ML20206B258

Monthly Operating Rept for May 1986.W/860610 1tr

ML20206B258
Person / Time
Site:	Salem
Issue date:	05/31/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8606190049
Download: ML20206B258 (12)

Text

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OPERATING DATA REPORT Docket No. 50-311 Date June 10,1986 Telephone 935-6000 Completed by Pell' White Extension 4451 Operating Status 1.

-Unit.Name Salem No. 2 Notes 2.

Reporting Period May 1986 3.

Licensed Thermal Power (MWt) 3411 4.

Nameplate Rating (Gross MWe)

TT76 5.

Design Electrical Rating (Net MWe)

TIT 5 6.

Maximum Dependable Capacity (Gross MWe) TIT 9 7.

Maximum Dependable Capacity (Net MWe) 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-Date Cumulative

11. Hours in Reporting Period 744 3623 40608

12. No. of Hrs. Reactor was Critical 713.4 3128.0 23453.8 13.- Reactor Reserve-Shutdown Hrs.

0 0

3533.6

14. Hours Generator On-Line 700.0 3087.7 22624.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2324078 10233464 69979162

17. Gross Elec. Energy Generated (MWH) 750850 3363200 22939680

18. Net Elec. Energy Generated (MWII) 718914 3219044 21753888

19. Unit Service Factor 94.1 85.2 55.7

'20. Unit Availability Factor 94.1 85.2 55.7

21. Unit. Capacity Factor (using MDC Net) 87.4 80.3 48.4

22. Unit Capacity Factor (using DER Net) 86.7 79.7 48.0

23. Unit Forced Outage Rate 5.9 12.3 34.7 24.' Shutdowns scheduled over next 6 months (type, date and duration of each)

REFUELING 9-20-86

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

N/A

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

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81

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8606190049 860531

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-311 Unit Name Salem # 2 Date June 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month May 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET)

-1 930 17 1057 2

0 18 1064 3

0 19 1060 4-771 20 1065 5

1059 21 1054 6

1067 22 1050 7

1065 23 899 8

1081 24 1026 9

1075 25 1049 10 1058 26 1048 11 999 27 1032 12 1068 28 1052 13 1057 29 1052 i

14 1065 30 1047 15 1065 31 1014 16 1071 l

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Docket-No. 50-311~

UNIT' SHUTDOWN AND POWER REDUCTIONS

~ REPORT MONTH MAY 1986-Unit'Nr.me Stalem NA 2 Date.

Juno 10,1986-Telephone. 609-935-6000

. Completed by-Pell' White Extension 4451 Method of cause and corrective-Duration Shutting License Action to No..

Date Type Hours Reason Down Event System Component

. Prevent Recurrence-1 2

Reactor Report Code 4 Code 5 Other Nuclear-Reactor SF-VESSEL Problems Misc.

268 0501-F 5.2 A

5 Other Nuclear-Reactor SF VESSEL Problems Misc.

270 0502 F

44.0 A

1

~ Loss of' Vacuum /High HC HTEXCH Back Pressure 320 0523 F.

12.4 A-5 Feedwater Pump Drive CH PUMPXX Lube Oil System 348 0531 F

2.1 A

5 3 Method 4 Exhibit-G 5 Exhibit 1 1

2 Reason 1-Manual Instructions Salem as F: Forced A-Equipment Failure-explain 2-Manual Scram.

for Prepara-Source S: Scheduled B-Maintenance or Test 3-Automatic Scram, tion of. Data C-Refueling 4-Continuation of. Entry. Sheets D-Regulatory Restriction E-Operator Training & Licensing Exam Previous Outage for. Licensee 5-Load Reduction Event Report-F-Administrative 9-Other (LER) File G-Operational Error-explain (NUREG 0161)

H-Other-explain

-MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 REPORT MONTH MAY 1986 UNIT NAME:

Salem 2 DATE:

June 10, 1986 COMPLETED BY:

J.

Ronatalvy TELEPHONE:

609/339-4455

• DCR NO.

PRINCIPAL SYSTEM SUBJECT 2EC-1501 Diesel Generators Install control circuit transfer switches on the engine and generator control panels of each diesel generator to enable an operator to start the diesel generators under postulated fire and blackout conditions.

