ML20106J315

Monthly Operating Rept for Jan 1985

ML20106J315
Person / Time
Site:	Salem
Issue date:	01/31/1985
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8502150581
Download: ML20106J315 (11)

Text

P" AVEPAGE DA"ILY NNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date Feb. 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month January 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 7 17 1105 2 838 18 1080 3 1088 19 1096 4 1100 20 1102 5 1086 21 1093 6 1047 22 1087 7 1101 23 1110 8 1104 24 1112 9 1075 25 1110 10 1052 26 1098 11 1097 27 1094 12 1110 28 1110 13 1092 29 1108 14 1102 30 1110 15 1103 31 1104 16 1099 P. 8,1-7 R1 DOhh0f0h0hfp eDe /l I

OPERATING DATA REPORT '

Docket No.50-272-Date -Feb. 10, 1985-Telephone- 935-6000 Completed by J. P. Ronafalvy' Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes

2. Reporting Period .

January 1985:

3. Licensed Thermal- Power -(MWt) 3338 4.. Nameplate Rating . (Gross MWe) 1170*

- 5. ' Design Electrical Rating (Net MWe) - T690

6. Maximum- Dependable Capacity (Gross MWe)1124

7. Maximum Dependable Capacity (Net MWe) 1079

8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason

• Previous value reported was the turbine rating, not the generator rating as required.

9. Power Level to Which Restricted, if any (Net MWe) N/A

10. Reasons-for Restrictions, if any N/A

.This Month: Year to Date Cumulative

11. Hours in Reporting Period 744 744 66553

12. No. of Hrs. Reactor was Critical 726.6 726.6 36559.1 ,

13. Reactor Reserve Shutdown Hrs. 0 0- 3088.4 l 14. Hours Generator On-Line 723.7 723.7 34882.3

15. Unit Reserve Shutdown Hours 0 0 0-

16. Gross Thermal Energy. Generated (MWU) .

2382022 2382022 105150019

17. Gross Elec. Energy Generated (MTRI) 815390 815390 34731440 l 18. Net Elec. Energy Generated (MWH) 782864- 782864- __32880846 l 19. Unit Service Factor 97.3 97.3 52.4

20. Unit Availability Factor 97.3 97.3 52.4

21. Unit Capacity Factor (using MDC Net) 97.5 97.5 45.8 i

22. Unit. Capacity Factor

. (using DER Net) 96.5 96.5 45.3 i 23. Unit Forced Outage Rate 2.7 2.7 32.8

24. Shutdowns scheduled over next 6 months (type, date and duration of each) l N/A

25. If shutdown at end of Rep, ort Period, Estimated Date of Startup:

N/A'

26. Units in Test Status (Prior to Commercial Operation) : ..

Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity-. 11/1/76 12/25/76-Commercial Operation 12/20/76 4/30/77 8-1-7.R2 Page of

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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH Janunry 1985 Unit N m3 Salem No.1 Date Feb. 10,1985 Completed by J.P. Ronafalvy Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Rea cto r Report Code 4 Code 5 Prevent Recurrence Feedwater Regulating Boiler Level 85-010 1-01 F 20.3 A 3 -

HH VALVEX Control Valve 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source l C-Refueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) l

y i MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272'

. REPORT MONTH ~ January 1985 UNIT NAME: Salem 1 DATE: February 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455 , ,

• DC R NO . - PRINCIPLE SYSTEM SUBJECT 1

lEC-1417 Over/Under Voltage Remove over/under voltage . l Check check restrictions on breaker 11X, 21X, and 31X closing /reclosing-control.

1

.i 1EC-1747 Eydrogen & Seal Oil Add liquid level sensor with alarm to indicate high water level in moisture separator 4 located in discharge from loop

seal drain vapor extractor..

4 1ET-1940 4KV Power System Test the 4KV U.V. transfer scheme on the 1B Vital Bus.

