ML20203A276

Monthly Operating Rept for June 1986

ML20203A276
Person / Time
Site:	Salem
Issue date:	06/30/1986
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8607170205
Download: ML20203A276 (14)

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date July 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month June 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 722 17 1013 2 1067 18 1021 3 1070 19 1029 4 1075 20 1013 5 1083 21 1016 6 1040 22 1043 7 1049 23 1041 8 1062 24 1046 9 1059 25 1037 10 1054 26 1035 11 1053 27 1065 12 1044 28 1057 13 1060 29 1062 14 1050 30 1030 15 1055 16 1046 Pg. 8.1-7 R1 0607170205 860630 PDR ADOCK 05000311 YUR

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• i OPERATING DATA REPORT 1

i Docket No. 50-311 '

3 Date July 10,1986 4

Telephone 935-6000 Completed by Pell White Extension 4451  :

Operating Status i Notes

1. Unit Name Salem No. 2

] 2. Reporting Period June 1986

3. Licensed Thermal Power (MWt) 3411 i 4. Nameplate Rating (Gross MWe) 1170 1 5. Design Electrical Rating (Net MWe) TITT

6. Maximum Dependable Capacity (Gross MWe)1149 ,

j 7. Maximum Dependable Capacity (Net MWe) 1106 3 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last l Report, Give Reason N/A i

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

! 10. Reasons for Restrictions, if any N/A 1- ,

This Month Year to Date Cumulative i

11. Hours in Reporting Period 720 4343 41328

12. No. of Hrs. Reactor was Critical 720 3848 24173.8

13. Reactor Reserve Shutdown Hrs. 0 0 3533.6

14. Hours Generator On-Line 720 3807.7 23344.5

15. Unit Reserve Shutdown Hours 0 0 0 l

j 16. Gross Thermal Energy Generated 1

(MWH) 2429813 12663277 72408975 j 17. Gross Elec. Energy Generated

(BOGI) 778230 4141430 23717910

18. Net Elec. Energy Generated (MWH) 746272 3965316 22500160

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i 19. Unit Service Factor 100 87.7 56.5 i 20. Unit Availability Factor 100 87.7 56.5 1 21. Unit Capacity Factor i (using MDC Net) 93.7 82.6 49.2

22. Unit Capacity Factor

(using DER Net) 93.0 81.9 48.8 i 23. Unit Forced Outage Rate 0.0 10.2 34.0 l 24. Shutdowns scheduled over next 6 months (type, date and duration of each)

{ REFUELING 9-20-86 d

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

i l N/A l 26. Units in Test Status (Prior to Commercial Operation) :

I 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 l 8-1-7.R2 l

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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH June 1986 Unit Nama Salem No.2 Date July 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Methoc of Duration Shutting License Cruse and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Feedwater Pump Drive 348 0531 F 17.3 A 5 -

CH PUMPXX Lube Oil System 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as B-Maintenance or Test 2-Manual Scram. for Prepara- Source

.S: Scheduled 3-Automatic Scram. tion of Data C-Ref ueling 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)

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH JUNE 1986 UNIT NAME: Salem 2 DATE: July 10, 1986

COMPLETED BY: J. Ronafalvy i TELEPHONE: 609/339-4455

• DC R NO . PRINCIPAL SYSTEM SUBJECT 2 EC-06 51 Service Water System Replacement of the strainer backwash line with stainless-

! steel piping at the entire water intake structure (R.P.

Adams strainer) . The

material of pipe will be

SS316, and insulated with

'i fiberglass material. The pipe sections changed will be from strainer backwash discharge to SW25 valves (there are already S.S.

1 pipes in the two (2) orifices sections) .

] 2EC-1688 Service Water Replace existing C.S.

piping with S.S. at l selected high erosion

, areas upstream and j downstream of 21 & 22 fan i coil units. These areas are downstream of 21 & 22 SW58 and upstream and'

downstream of 21 & 22

SW65.

