ML20197H825

Monthly Operating Rept for Apr 1986

ML20197H825
Person / Time
Site:	Salem
Issue date:	04/30/1986
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8605190299
Download: ML20197H825 (15)

Text

AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-311 Unit Name Salem # 2 Date May 10,1986 Completed by Pell White Telephone 609-935-6000 i

Extension 4451 Month April 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1079 17 0

2 1069 18 623 3

1076 19 924 4

1074 20 1084 5

1087 21 1093 6

1089 22 1055 7

1073 23 1085 8

1083 24 1084 9

1087 25 1065 10 1102 26 1065 11 1064 27 1008 12 696 28 1072 13 722 29 1061 14 1080 30 1066 15 1107 31 16 703 Pg. 8.1-7 R1 m=m mapy R

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

Unit Name Salem No. 2 Notes 2.

Reporting Period April 1986 3.

Licensed Thermal Power (MWt) 3411 4.

Nameplate Rating (Gross MWe) 1170 5.

Design Electrical Rating (Net MWe) 1115 6.

Maximum Dependable Capacity (Gross MWe) 1149 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 719 2879 39864

12. No. of Hrs. Reactor was Critical 699.2 2414.6 22740.4

13. Reactor Reserve Shutdown Hrs.

0 0

3533.6

14. Hours Generator On-Line 690.3 2387.7 21924.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (FMH) 2257325 7909386 67655084

17. Gross Elec. Energy Generated (MWH) 738530 2612350 22188830

18. Net Elec. Energy Generated (MWH) 707443 2500130 21034974

19. Unit Service Factor 96.0 82.9 55.0

20. Unit Availability Factor 96.0 82.9 55.0

21. Unit Capacity Factor (using MDC Net) 89.0 78.5 47.7

22. Unit Capacity Factor (using DER Net) 88.2 77.9 47.3

23. Unit Forced Outage Rate 4.0 14.0 35.4

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 Status (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 8-1-7.R2

l UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH APRIL 1986 Unit Name Salem No. 2 Date Mny 10,1986 Completed 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 Report Code 4 Code 5 Prevent Recurrence 212 0412 F

8.0 A

5 HA GENERA Generator Vibration 214 0412 F

8.0 A

4 HA GENERA Generator Vibration 216 0413 F

4.0 B

5 HC PUMPXX Condensate /

Hotwell Pumps 218 0113 S

10.4 B

4 HC PUMPXX Condensate /

Hotwell Pumps 222 0418 F

0.9 A

5 HH PUMPXX Feedwater Pump / Drive Lube Oil System 3 Method 4 Exhibit G 5 Exhibit 1 1

2 Reason F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-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 G-Operational Error-explain 9-Other (LER) File (NUREG 0161)

H-Other-explain

-MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 REPORT MONTH APRIL 1986 UNIT NAME:

Salem 2 DATE:

May 10, 1986 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DCR NO..

. PRINCIPAL SYSTEM SUBJECT 2EC-1589 Cable Trays - Various Retag, ' repull various cables FSAR Sec-B,R1,4,2,3 throughout the plant to match wiring diagrams. prior to the implementation of the DCR System.

2EC-1658 Control Rods Salem 1 & 2 have different control-rod patterns, as regards bank location and bank identification in certain selected control banks to achieve a close resemblance to the Unit.1 control rod pattern.

Table 1 lists the current and proposed control bank identification scheme.

2EC-1789 Various Environmentally upgrade numerous limitorque valve motor operators. This upgrading is.to be accomplished by the replacement of various motor operator parts with parts which are better suited for use in harsh environmental zones.

Design Change Request

UNIT 2 PLANT MODIFICATIONS (continued)

REPORT MONTH APRIL 1986

• DCR NO.

PRINCIPAL SYSTEM SUBJECT 2EC-1861 CVC - Charging /

Replace the existing lube Safety Inj. Pumps oil coolers on the Nos. 21 Lube Oil Coolers and 22 C/SI pumps with coolers of similar design characteristics but upgraded materials of construction.

The upgraded coolers will have outer tube sheets and tubes consisting of titanium material.

The new coolers will involve a change to their respective lube oil tubing and service water piping, and cooler support plate.

2EC-1863 Safety Inj. System Replace the existing Lube Oil Coolers on the Nos. 21 & 22 SI pumps with coolers of similar design characteristics but upgraded materials of construction.