2EC-1566 Chilled Water System Install a 10 PSIG' relief valve at the chilled water expansion tank.

2EC-1785 Safe Guards Emergency Install new Lamda Power Controls Supplies new Potter Brumfield relays in 2B SEC, 2A SEC and 2C SEC.

2EC-1970 Containment Personnel Install caps and valving Hatch at personnel hatch -

El. 100 & 130.

2EC-2000 Main Reheat & Turbine Replace turbine first stage Bypass impulse pressure pressure transmitters PA-0195 and PA-0216 and mount so as to reduce vibration.

I 2SC-1168 Reactor Coolant System Change reactor coolant flow transmitter from Fisher Porter model # 10B2496PB to new model and type specified I

by Engineering.

l Design Change Request l

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MAJOR PLANT MODIFICATIONS DOCKET NO:

50-311 REPORT MONTH - MAY 1986 UNIT NAME:

SALEM 2 DATE:

MAY 10, 1986 COMPLETED BY:

J.

RONAFALVY TELEPHONE:

Tro9)339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1501 This design change improves the plant safety by making vital power available much sooner during certain postulated fire plus blackcut conditions.

Failure of the control transfer switch may cause the associated diesel to fail to start during a safeguards actuation.

This failure is considered to be within the realm of the single failure criteria.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

2EC-1566 This design change does not jeopardize the pressure retaining boundary nor impact the operation or basic design criteria of the Chilled Water System.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

2EC-1785 This design change replaced existing components with ones manufactured by a different vendor.

The replacement components have been seismically qualified to IEEE 344 which is to the same or higher stress levels as the original equipment.

l This modification does not alter any plant j

process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

l 2EC-1970 All realistic failure modes have been considered l

but are not applicable.

This design change meets l

GDC 56 requirements and complies with Safety Guide #11.

The-additional equipment meets the-l design criteria of seismic I and nuclear class j

II.

This modification does not alter any plant l

process or discharge.

Therefore, no unreviewed i

safety or environmental questions are involved.

i Design Change Request l

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UNIT.2 MAJOR PLANT MODIFICATIONS (contd)

REPORT MONTH - MAY 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-2000 The existing transmitters malfunction.

The replacement ones are of better design.

There is no functional change in the system or component.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or env'.ronmental questions are involved.

-2SC-1168 All potentiel, realistic failure modes have been considered but are not applicable.

Regulatory requiremen'.s do not apply.

The replacement transmitters do not modify the function of the system.

the original transmitters _are considered obsolete by the manufacturer.

This modification does no+. alter any plant process or discharge.

Therefere, no unreviewed safety or environmental questions are involved.

Design Change Request

PSE&G SALEM-GENERATING STATION' SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8604251090 2

21 CHILLER CONDENSER FAILURE DESCRIPTION:

21 CHILLER CONDENSER HAS A TUBE LEAK.

CORRECTIVE ACTION:

REPLACED DEFECTIVE CONDENSER TUBE, PRESSURE TESTED SYSTEM.

REPLACED FILTER, DRYERS AND OIL.

8605020580 2

RTD ORIFICE FAILURE DESCRIPTION:

22 RCP COLD LEG BYPASS RTD ORIFICE IS BLOWING AND LEAKING ONTO FLOOR.

CORRECTIVE ACTION:

REPLACED GASKET IN FLANGES.

8605121173 2

21 SW PUMP AUTO CONTROL FAILURE DESCRIPTION:

21 SERVICE WATER PUMP WILL NOT STAY IN THE AUTO CONTROL MODE.

CORRECTIVE ACTION:

INSTALLED NEW OPERATE RESET RELAY-IN BAILEY CABINET RC-116.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8605121513 2

26 SW PUMP FAILURE DESCRIPTION:

PUMP HAS EXCESSIVE PACKING LEAKAGE.

CORRECTIVE ACTION:

REPACKED PUMP.

8605140500 I

2 21 SW STRAINER FAILURE DESCRIPTION:

STRAINER HAS A SEVERE PACKING LEAK.

l CORRECTIVE ACTION:

REPLACED PACKING.