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2EC-1916 Reactor Coolant System Replace RTD bypass loop

, valves 22RC 16, 17, 24,

! 25, & 28, Mark No. FA-17 with Mark No. FA-131.

l 2EC-1917 Reactor Coolant System Replace RTD bypass loop i valves 23RC 16,17,24, i 25, & 28, Mark No. FA-17 with Mark No. FA-131, 2EC-1918 Reactor Coolant System Replace RTD bypass loop i

valves 24RC 16, 17, 24, 25, & 28, Mark No. FA-17 j and with Mark No. FA-131.

2EC-1919 Reactor Coolant System Replace RTD bypass loop valves 21RC 16, 17, 24, 25, & 28, Mark No. FA-17 and with Mark No. FA-131.

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MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH JUNE 1986

• DCR No. PRINCIPLE SYSTEM SUBJECT 2EC-1946 VS Containment Fan Installation of spring coil units assembly in the backdraft damper mechanism of the containment fan coil units i

Nos. 21, 22, 23, 24, and 25.

2EC-2072 Main Reheat & To adjust, in a uniform Turbine bypass manner, the cold load setting of nine (9) spring hangers located on the NO.

24 Main Steam Header i between the Reactor containment wall and the-mixing bottle, to a.new d

load setting.

2SC-1281 Gen Cooling System Change nipple joint configuration on failed tube connections; expand

, capacity of Doric Scanner; Add 48 thermocouples to Main Generator.

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• Design Change Request 4

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MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - JUNE 1986 UNIT NAME: SALEM 2 DATE: July 10, 1986 COMPLETED BY: J. RONAFALVY TELEPHONE: (609)339-4455

• DC R SAFETY EVALUATION 10 CFR 50.59 2EC-0651 The replacement of the Service Water strainer backwash line carbon steel line with 316 stainless steel material will not cause an accident or malfunction not previously mentioned or analyzed in the SAR. The new piping will better withstand service water erosion and therefore will not compromise the service water pressure boundary integrity.

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

2 EC-16 88 This piping replacement is an improvement since the materials used will be better able to withstand the corrosive / erosive affects of the system. No change in the system function will result. Also, the additional supports will ensure the structural integrity of the Seismic I system. This modification does not alter any plant process. Therefore, no unreviewed safety or environmental questions are involved.

2EC-1916 The replacement of the valves does not alter the ability of th. piping system to perform as designed. The new valve meets or exceeds the seismic, nuclear, and pressure class of the existing valves. The installed flowmeter will ensure that the required flow is not affected.

LER 84-001-00 committed the Station to making this modification. This modification does not alter any plant process or discharge. Therefore, no unreviewed safety or environmental questions are involved.

2 EC-1917 The replacement of the valves does not alter the ability of the piping system to perform as designed.

The new valve meets or exceeds the seismic, nuclear, and pressure class of the existing valves. The installed flowmeter will ensure that 1 the required flow is not affected. LER 84-001-00 l committed the Station to making this modification.

This modification does not alter any plant process or discharge. The re fore , no unreviewed i safety or environmental questions are involved. l l

Design Change Request

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UNIT 2 MAJOR PLANT MODIFICATIONS (contd) l REPORT HONTH - JUNE 1986 i

• DCR SAFETY EVALUATION 10 CFR 50.59 2BC-1918 The replacement of the valves does not alter the ability of the piping system to perform as designed. The new valve meets or exceeds.the seismic, nuclear, and pressure class of the 4

existing valves. The installed flowmeter will j ensure that the required flow is not affected.

- LER 84-001-00 committed the station to making this modification. This modification does not-4l alter any plant process ce discharge. Therefore, no unreviewed safety or environmental questions

are involved. ,

2BC-1919 The replacement of the valves does not alter the ability of the piping system to perform as 1

designed. The new valve meets or exceeds the seismic, nuclear, and pressure class of the existing valves. The installed flowmeter will j ensure that the required flow is not affected.

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

f 2EC-1946 The presently installed dampers in the Fan Coil

] Unit system are sluggish in closing after-the fan -

j is turned off. The purpose of the dampers is to

! prevent back flow through the non-operating fan.

j The new spring assembly (outside the airflow) will provide the necessary initial momentum to the counter weights thereby assisting in closing

! the dampers positively. The spring assembly will not prevent opening the dampers for fan operation.