The upgraded coolers will have outer tube sheets and tubes consisting of titanium material. Installation of the new coolers will involve a change to their respective lube oil tubing, service water piping and cooler mounting location.

2EC-2081 Aux Feedwater System Present B-J Aux Feed Pump No.

22 is damaged.

Replacement with an equivalent pump from Ingersoll-Rand is required.

2SC-1354 VS - Fuel Handling Revised long time trip Area setting of Aux. Building and Fuel Handling Building Exhaust Fans Feeder breaker.

Design Change Request

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' UNIT 2 PLANT MODIFICATIONS (continued)

' REPORT MONTH APRIL 1986

• DCR NO.

PRINCIPAL SYSTEM SUBJECT 2

2SC-1358 VS - Containment Fan Replace Containment Fan Coil Coil Units Unit Suction expansion joints with ones of improved. design.

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• Design Change Request 1

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s MAJOR PLANT MODIFICATIONS DOCKET NO:

50-311 REPORT MONTH - APRIL 1986 UNIT NAME:

SALEM 2 j

DATE:

APRIL 10, 1986 j

COMPLETED BY:

J.

RONAFALVY TELEPHONE:

(609)339-4455 4

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• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1589 This design change involves only field verification of cable routings and termination.

There are no actual changes in any system.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

)

2EC-1658 Electrical failure concerns were reviewed in preparing this design change but were-found not 4

i to involve any unreviewed safety questions.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

2EC-1789 The replacement of the existing motor operator

~j components with environmentally qualified ones increases the functional reliability of the affected valve operators.

This modification does

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not alter any plant process-or discharge.

^

Therefore, no unreviewed safety or environmental questions are involved.

2EC-1861 The new lube oil coolers are constructed of better materials.

They have greater corrosive t

resistance to the affects of service water.

They meet the required ASME code (s).

The original coolers were non-code / commercial coolers.

Therefore, this is a design upgrade.

The oil reservoir for the new coolers has a slight (insignificant) increase in capacity.

This modification-does not alter any plant process or discharge. Therefore, no unreviewed safety or environmental questions are. involved.

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Design Change Request i

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-... - - _., _ _ _.___...._. _. ~..._,_., -,,_ ~.,,,,, _ --._ -. _ _ _._.,,.- -

UNIT 2 MAJOR PLANT MODIFICATIONS ~ (contd)

REPORT MONTH - APRIL 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1863 This design change upgrades the Safety-1 Injection Lube Oil Coolers.

The new coolers are seismically qualified.

The new tube, shell and bonnet construction materials are much less susceptible to the corrosive characteristics of the service water system fluid.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

2EC-2081 The new pump does not compromise structural integrity.

The new pump is equivalent to the design characteristics of the original pump.

This modification does not alter any plant process or discharge.

Therefore, no unreviewed safety or environmental questions are involved.

2SC-1354 This design change involves the adjustment of the long time overcurrent protection on the Aux, and Fuel Buildings exhaust fan motors.

This modification will eliminate nuisance tripping of the motors due to setpoint drift on the breaker 3

overcurrent trip device.

The new setpoints will provide adequate overcurrent protection for the fans.

This modification does not alter any plant process or discharge. Therefore, no unreviewed safety or environmental questions are involved.

Design Change Request i

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UNIT 2 MAJOR PLANT MODIFICATIONS -(contd)

REPORT MONTH - APRIL 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 2SC-1358 The expansion joint connects the fan section to the filter section of the containment fan coil unit (CFCU).

The joint is designed to absorb vibration and thermal expansion in the fan coil unit.

The existing joint has been degraded due to aging and poor design.

The replacement joint is made of better materials and is qualifeid to withstand the environmental conditions inside the Containment after an accident.

Loss in the sense of a hole or tear in any one of -the expansion joints will not impact the Containment cooling capability since only three out of the five CFCU's are required to mitigate the consequences of a design basis accident.

The new joint does not affect any presently performed safety analysis nor does it create any new safety hazards.

The rubber material used in these joints has been "hypalon" jacketed to minimize the fire hazard of the material and is resistant to radiation degradation.

This modification does not alter any plant process or discharge.

Tehrefore, no unreviewed safety or environmental questions are involved.

I Design Change Request ij.

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 I

i WO NO UNIT EQUIPMENT IDENTIFICATION 8603050031 2

22 CC PUMP i

FAILURE DESCRIPTION:

THE INBOARD BEARING CASING IS LOOSE WHICH IS CAUSING EXCESSIVE OIL LEAKAGE FROM BEARING HOUSING.

