W3P85-1410, Monthly Operating Rept for May 1985

Monthly Operating Rept for May 1985

ML20127B311
Person / Time
Site:	Waterford
Issue date:	05/31/1985
From:	Drummond F, Geoffrey Miller LOUISIANA POWER & LIGHT CO.
To:	Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
W3P85-1410, NUDOCS 8506210417
Download: ML20127B311 (11)

Text

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Sheet I of 2

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, s NRC MONTHLY OPEIDTING REPORT 4

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SUMMARY

OF OPERATIONS WATERFORD 3

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MAY 1985

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e Power ascension testing continued during the'mo' nth -as-the unit achieved'80%

power. The unit started the month at 50% power. On May 2 a power redaction to 20% was initiated in preparatgon for the remote shutdown test.

On May 2 at 1110, at 20% power, the reactor was manually tripped to test remote shutdown j

capability. On May 4 at 0450, the generator was back on line. On*May 5 at 0007, at 17% powee, a reactor trip occu~rred on' low departure from nucleate boiling ratio due to inadvertent closure of a main steam isolation valve. On i,

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May 5 at 1707, the generator was back on line. On May 6, a power increase from 50% power to 80% power was started. On May 7, the unit achieved 80% power.

s On May 11 at 0945, at 65% power, a shutdown was commenced due to reactor coolant systein leakage greater than one gallon per minute. At 1530, the generator wiis aken off line. At 1543 at 0.8% power, a reactor trip occurred on high stean generator level. The cause of.the reactor coolant system leakage was identified as packing leaks on the pres"surizer spray valves. The unit remained shut down to perform repairs. On May 18 at 1212, the generator was back on line. On May 18 at 1808", at 25% power, a^ reactor trip occurred on low steam generator level due to a,'feedwater pump trip.'

On May 19 at 1125, the generator was back on line. On'May 23 at 2039, at 65% power, a reactor trip occurred on low steam generator level due to a feedwater pump trip. On May 24 at 1433, at 11% power, a reactor trip occurred on high steam generator level due to a malfunction of a steam bypass control valve. On May 24 at 1927, the generator was back on line. On May 28 at 1245, at 80% power, a reactor trip occurred on low departure from nucleate boiling ratio due to manually tripping the reactor cooling pumps as a part of.'the loss of reactor coolant flow test.

On May 29 et 0450', the generator was' back on line.

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Sheet 2 of 2 On May 29 at 0631, at 20% power, a reactor trip on low reactor coolant flow

. occurred due to manually tripping the turbine as a part of the loss of offsite power test.

On May 31 at-0655, the reactor was returned to critical. On May 31 at 1650, the unit was shut down to remove lead carbonate deposits found in the electrical generator. The unit remained in this condition through the l

1 end of the month.

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SPRING-LOADED PRESSURIZER SAFETY VALVE FAILURES AND CHALLENGES WATERFORD 3 During the month of May 1985, there were no spring-loaded pressurizer safety valve failures or challenges.

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OPERATING DATA REPORT UNIT NAME: WATERFORD 3 CITY / STATE: KILLONA/LA DATE:

JUNE 1985 OPERATING STATUS

1. Docket: 50-382 Notes (1) Maximun Dependable

2. Reporting Period: MAY 1985 Capacity (Gross and Net MWe) will be determined after the

3. Utility

Contact:

GEORGE MILLER 100% warranty run.

Phone Number:

(504) 467-8211

4. Licensed Thermal Power (MWt): 3390

5. Nameplate Rating (Gross Mwe): 1153

6. Design Electrical Rating (Net NWe): 1104

7. Maximum Dependable Capacity (Gross MWe): (Note 1)

8. Maximum Dependable Capacity (Net MWe): (Note 1)

9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:

N/A 10.

Power Level To Which Restricted, if Any (Net MWe):

NONE 11.

Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative 12.

Hours In Reporting Period 744.0 1777.1 1777.1 13.

Number Of Hours Reactor Was Critical 440.4 1045.8 1045.8 14.

Reactor Reserve Shutdown Hours 15 Hours Generator On-Line 384.0 918.1 918.1 16.

Unit Reserve Shutdown Hours

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OPERATING DATA REPORT (Continued)

This Month Yr.-to-Date Cumulative 17.

Gross Thermal Energy Generated (MWH) 809,488.3 1,465,992.0 1,465,992.0 18.

Gross Electrical Energy Generated (MWH) 248,310.0 430,790.0 430,790.0 19.

Net Electrical Energy Generated (MWH) 230,369.0 389,747.0 389,747.0 20.

Unit Service Factor N/A N/A N/A 21.

Unit Availability Factor N/A N/A N/A 22.

Uni r.

Capacity Factor (Using MDC Net)

N/A N/A N/A

23.. Unit Capacity Factor (Using DER Net)

N/A N/A N/A 24.

Unit Forced Outage Rate-33.6 44.2 44.2 25..

Unit Forced Outage Hours 287.3 786.3 786.3 26.

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

N/A 27.

If Shut Down At End of Report Period, Estimated Date of Startup:

06/20/85 28.

