W3P85-1217, Monthly Operating Rept for Mar 1985

Monthly Operating Rept for Mar 1985

ML20115H408
Person / Time
Site:	Waterford
Issue date:	03/31/1985
From:	Cook K, Geoffrey Miller LOUISIANA POWER & LIGHT CO.
To:	Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
W3P85-1217, NUDOCS 8504230106
Download: ML20115H408 (11)

Text

r Shest 1 of 2 9

1 NRC MONTHLY OPERATING REPORT

SUMMARY

OF OPERATIONS WATERFORD 3 MARCH 1985 The unit achieved initial criticality and first electrical production during the month. The unit started the month in Mode 5.

On March 2, the unit reached hot zero power conditions and preparations for the approach to criticality were started. On March 4 at 2148, the unit ach.eved initial criticality (Mode 2).

Low Power Physics testing was conducted and was completed on March 10.

Prior to the receipt of the full power operating license, the schedule

. permitted the performance of several activities. On March 10 at 1126, a shutdown was commenced to perform testing to clear post core hot functional test deficiencies and to perform maintenance activities inside the reactor containment building. On March 14 and 15~, reactor startups and shutdowns were performed to satisfy operator training and license requirem'.nts. On March 15 at 417 following a manual reactor shutdown, control element assembly #46 dropped and could not be withdrawn. The unit remained in Mode 3 to perform repairs on the control element assenbly drive mechanism. Repairs were completed on March 15.

On March 16, the unit received a full power operating license. On March 17 at

' 844, in Mode 2 at 4.5% power, a reactor trip occurred on high water level in steam generator #2. At 1250 the unit returned to Mode 2.

On March 18 at 209, the unit reached Mode 1 for the first time. On March 18 at 2156, the unit achieved first electrical production.

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Sheet 2 of 2' NRC MONTHLY OPERATING REPORT

SUMMARY

'0F OPERATIONS WATERFORD 3 MARCH 1985 On March.19 at 1423 in Mode 1 at 15% power, a reactor trip occurred on high water level. in steam generator #1. On March 20 at 354,.the generator was back on line. On March 21 at 1834 in Mode 1 at 19.5% power, a reactor trip occurred son low water level in steam generator #1. -The event resulted from a main feedwater pump turbine trip due to a perturbation in condensate flow. The unit returned to Mode 1 on March 22 at 144. On March 22 at 303 in Mode 1 at 15%

power, a reactor trip occurred on low steam generator water level..This event

resulted from a main feedwater pump turbine trip due to high vibration. On

-March 22 at 822 the unit returned to Mode 2.

At 905, a manual reactor shutdown to Mode 3 was performed when it was noticed that the entry into Mode 2 was-made with one inoperable hydrogen monitor which violates the Technical Specifica--

-tions. "On March 23 at 647, the unit returned to Mode 2.

On March 24 at 811, the reactor was manually shutdown due to secondary system chemistry being out-of-specification. The unit was cooled down to Mode 5 on March 24 at 2359 to perform cleanup.

r on March 28 at 1825 the unit entered Mode 4 with the RCS at 200 F.

The unit ended the reporting period in this condition.

d L_u-

e F

s 4

l SPRING-LOADED PRESSURIZER SAFETY VALVE

' FAILURES AND CHALLENGES WATERFORD 3 f

. During the month of March 1985, there were no spring-loaded pressurizer

' safety valve failures or-challenges.

y-OPERATING DAPA REPORT V.

UNIT NAME:.WATERFORD 3 CITY / STATE: KILLONA/LA DATE:

APRIL 1985

-OPERATING STATUS

1. Docket: 50-382 Notes (1) Maximum Dependable Ca a ross and-

2. Reporting Period: MARCH 1985 determined after the 3.' Utility

Contact:

GEORGE MILLER 100% warranty run.

Phone Number:

(504) 467-8211 (2{

d tr h

first electrical

4. Licensed Thermal Power (MWt): 3390 production on 3/18/85 at 21:56.

5. Nameplate Rating (Gross Mwe): 1153 (3) Prior to first electrical production, e ] to ws

6. Design Electrical Rating (Net HWe): 1104 g

97.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Per NRC 7.= Maximum Dependable Capacity (Gross MWe): (Note 1) instructions, these hours are not included in item 13.

8. -Maximum Dependable ;.:apacity (Net MWe): (Note 1)

9. If Changes Occur in Capacity Ratings (Items Number 4 Throagh 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 (2) 314.1 314.1 314.1 13.