CORRECTIVE ACTION:

DISASSEMBLED PUMP AND REPLACED OIL AND MECH SEALS.

REASSEMBLED PUMP.

0099183978 2

21 SW PUMP STRAINER l

FAILURE DESCRIPTION:

STRAINER HAS A BROKEN SHEER KEY.

CORRECTIVE ACTION:

INSPECTED BACKWASH ARMS, REPLACED ONE SEAL PLATE, RESET SHAFT LIFT, REPLACED KEY.

0099183927 2

HEAT TRACE-FOR 2SJ12 l

FAILURE DESCRIPTION:

TEMP-IS LOW AND AMP READINGS ARE LOW.

CORRECTIVE ACTION:

REPLACED THE DAMAGED SECTIONS OF HEAT TRACE NUMBERS 2623 A & B.

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SALEM UNIT 3 WO-NO UNIT EQUIPMENT IDENTIFICATION 0099183986 2

22 AUX FEED PUMP FAILURE DESCRIPTION:

THE PUMP WOULD NOT STOP FROM CONTROL ROOM.

PUMP.

STOPPED LOCALLY AT BREAKER.

CORRECTIVE ACTION:

BREAKER SER 0224A6269 WAS TESTED AT TEST STATION.

SPRINGS WOULD NOT CHANGE.

BREAKER SERIAL 0224A6357-002 WAS INSTALLED IN 22 AUX. FEED PUMP.

0099184001 2

21E & 23E STEAM l

DUMP i

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. FAILURE DESCRIPTION:

THERE IS NO CLOSE INDICATION IN CONTROL ROOM.

CORRECTIVE ACTION:

REPOSITIONED ACTUATING ARM AND VERIFIED CLOSE. LIGHT IN CONTROL ROOM.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8601150292 2

22 AUX SUPPLY FAN

. FAILURE DESCRIPTION:

THE HEATING' COIL HAS A BAD LEAK.

THE COIL-HAS BEEN ISOLATED.

CORRECTIVE ACTION:

REPLACED HEATING COIL.

8604100032 2

24 SW STRAINER SHAFT FAILURE DESCRIPTION:

24 SW STRAINER SHAFT IS EITHER BENT OR WORN.

(REPACKED-& STILL LEAKS).

CORRECTIVE ACTION:

INSTALLED NEW SHAFT, REPACKED.

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

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

On April 12, 1986 at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, unit load was reduced to 25% due to a Turbine runback caused by a leak from a generator stator water sensing line which shorted a micro switch in the runback circuit.

At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> the same day, power ascension was initiated and stopped at 82% power in order to repair #22 Condensate Pump expansion joint.

Unit power ascension was resumed at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on April 13, 1986 and the unit was brought to full power operation.

On April 16, 1986 at 1627 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.190735e-4 months <br />, the unit tripped on #23 Steam Generator Hi-Hi Level as a result of the transient following the loss of #22 Steam Generator Feed Pump (SGFP).

The trip of #22 SGFP was due to an accumulation of water in the control oil due to an improperly functioning oil separator.

Following i

a complete oil replacement and repair to the separator, the unit was returned to service at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> on April 17, 1986 and brought to full power.

On April 27, 1906 at 0502 hours0.00581 days <br />0.139 hours <br />8.300265e-4 weeks <br />1.91011e-4 months <br />, power was reduced to permit repacking of the #23 Heater Drain Pump. The unit was returned to full power operation at 1507 hours0.0174 days <br />0.419 hours <br />0.00249 weeks <br />5.734135e-4 months <br /> the same day where it remained for the rest of the period.

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REFUELING INFORMATION DOCKET NO.:

50-311 COMPLETED BY:

J.

Ronafalvy UNIT NAME:

Salem 2 DATE:

May 10, 1986 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month April 1986 1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for 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 NO l

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 1

5.

Scheduled date(s) for submitting proposed licensing action:

August 1986 if required 6.

Important licensing considerations associated with refueltng:

NONE 7.

Number of Fuel Assemblies:

A)

Incore 193 B)

In Spent Fuel Storage 140 l

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:

March 2003 8-1-7.R4

8 >SEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08033 Salem Generating Station May 10, 1986 Director, Office of Insi action 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 Sal'em Technical Specification, 10 copies of the following monthly operating reports for the month of April 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, 0

0

\\

( g a

r C.M.

Zttpko Jr.

i;cneral 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

' l The Energy People

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