Units In Test Status (Prior to Commercial Operation):

1 Forecast Achieved i

INITIAL CRITICALITY 3/4/85 INITIAL ELECTRICITY 3/18/85 COMMERCIAL OPERATION 6/85

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-382 UNIT WATERFORD 3 DATE JUNE 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 MONTH MAY 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 500 17 2 166 18 16 3 19 96 4

16 20 469 5

83 21 444 6

527 22 510 7

739 23 490 8

846 24 43 9

841 25 617 10 819 26 792 11 386 27 772 12 28 416 13 29 7

14 30 15 31 16 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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UNIT SHITTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1985 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE JUNE 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to t

No.

Date Type (HOURS)

REASON 2 Down Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence 85-005 850502 S 56.6 B

2 N/A ZZ ZZZZ At 20% power, the reactor was manually tripped to test remote shutdown capability.85-006 850505 F 17.0 A

3 85-017 SB ISV At 17% power, a reactor trip occurred on low departure from nucleate boiling ratio due to inadvertent closure of a main steam isolation valve.

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3 F: Forced Reason:

Method S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation 4

E-Operator Training &

5-Load Reduction IEEE Std. 805-1984 License Examination 9-Other 5

F-Administrative IEEE Std. 803A-1983 G-Operational Error (Explain)

H-Other (Explain)

s UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1985 DOCKET NO 50-382 UNIT NAME

. WATERFORD 3 DATE JUNE 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.

Date Type (HOURS)

REASON 2 Down Reactor 3 l

Report #

Codei Code 5 Prevent Recurrence 85-007 850511 F

164.7 A

1 85-018 AB V

At 65% power, a shut-down was commenced due to reactor coolant system leakage greater than one gallon per minute.85-008 850518 F

17.3 H

3 85-020 ZZ ZZZZ At 25% power, a reactor trip occurred on low steam generator level due to a feedwater pump trip.85-009 850523 F

22.8 H

3 85-021 ZZ ZZZZ At 65% power, a reactor trip occurred on low steam generator level due to a feedwater pump trip.

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3 F: Forced Reason:

Method S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

C-Refueling 3-Automatic Scrah.

D-Regulatory Restriction 4-Continuation 4

E-Operator Training &

5-Load Reduction IEEE Std. 805-1984 License Examination 9-Other 5

F-Administrativd IEEE Std. 803A-1983 G-Operational Error (Explain)

H-Other (Explain)

6 UNIT SHirTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1985 DOCKET NO

'50-382 UNIT NAME

.WATERFORD 3 DATE JUNE 1985 l

COMPLETED BY GEORGE NILLER i

TELEPHONE 504-467-8211 i

Method of Licensee Cause & Corrective j

Duration Shutting Event System Component' Action to 1

No.

Date Type (HOURS)

REASON 2 Down Reactor 3 t

Report #

Code

• Code 5 Prevent Recurrence i 010 850528 S

16.1 B

3 N/A ZZ ZZZZ.

At 80% power, a reactor j

trip occurred on low l

departure from nucleare' boiling ratio due to

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manually tripping the I

reactor coolant pumps as a part of the loss

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of reactor coolant flow 3

test.

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1 2

3 1l F: Forced Reason:

Method I

l S: Scheduled A-Equipment Failure (Explain) 1-Manual l

B-Maintenance or Test 2-Manual Scram.

• j C-Refueling 3-Automatic Scram.

I D-Regulatory Restriction 4-Continuation 4

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E-Operator Training &

5-Load Reduction IEEE Std. 805-1984 l

License Examinat. ion 9-Other 5

F-Administrative IEEE Std. 803A-1983 G-Operational Error (Explain) j H-Other (Explain) l I

IRIIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MAY 1985 DOCKET NO 50-382 UNIT NAPE WATERFORD 3 DATE JUNE 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.

Date Type (HOURS)

REASON 2 Cewn Reactor 8 l

Report #

Code

• Code 5 Prevent Recurrence 85-011 850529 S,F 65.5 B,A 3

N/A ZZ ZZZZ At 20% power, a reactor trip on low reactor coolant flow occurred due to manually trip-ping the turbine as a part of the loss of offsite power test.

The unit was later shut down to remove lead carbonate deposits found in the electrical generator.

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3 F: Forced Reason:

Method S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation 4

E-Operator Training &

5-Load Reduction IEEE Std. 805-1984 Yicent.c Examination 9-Other 5

F-Administrative IEEE Std. 803A-1983 G-Operational Error (Explain)

H-Other (Explain)

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LOUISIANA P O W E R & L 1 G H T ! New cateANs touSANA 4 4= o-o~os r-er.

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70174-4,00e 9 (504) 3ee-e345

$uS$0YS EM June 13, 1985 W3P85-1410 A4.05 Mr. Learned W. Barry Director and Controller Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 MONTilLY OPERATING REPORT Enclosed is the subject monthly report which covers the operating statistics for the month of May 1985. This report is submitted per Section 6.9.1.6 pf the Waterford 3 Technical Specifications for Facility Operating License No NPF-38.

Very truly yours, M "*1 F. J. Drummond Nucicar Services Manager FJD:GEW nms Enclosure cc R.D. Martin, NRC Region IV NRC, Director, Office of IAE G.W. Knighton, NRC-NRR D.M. Crutchfield, NRC-NRR NRC Resident Inspectors Office INPO Records Center (J.T. Wheelock)

B.W. Churchill W.H. Stevenson i I

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