W3P85-3276, Monthly Operating Rept for Oct 1985
| ML20136D919 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 10/31/1985 |
| From: | Cook K, Geoffrey Miller LOUISIANA POWER & LIGHT CO. |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| W3P85-3276, NUDOCS 8511210390 | |
| Download: ML20136D919 (8) | |
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NRC MONTHLY OPERATING REPORT
SUMMARY
OF OPERATIONS WATERFORD 3 OCTOBER 1985
.The unit started the month at approximately 20% power and reached 100% power on October 1.
On October 2 at 912, at 100% power, a reactor trip occurred on low steam generator level resulting from a feedwater pump trip due to a failure in the feedwater control system. On October 2, at 1358, the reactor achieved criticality. On October 2 at 2035 a reactor trip occurred on high steam generator level. The unit remained shutdown to replace reactor coolant pump seals. On October 10 at 1330, the reactor achieved criticality and at 1637'a reactor trip occurred on high steam generator level. On October 10 at-1934 the reactor returned to criticality and at 2211 the generator was back on line.
I On October 28 at 1920, at 100% power, a reactor trip occurred resulting from an auxiliary high pressurizer pressure trip generated by the core protection calculators..This trip was a result of a steam leak which caused water from the fire protection deluge system to enter the feedwater pump control system catasing a feedwater pump trip. On October 29 at 1020, the reactor achieved criticality and on Octobe r 30 at 309, the generator was back on line. On October 31, the unit reached 100% power.
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PRESSURIZER SAFETY VALVE FAILURES AND CHALLENGES.
WATERFORD 3 I-During the month of October 1985, there were no pressurizer safety valve failures or challenges.
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g OPERATING DATA REPORT UNIT NAME: WATERFORD 3 CITY / STATE: KILLONA/LA DATE: NOVEMBER 1985 OPERATING STATUS
- 1. Docket: 50-382 Notes (1) Maximum Dependable
- 2. Reporting Period: OCTOBER 1985 Capacity-(Gross and Net MWe) will be
- 3. Utility
Contact:
GEORGE MILLER a b Phone Number:
(504) 467-8211
- 4. Licensed Thermal Power (MWt): 3390
- 5. Nameplate Rating (Gross Mwe): 1153
- 6. Design Electrical Rating (Net MWe): 1104
- 7. Maximum Dependable Capacity (Gross MWe): (Note 1)
- 8. Maximum Dependable Capacity (Net MWe): (Note 1)
- 9. If Changes Occur in Capacity Ratings (lcems 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 l
This Month Yr.-to-Date Cumulative
.12.
Hours In Reporting Period 745.0 5450.1
~5450.1 I
13.
Number Of Hours Reactor Was Critical 537.3 2189.4 2189.4 14.
Reactor Reserve Shutdown Hours -15 Hours Generator On-Line 508.2 1930.8 1930.8 16.
Unit Reserve Shutdown Hours l
OPERATING DATA REPORT (Continued)
This Month Yr.-to-Date Cumulative
- 17.. Gross Thermal Energy Generated (MWH) 1,581,557 4,447,788 4,447,788 18.-
Gross Electrical Energy Generated (MWH) 526,590 1,403,630 1,403,630
- 19. Net Electrical Energy Generated (MWH) 500,935 1,311,568 1,311,568
- 20. Unit Service Factor 68.2 35.4 35.4
- 21. Unit Availability Factor 68.2 35.4 35.4
.22.
Unit Capacity Factor (Using MDC Net)
(NOTE 1)
(NOTE 1)
(NOTE 1)
- 23. Unit Capacity Factor (Using DER Net) 60.9 21.8 21.8
.24.
Unit Forced Outage Rate 31.8 64.1 64.1
.25.
Unit Forced Outage Hours 236.8 3446.8 3446.8 l
26.
Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
Unit shutdown scheduled in March 1986 to perform Technical Specification surveillances requiring a unit shutdown, duration: approximately 28 days.
27.
If Shut Down At.End of Report Period, Estimated Date Of Startup:
- 28. Units In Test Status (Prior to Commercial Operation):
l Forecast Achieved r
INITIAL CRITICALITY 3/4/85 INITIAL ELECTRICITY
_,3/18/85 COMMERCIAL OPERATION 9/24/85
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t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-382 UNIT WATERFORD 3 DATE NOVEMBER 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 MONTH OCTOBER 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1-c '1 17 1087 2
408 18 1088 3 19 1089 4 20 1090 5 21 1088 6 22 1090 7 23 1092 8 24 1096 9 25 1093 10 9
26 1086 11
'418 27 1087 12 782 28 873 13 1045 29 14-1066 30 433 15 1090 31 979 16 1068 l
IFSTRUCTIONS
[
On this format list the average daily unit power level in MWe-Net for each l
day in the reporting month. Compute to the nearest whole megawatt.
1 (9/77) l-t
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR OCTOBER 1985 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE.
NOVEMBER 1985 COMPLETED BY GEORGE MILLER-TELEPHONE I 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.
Date Type (HOURS)
REASON 2 3
Down Reactor 3 d
Report #
Code Code 5 Prevent Recurrence 85-020 85 002 F 205.0 A
3 85-041 JB FT At 100% power, a reactor trip occured on low steam generator level resulting from a feedwater pump trip due to a failure in the feedwater control system. Unit resained shutdown to replace reactor coolant pump seals.
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 OCTOBER 1985 DOCKET NO 50-382 UNIT NAME WATERFORD 3 DATE NOVEMBER 1985 COMPLETED BY GEORGE MILLER TELEPHONE 504-467-8211 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to Ns.
Date Type (HOURS)
REASON 2 l
Down Reactor 3 Report #
Code 4 Code 5 Prevent Recurrence 85-021 851028 F 31.8 H
3 85-048 JK ZZZZ At 100% power, a reactor trip occurred resulting from an auxiliary high pressurizer pressure trip generated by the core protection calculators. This trip was a result of a steam leak which caused water from the fire protection deluge system ta enter the feedwater pump control system causing a feedwater pump trip.
I 2
3 F: Ecrced 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)
E LOUISIANA P O W E R & L 1 G H T! P O BOX 6008
- NEW OnLEANS. LOUISIANA 24a ouAnoNoe S1neer 70174 * (5041 366-2345 Eu?$sysE November 14, 1985 W3P85-3276 A4.05 QA Mr. Ronald M. Scroggins Controller and Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Lear Mr. Scroggins:
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 October 1985. This report is submitted per Section 6.9.1.6 of the Waterford 3 Technical Specifications for Facility Operating License No. NPF-38.
Very truly yours, K.W. Cook Nuclear Support & Licensing Manager KWC:GEW:sms Enclosure cc:
R.D. Martin, NRC Region IV NRC, Director, Of fice of 1&E C.W. Knighton, NRC-NRR NRC Resident Inspectors Office INPO Records Center (J.T. Wheelock)
B.W. Churchill W.M. Stevenson i s I
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