ML20211Q131

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Monthly Operating Rept for Nov 1986
ML20211Q131
Person / Time
Site: Salem 
Issue date: 11/30/1986
From: Miller L, White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8612190205
Download: ML20211Q131 (12)
v • d • e


Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name

" Salem # 1 Date December 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month November 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1127 17 1132 2

1128 18 1130 3

1118 19 1131 4

1137 20 1130 5

1130 21 1135 6

1122 22 1115 7

1135 23 1087 8

1128 24 1131 9

1127 25 1126 10 1149 26 1095 11 1119 27 1139 12 1137 28 1113 13 1130 29 1137 14 1097 30 1109 15 1108 31 16 1122 P. 8.1-7 R1 l

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OPERATING DATA REPORT Docket No.50-272 Date December 10,1986 Telephone 935-6000 Completed by Pell. White Extension 4451 Ope ra t in g Status 1.

Uni t Name Salem No. 1 Notes 2.

Reporting Period November 1986 3.

Licensed The rmal Power (HWt) 3411 4.

Nameplate Rating (Gross MWe) 1170 5.

Design Electrical Rating (Net MWe) 1115 6.

Maximum Dependabic Capacity (Gross MWe)ll49 7.

Maximum Dependable Capacity (Net HWe) 1106 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A 9.

Power Level to Which Restricted, if any (Net MWe)

N/A

10. Reasons for Restrictions, if any N/A This Month Year to Dnte Cumulative
11. Ilours in Reporting Period 720 8016 82585
12. No. of Ilrs. Reacto r was Critical 720 6353.2 50538.6
13. Reactor Reserve Shu tdown ilra.

0 0

0

14. Ilou r s Genera tor on-Lin e 720 6179.8 48684.6
15. Unit Reserve Shutdown llours 0

0 0

16. Gross Thermal Energy Generated (MWil) 2452313 19678676 150162705
17. Gross Elec. Energy Generated (MWil) 838950 6553810 49849820
18. Not Elec. Energy Generated (MWil) 809313 6259519 47365011
19. Unit Service Factor 100 77.1 59.0
20. Unit Availability Factor 100 77.1 59.0
21. Unit Capacity Factor (using MDC Net) 101.6 70.6 51.9
22. Unit Capacity Factor (using DER Net) 100.8 70.0 51.4
23. Unit Forced Outage Rate 0

10.5 26.8

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

N/A

25. If shutdown at end of Report Period. Estimated Date of Startup:

N/A

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

l'o r e c a s t Achieved initial Criticality 9/30/76 12/11/76 Initial Elcetricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Dockot No.50-272 REPORT MONTH NOVEMBER 1986 Unit Nc=2 Snic7 No.1 Date December 10,1986 Ccmpleted by Pell White Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No.

Date Type Hours Reason Down Event System Component Action to 1

2 Reactor R ep ort Code 4 Code 5 Prevent Recurrence There were no outages in November resulting in a 202 MW or over load reduction 1

2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled E-Maintenance or Test 2-Manual Scram.

for Prepara-Source 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 C-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONT!!

NOVEMBER 1986 UNIT NAME:

Salem 1 DATE:

December 10, 1986 COMPLETED BY:

L.

Miller TELEPilONE:

609/339-4497

  • DCR NO.

PRINCIPAL SYSTEM SUBJECT lEC-1681 Cranes Revise upper limit switch protection arrangement as necessary to follow the recommendations made by Westinghouse's Nuclear Division contained in Technical Bulletin #NSD-TB 25-9, dated 9-15-75.

lET-2107 Component Cooling Set up test to measure the pressure and flow transients across the Component Cooling plate heat exchanger (SE & CC Systems) during various system transient evolutions.

ISC-1487 Service Water Provide permanent engineering design to satisfy Operations Department test SP (O) 4.0.5-V leak rate check for 11 and 12 SW51 and 11 and 12 SW79 valves.

  • DCR - Detilgn Chango Request l

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MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH NOVEMBER 1986 UNIT NAME:

Salem 1 DATE:

December 10, 1986 COMPLETED BY:

L. Miller TELEPHONE:

609/339-4497

affect the safe shutdown of the reactor, nor does l

it create a new fire hazard.

This design change does not affect any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

1ET-2107 This test is a temporary hook-up to record pressure transients in the component cooling and service water systems.

There is no permanent change to either system.

This test has no impact on the safe operation of either system.