Number Of Hours Reactor Was Critical (3) 93.2 93.2 93.2

14. ' Reactor Reserve Shutdown Hours 15 Hours Generator On-Line 55.2 55.2 55.2 16.

Unit Reserve Shutdown Hours L.

OPERATING DATA REPORT (Continued)

This Month Yr.-to-Date Cumulative 17.

Gross Thermal Energy Generated-(MWH) 42,830.6 42,830.6 42,830.6

-18.

Gross Electrical Energy Generated (MWH)-

6,970.0 6,970.0 6,970.0

19. Net Electrical Energy Generated (MWH) 4,553.0 4,553.0 4,553.0

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

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

Unit. 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 82.4 82.4 82.4

25.. Unit Forced Outage Hours 258.9 258.9 258.9 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:

April 1, 1985-l ~

28.

Units-In Test Status (Prior to Commercial Operation):

E Forecast Achieved INITIAL CRITICALITY 3/4/85 INITIAL ELECTRICITY 3/18/85 COMMERCIAL OPERATION 6/85 i

L

-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-382 UNIT WATERFORD 3 DATE APRIL 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211

' MONTH MARCH 1985' DAY-

-AVERAGE DAILY POWER LEVEL

, DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 17 2 18 2

3 19 24 4 20 84 5 21 79 6 22 7 23 8 24 9 25 10 26 11' 27 12 28,

13 29 14-30 15 31 l 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)

\\.

~ UNIT SHUTDOWNS.AND POWER REDUCTIONS 4

REPORT FOR MARCH 1985 Sheet 1 of 4 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE APRIL 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee

.Cause & Corrective 1 Duration Shutting Event System Component

-Action to l

No.

Date Type (HOURS)

REASON 2 Down Reactor 3 Report #

Code 4 Codes Prevent Recurrence N/A 850220 F

42.6 A

N/A 85-006 AB SEAL.

Inadvertent contain-Total = 243.3 ment spray actuation resulted in a loss.

of component cooling water,and damage to reactor coolant pump seals. Unit-was.

cooled down to repair seals.

N/A 850308 S 2.1 B

2 N/A ZZ ZZZZ During low power-physics testing, reactor was manually tripped tu satisfy technical specification special test exception requirements.

I 2

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)

-3 UNIT-SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MARCH 1985 Sheet 2 of 4 DOCKET NO

'50-382 UNIT NAME WATERFORD 3 DATE APRIL 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to l

No.

Date Type (HOURS)

REASON 2 Down Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence N/A 850310 S 137.0 B, E 2

N/A ZZ ZZZZ Prior to receipt of.

full power license, unit was shut down to perform testing and to perform reactor startups and shutdowns to satisfy operator training.

. requirements and to repair a control element assembly drive mechanism.

I 2

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS i

REPORT FOR MARCH 1985 Sheet 3 of 4 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE APRIL 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 #

Code 4 Code 5 Prevent Recurrence N/A 850317 F 5.1 G

3 85-008 ZZ ZZZZ At 4.5% power, the reactor tripped on high water level in steam generator #2 while levels were being manually controlled.85-001 850319 F

13.5 G

3 85-008 ZZ ZZZZ At 15% power, the reactor tripped on high water level in steam generator

1. 1 while controlling levels manually.

I 2

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR MARCH 1985 Sheet 4 of 4 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE APRIL 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to l

No.

Date Type (HOURS)

REASON 2 Down Reactor 3 Report #

Code 4 Code 5 Prevent Recurrence 85-002 850321 F 245.4 H

3 85-010 ZZ ZZZZ At 19.5% power, the reactor tripped on low steam generator water level. The event resulted from a main feedwater pump turbine trip due to aperturbation in condensate flow caused by transfer of the condensate polisher system aggravated by a clogged strainer in the condensate system.

I 2

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)

Louisiama / 44 0.-

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30WER & L1GHT /

N.W CAL.ANS LoueANA 70174-6000 9 (504)365-2345 MIODLE SCUTH S SYSW April 15, 1985 W3P85-1217 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 MONTHLY OPERATING REPORT Enclosed is the subject monthly report which covers the operating statistics for the month of March 1985. This report is submitted per Section 6.9.1.6 of the Waterford 3 Technical Specifications for Facility Operating License No. NPF-38 which was issued on March 16, 1985.

Very truly yours, D

K.W. Cook Nuclear Support & Licensing Manager KWC:GEW:sms 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)

E.L. Blake fh&2, W.M. Stevenson t

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