1EC-1990 Auxiliary Feedwater Change relay setting for #11 and #12 Aux.fFeed Pump motors.

l 1SC-0419 Service Water Revise motor service water cooling' piping to the service water pump motor coolers which

will allow quick removal and restoration of piping hangers and associated piping during j motor change out.

1SC-1341 Service Water Replace the ladders located Structure between the Service Water Pump inlets and rotating screens.

New ladders should-be made of I

non-corrosive material.

.J

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH JANUARY 1985 UNIT NAME: Salem 1 DATE: February 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DC R NO. SAFETY EVALUATION 10 CFR 50.59 1EC-1417 The temporary jumpers across the overvoltage relay contacts on the 500 KV line do not affect the performance of any safety related equipment. No unreviewed safety or environmental questions are involved.

lEC-17 47 The addition of a level detector on the moisture separator located in the discharge from the loop seal drain vapor extrator of the Hydrogen Seal Oil System will not affect the function or operation of the system or any safety related equipment. No unreviewed safety or environmental questions are involved.

1ET-1940 This DCR is only a test of the 4160 Vital Bus U. V.

transfer scheme in order to obtain necessary data for the protective relay evaluation. No unreviewed safety or environmental questions are involved.

1EC-1990 This DCR only involves a relay setpoint change. No unreviewed safety or environmental questions are involved.

I SC-0419 No basic arrangement, function or operating component has been changed per this DCR. Only the cooling water hard piping to the pump motor coolers has been modified to allow for easier change-out of the pump motors. The flex hose used is supplied in accordance with quality assurance requirements of 10CFR50, including seismic testing. No unreviewed safety or environmental questions are involved.

ISC-1341 This DCR replaces carbon steel ladders with stainless steel ladders. Failure of the anchorage units or the ladder assemblies will not affect any system associated with the safe shutdown of either reactor. No unreviewed safety or environmental questions are involved.

• DCR - Design Change Request Ab

i PSE&G SALEM GENERATING STATION ,

1 SAFETY RELATED. WORK ORDER LOG-SALEM UNIT 1

• WO NO DEPT UNIT EQUIPMENT IDENTIFICATION

85-01-12-104-3 SMD 1 NO. 11 BORIC ACID TRANSFER PUMP FAILURE DESCRIPTION: BAD SEAL LEAK 4

CORRECTIVE ACTION: REPLACED SEAL a

0099120712 SMD 1 1CV346 (CHARGING LINE DRAIN VALVE)

FAILURE DESCRIPTION: VALVE IS: LEAKING t CORRECTIVE ACTION: CUT DRAIN. SIDE OF VALVE AND INSTALLED A PIPE CAP:

OVER THE LINES (PER DR #MD84-3352) 84-11-09-054-6 SMD 1 VALVE 1CV144 l FAILURE DESCRIPTION: VALVE LEAKS I CORRECTIVE ACTION: INSTALLED NEW BONNET ASSEMBLY WITH HANDWHEEL, STEM AND GASKET-009911930-7 1 VITAL HEAT TRACE HEATER #208 FAILURE DESCRIPTION: HEATER NOT MAINTAINING, TEMPERATURE.

CORRECTIVE ACTION: REPLACED HEAT TAPE;~ INSULATED 85-01-059-2

. SMD 1 16 SW PUMP STRAINER FAILURE DESCRIPTION: SHEAR PIN BROKEN CORRECTIVE ACTION: REPLACED SHEAR KEY AND FILTER ELEMENTS 4

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SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099104377 SMD 1 NO. 12 B. U. GROUP - PRESSURIZER HEATERS FAILURE DESCRIPTION: SEVEN OF THE FOURTEEN ACB'S WILL NOT RESET OR THEY-TRIP OUT FREQUENTLY CORRECTIVE ACTION: REPLACED TWO OF THE ITE CIRCUIT BREAKERS AND RESET THE OTHERS 0099104385 SMD 1 NO. 11 BAT PUMP FAILURE DESCRIPTION: LEAKING WATER EXCESSIVELY THROUGH SEALS CORRECTIVE ACTION: REPLACED PUMP .