This design changes does not alter any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

l 1SC-1487 This design change provides a more reliable means of leak rate testing of check valves 11 & 12 SW21 and 11 & 12 SW79.

This improved design will ensure the integrity of the valves.

There is no j

change to the function of the system.

This design changes does not alter any plant process or i

I discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

  • Design Change Request

SALEM UNIT 1 b

MO No UNIT EOUIPMENT IDENTIFICATION l

8611170059 l

1 ENCLOSURE HEATER l

l FAILURE DESCRIPTION:

HEATER FOR THE BAT PUMP ENCLOSURE IS CLOGGED WITH I

BORIC ACID.

TilIS CLOGGING IS AFFECTING THE l

TEMPERATURE ALMOST TO THE POINT OF ENTERING THE ACTION STATEMENT.

PLEASE CLEAN THE HEATER.

CORPICTIVE ACTION:

REPLACED HEATER, REATTACHED THERMOMETERS. HEATER NOW UP TO PROPER TEMP.

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8611170687 1

IWG41 FAILURE DESCRIPTION:

AFTER COMPLETION OF A GAS RELEASE TRIED TO CLOSE VALVE AND IT WOULD NOT CLOSE, EITHER FROM THE CONTROL ROOM I

OR LOCALLY.

HAD TO FAIL THE AIR SUPPLY TO GET VALVE FULLY CLOSED.

PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION:

FOUND SOLENOID SV-611 CLOGGED WITH CORROSION, CLEANED AND REINSTALLED.

FOUND POSITIONER HANGING UP BECAUSE OF FRICTION BETWEEN INTERNALS AND COVER, DUE TO WORN GASKET.

REPLACED GASKET. VERIFIED VALVE ACTION.

8611251130 1

12CS2 FAILURE DESCRIPTION:

12CS2 IS LEAKING OIL FROM THE MANUAL OPERATION LEVER.

PLEASE REPAIR.

1 CORRECTIVE ACTION:

TIGHTENED FLANGE ON VALVE, CLEANED UP OIL.

NO LEAK FROM ACTUATOR.

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 j

WO NO UNIT EQUIPMENT IDENTIFICATION 8610230104 1

11 S/G W.R.

LEVEL CHART i

FAILURE DESCRIPTION:

DURING THE MID SHIFT THIS CHANNEL OF THE CHART RECORDER

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EXHIBITED SEVERE LEVEL INDICATION FLUCTATIONS.

j PLEASE REPAIR.

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CORRECTIVE ACTION:

RECALIBRATED RECORDER PROCEDURE IC-2.10.103. CHECKED WITH OPERATIONS, HAD NOT OCCURRED AGAIN.

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8610260119 i

1 AGITATOR i

FAILURE DESCRIPTION:

THE MOTOR FOR THE BORIC ACID BATCH TANK IS RUNNING 4

BUT THE AGITATOR ITSELF IS NOT TURNING.

PLEASE l

CHECK AND REPAIR.

l CORRECTIVE ACTION:

INSTALLED NEW ROLL PIN ON MOTOR SHAFT GEAR.

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-i 8610290476

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1 12GB4 I

FAILURE DESCRIPTION:

VALVE HAS A BODY TO BONNET STEAM LEAK AND IT IS GETTING WORSE.

PLEASE REPAIR.

i CORRECTIVE ACTION:

BONNET REPAIRED BY FURMANITE REPAIR.

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SALEM UNIT 1 WO NO UNIT EQUIPMENT. IDENTIFICATION 8610300188 1

1TE-441 CHANNEL FUNCTIONAL TEST FAILURE DESCRIPTION:

REACTOR PROTECTION SYSTEM. PERFORM CHANNEL FUNCTIONAL TEST ON ITE-441A/B.

CORRECTIVE ACTION:

FOUND OUT OF SPEC. FOUND LOW LEVEL AMP 1TM-441B OUT OF SPEC. ADJUSTED TO SPEC.

COMPLETED FUNCTIONAL IPD-2.6,013.-

USED PAGE 21 OF IC-2. 2. 013 9N) BE SAT INTO SPEC.

8610300901 1

1R46E DRAWER FAILURE DESCRIPTION:

DRAWER FAILED HIGH.

PLEASE INVESTIGATE AND REPAIR

.AS REQUIRED.

CORRECTIVE ACTION:

FOUND +25 VDC LOW.

REPLACED C5 AND C6 CAP.

PERFORMED DRAWER CAL.

USED CH~ CAL PROCEDURE 1PD-4.l~.082 TO REPAIR DRAWER.

