordance with Regulatory Guide 1.108, Section c.2.e. (2) in that the trip was caused by a condition bypassed durig emergency operation. The diesel was returned to service in two and a half hours following the trip.

'C' DieselTurboCharger Thrust Bearing Failure During the performance of Surveillance test procedure S0-224-002 " Eighteen Month Diesel Generator Auto Start and ESS Bus Energization on Loss of Off-site Power-Plant Shutdown", Diesel Generator 'C' tripped due to a turbo charger thrust bearing trouble alarm / trip. The cause of the trip was determined I to be excessive wear on the turbo charger thrust bearing that may be attri- l butable to a low turbo charger inlet pressure. Investigations are continuing to determine the cause of the low inlet pressure. The. thrust bearing was replaced and the 'C' Deisel returned to service in approximately sixty-eight hours.

The test was classified as non-valid in accordance with Regulatory Guide 1.108, Section c.2.e(2) in that the trip was caused by a condition bypassed during mergency operation.

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

• Allentown, PA 18101 + 215 / 77G5151 Bruce D. Kenyon Vice President-Nuclear Opcrations 215/770-7502 MAR 131984 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 REPORT - FEBRUARY 1984 ER 100450 FILE 841 PLA-2122 Docket No. 50-387

Dear Mr. Beebe:

The February 1984 monthly operating report for Susquehanna SES Unit 1 is attached.

Very truly yours, 1

7 w B. D. Kenyon 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. 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 Q Mr. R. L. Perch - NRC .s* T

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