8605150882 o

2 REACTOR VESSEL FLANGE LEAKOFF INDICATOR FAILURE DESCRIPTION:

BEZEL INDICATION HAS_ FAILED HIGH, VERIFIED VESSEL LEAKOFF WITH COMPUTER POINT.

CORRECTIVE ACTION:

FOUND LOWER LEVEL AMP 2TM-401 FAILED HIGH. REPLACED S/N E092 WITH S/N E040.

CALIBRATED TO-AS LEFT' VALUES.OF TABLE 20.0 PAGE 5 OF 2IC-2.10.047.

RETURNED CHANNEL TO SERVICE.

TEMPERATURE INDICATION WAS 87 DEGREES F.

-SALEM UNIT 2 WO NO UNIT-EQUIPMENT IDENTIFICATION 8605190019 2

ACCUMULATOR LEVEL CHANNEL' FAILURE DESCRIPTION:

1. 24-ACCUMULATOR CHANNEL 2 LEVEL HI-LO ALARM IS

-ILLUMINATED.

NO-APPARENT LEVEL PROBLEM.

CORRECTIVE' ACTION:

REPLACED PC BOARD IN RELAY RACK #112 AND TESTED OKAY.

8605200073 2

CHARGING FLOW ORIFICE FAILURE DESCRIPTION:

NO CLOSED INDICATION.

CORRECTIVE ACTION:

REALIGNED LIMIT SWITCH ACTUATING ARM AND TIGHTENED.

TIGHTENED LIMIT SWITCH BRACKET.

CONTROL STROKED AND VERIFIED LIMITS.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 MAY 1986 SALEM UNIT NO. 2 The Unit began the period operating at full power.

On May 2, 1986 at 1717 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.533185e-4 months <br />, a controlled shutdown was initiated to perform environmental equipment qualification inspections in the containment.

As the Unit was taken off the line, on May 3, 1986 at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br />, a Reactor Trip with Safety Injection occurred due to "Higl. Steam Line Flow With Low Tave" which aas apparently caused by a steem flow spike when the Generator output breakers were opened.

On May 3, 1986 at 2231 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.488955e-4 months <br />, the Turbine was latched and power ascension to full power operations was initiated.

Unit power was reduced to 65% on May 11, 1986 at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> due to limited system load demand. The Unit was returned to full power the same day at 0642 hours0.00743 days <br />0.178 hours <br />0.00106 weeks <br />2.44281e-4 months <br />.

During the period from May 23, 1986 to May 25, 1986 minor load reductions were required '

due to high river grasses and debris causing Circulating Water System problems.

On May 31, 1986 at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> a load reduction to 61% was commenced in order to remove #21 SGFP from service for replacement of

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the governor.

On June 1, 1986 at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, work on #21 SGFP was completed and the Unit was returned to 100% power where it remained for the rest of the period.

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REFLELING INFORMATION

c DOCKET NO.

50-311

~ Ronafalvy UNIT NAME:

Salem 2 COMPI7.TED BY:

J.

DATE:

June 10, 1986 t

TELEPHONE:

609/935-6000 EXTENSION:

4455 Month May 1986 _

1.

Refueling information has changed from last month:

YES NO X

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2.

~ Scheduled date fcer next refueling:

September 20, 1986 3.

Scheduled date for restart following refueling: November 19, 1986 4.

A)

Will Technical Specification changes or other license amendments be required?

YES ND Not determined to date B)

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

YES NO X

If no, when is it scheduled?

August 1986 5.

Scheduled date (s) for submitting proposed licensing action:

August 1986 if required 6.

Important licensing considerptions associated with refueling:

NONE 4

7.

Number of Fuel Assemblies:

A)

Incore 193 B)

In Spent Fuel Storage 140 8.

Present licensed spent fuel stcrage 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:

March 2003 8-1-7.R4

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([]>IP'!!ilBitEi Public Service Electric and Gas Company P O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June'10, 1986 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear-Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In compliance with'Section 6.9, Reporting Requirements for the Salem Technical Specification, 10 copies of the following monthly operating reports for the month of May 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 The Energy People

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