0099125307 SMD 1 VALVE IVC 5 .

FAILURE DESCRIPTION: VALVE WON'T CLOSE FROM CONTROL ROOM BEZEL CORRECTIVE ACTION: REPLACED SOLENOID VALVE 0099124319 SIC 1 R41 A FAILURE DESCRIPTION: THE.HI/LO FLOW ALARMS UP CORRECTIVE ACTION: REPLACED THE APD PUMP 0099123746 SIC 1 1R41C FAILURE DESCRIPTION: CHANNEL PEGGING HIGH CORRECTIVE ACTION: INSTALLED'NEW PINS IN "J" CONNECTORS FOR THE CONTROLLER'AND SCALER

SALEM UNIT l WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-09-12-015-1 SIC 1 MAIN STEAM LINE MONITOR

- FAILURE DESCRIPTION: CHANNEL SPIKING CORRECTIVE ACTION: REPAIRED DRAWER AND DRIED OUT THE DETECTOR CONNECTORS, AND CABLES 84-12-30-015-7 SMD 1 10 4 PANEL FAILURE DESCRIPTION: POWER LOSS TO THE ALARMS 1

CORRECTIVE ACTION: AUDIBLE HORN REPLACED 84-12-24-009-0 SMD 1 INCORE SYSTEM FAILURE DESCRIPTION: DETECTORS A AND F ARE DRIFTING EXCESSIVELY CORRECTIVE ACTION: REPLACED A AND F CABLES 0099118777 SMD 1 1RC30 FAILURE DESCRIPTION: BORIC ACID PACKING LEAK CORRECTIVE ACTION: VALVE WAS FURMANITED 4

SALEM. GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 JANUARY 1985 S ALEM NO. 1 The period began with the Unit power increasing to full power.

Monitoring of the Electro-Hydraulic Control (EHC) System was continuing. On 12/31/84 at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br />, the Unit tripped due to No. 11 Steam Generator Steam Flow / Feed Flow mismatch combined with Steam

. Generator Low Level. This mismatch was a result of partial closure of No. 11 Steam Generator'Feedwater Control valve llBF19 caused by a malfunctioning solenoid. Following replacement of the solenoid, the Unit was returned to service on 1/1/85 at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br />. Full power operation was achieved on 1/2/85 and continued for the remainder of the period. On 1/11/85, the additional monitoring of the Electro-Hydraulic Control (EHC) System, instituted af ter the reactor.

trips of 11/06/84 and 11/11/84, was discontinued. No abnormal readings were identified during the entire monitoring period that could have caused the two (2) reactor trips associated with the EHC-System. It has been assumed that the cards replaced, after the trips, contributed to the cause of the reactor trips. No significant freeze-problems have occurred during the current extreme cold weather conditions.

1 l

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.. o REFUELING'INFORMATION DOCKET NO. : 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: . February-10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month January 1985

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next' refueling: Febru'ary 22,- 1986

3. Scheduled date for restart following refueling: May-4,1986 i

4. A) Will Technical Specification changes or other license 4 ' amendments be required?-

YES NO NOT DETERMINED TO DATE 10/1/84 B) Has the reload fuel design been reviewed by the' Station Operating Review Committee?

i YES NO X j If no, when is it scheduled? January 1986

5. Scheduled date(s) for submitting proposed licensing action:

January 1986 if required J 6. Important licensing considerations associated with refueling:

NONE 4

7. Number of Fuel Assemblies:

1 A) Incore 193 B) In Spent Fuel Storage 296

8. Present licensed spent fuel storage capacity:- 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged '

to spent fuel pool assuming the present licensed. capacity: September 2001 l

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- Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 10, 1985 Director,. Office of Inspection and Enforcement U.S. Nuclear _ Regulatory Commission.

Washington,' DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of January 1985 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, 6 4d J . M .' Zupko, Jr.

General Manager - Salem Operations JR:sbh cc: Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control

-U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page of 8-1-7.R4 s

i l The Energy People anm av.o ne,