8611050967

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1 LIQUID DISCHARGE RADIATION MONITOR FAILURE DESCRIPTION:

PLEASE DECONTAMINATE OR REPLACE PIG IN-lR18 TO BRING RAD LEVELS TO"50K CPM:OR LESS.

PRESENT READINGS ARE AROUND 240K CPM,'WITH THE ALARM i

SETPOINT AT 400K CPM.

CORRECTIVE ACTION:

REMOVED SHIELDING PULLED PIG AND HAD IT DECONED.

NOW READS 100K.

INSTALLED, FLUSHED OUT LINE AND CHECKED FOR LEAKS, OKAY.

REINSTALLED SHIELDING.

IT IS NOW READING 70K CPM.

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.-q WO NO UNIT EQUIPMENT IDENTIFICATION e

4 8611060725 1

REACTOR PROTECTION'

'3 SYSTEM g

j FAILURE DESCRIPTION:

PLEASE ALIGN THE REACTOR PROTECTION SYSTEM.TO.THE-i NEW DELTA-T AND TAVE VALUES' MEASURED DURING STATE I

POINT DATA TAKEN ON NOVEMBER 3,1986 AS SHOWN ON "

THE ATTACHED SHEET (TABLE 1).

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CORPECTIVE ACTION:

.J3PD-2.6.013, 2.'2.013, 2.6.001, 2.2.001,2 2.6.005, 1PD-2.2.005, 1PD-2.6,009

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1 13 CFCU INLET l

FAILURE DESCRIPTION:

PLEASE RADIOGRAPH THIS VALVE.

FORWARD RESULTS TO j

SHIFT SUPERVISOR.

REQUIRED BY SP (O) 4. 0. 5-V-SW-2.

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CORRECTIVE ACTION:

RADIOGRAPHY PERFORMED 11/22/86.

RADIOGRAPHY REVEALED VALVE 11SW53 TO-BE HALF OPEN. W.O.

8611220021 l

WRITTEN TO MAINTENANCE TO REMOVE VALVE AND INSPECT FOR ABNORMALITIES.

8611100034 j

1 13 AUX FEED FLOW INDIC i

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FAILURE DESCRIPTION:

EVEN THOUGH NO FLOW EXISTS ON 13 AUX FEED LINE, THE l

~ BEZEL INDICATION IS FLUCTUATING IN THE OPERATING BAND.

TEMPERATURE INDICATIONS ON.THE AUX FEED LINES l

.ARE NORMAL AND DO'NOT INDICATE ANY " FLASHING" 1

PROBLEM.

PLEASE INVESTIGATE.

CORRECTIVE ACTION:

EQUALIZED TRANSMITTER AND VERIFIED SOLID 0% FLOW ON INDICATOR.

ALSO CHECKED INPUT AND-OUTPUT OF SQUARE ROOTER WITH TRANSMITTER EQUALIZED AND FOUND.AT 1.00 VDC.

RETURNED TO SERVICE. PROBLEM TO.BE.

POSSIBLE CHECK VALVE SEATING PROBLEM.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 NOVEMBER 1986 The Unit operated at 100%, 1130 MW Net until November 22, 1986.

On

. November 22, 1986, power was reduced to 85% to remove No. 12 Heater Drain Pump ~from service for repair to the motor power feed splice.

Power was increased to 92%, 1050 MW, while the repair work was performed.

The Unit was returned to 100% power at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on-November 23, and continued at that level until November 26, when power was briefly reduced to 92% due to feedwater heater control problems.

On November 26, 1986, the Unit was returned to 100% power where it continued to operate for the remainder of the period.

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REFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

L.K. Miller UNIT NAME:

Salem 1 DATE:

December 10, 1986 TELEPHONE:

T69/935-6000 EXTENSION:

4497 Month November 1986 1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

September 12, 1987 3.

Scheduled date for restart following refueling: November 26, 1987 4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE X

B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X

If no, when is it scheduled?

August 1987 l

S.

Scheduled date (s) for submitting proposed licensing action:

August 1987 if required 6.

Important licensing considerations associated with refueling:

NONE I

7.

Number of Fuel Assemblies:

A)-

Incore 193 B)

In Spent Fuel Storage 380 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 8-1-7.R4

.... =

O O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 12, 1986 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 November 1986 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, J.

M.

Zupko, Jr.

General Manager - Salem Operations JR:sl cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management U.S.

Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Enclosures 8-1-7.R4 fl!

The Energy People asmw i v m

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