Failure of the spring will not jeopardize the i operation of the backdraft damper. This change will not affect any presently performed safety analysis nor does it create any new hazards. No plant process or discharge is affected by this design change. No unreviewed safety or environmental questions are involved.

• Design Change Request

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s UNIT 2 MAJOR PLANT MODIFICATIONS (contd)

REPORT MONTH - JUNE 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 01 2BC-2072 The adjustment of nine hangers on the No. 24 Main F. team Header to a new load setting in no way will create a new safety hazard. There are no changes in the UFSAR nor to the Technical Specifications.

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

2SC-1281 This change expands the capacity of the Doric Scanner but does not alter its function or the function of the Generator Stator Water Cooling system. The safe shutdown of the reactor is not a f fected . This change also involved the addition of 48 thermocouples to the Main Generator. This modification does not alter any plant process or discharge. Therefore, 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 8605271701 2 21MS10 FAILURE DESCRIPTION: 21MS10 IS LEAKING BY.

CORRECTIVE ACTION: MADE ZERO ADJUST TO POSITIONER, STROKED VALVE 3.9 PSI FOR OPEN AND CLOSED INDICATION IN CONTROL ROOM.

8605230983 2 26 SW PUMP PACKING FAILURE DESCRIPTION: #26 SW PUMP HAS A PACKING LEAK.

CORRECTIVE ACTION: REPLACED PACKING.

8605230991 2 21 SW PUMP STRAINER PACKING FAILURE DESCRIPTION: #21 SW PUMP STRAINER HAS A PACKING LEAK.

CORRECTIVE ACTION: REPLACED STRAINER.

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SALEM UNIT 2 EQUIPMENT IDENTIFICATION WO NO UNIT

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8605220139 2 RCS HIGH/ LOW TAVG ALARM FAILURE DESCRIPTION: RCS HIGH/ LOW TAVG CONSOLE ALARM IS IN AND OUT q

OF ALARM. RCS TEMP. IS NOT AT ALARM SETPOINT. i CORRECTIVE ACTION: FOUND 2TC-422CD OUTPUT #1 WILL NOT RESET. REMOVED SN621 AND INSTALLED SN-156. ADJUSTED TO SPEC AS PER 2PD-2.1.059 PAGE 55. COMPLETED FUNCTIONAL 2PD-2.6.005 SAT. .

8605160659 2 2CV172 FAILURE DESCRIPTION: THE AUTO SETPOINT WILL NOT MAINTAIN AT SET VALUE DURING AUTO MAKEUP.

CORRECTIVE ACTION: STROKED VALVE ADJUSTED LIMIT SWITCH ACTUATOR AND VALVE POSITINER. FOUND RESET TO BE SLOW.

SET RESET TO 4.3 AS PER ICD CARD.

8605121564 2 21 BAT PUMP FAILURE DESCRIPTION: PUMP IS SHOWING EORIC ACID BUILD UP AROUND SEAL, INDICATIVE OF THE SEAL STARTING TO PAIL.

CORRECTIVE ACTION: INSTALLED A NEW MECHANICAL SEAL.

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1 SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION .

8601040039 2 22 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: #22 WASTE GAS COMPRESSOR MOTOR WAS SMOKED WHEN COMPRESSOR PUMPED EXCESSIVE WATER IN VENT HEADER.

COMPRESSOR MOTOR BREAKER TRIPPED ON OVERLOADS, BUT-NOT BEFORE MOTOR SMOKED.

CORRECTIVE ACTION: REPLACED MOTOR , REPLACED COMPRESSOR.

0099181975 2 21CN108 i FAILURE DESCRIPTION: 21CN108 BREAKER 2HYSTB10 A IS TRIPPED AND WILL NOT RESET.

CORRECTIVE ACTION: REPLACED CONTROL TRANSFORMER, REPLACED BAD AUX. RELAY.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO.~2 JUNE 1986 SALEM UNIT NO. 2 The Unit operated at essentially full power for the entire period.

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r REFUELING INFORMATION DOCKET NO. : 50-311 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: July 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month June 1986

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: OCTOBER 4, 1986

3. Scheduled date for restart following refueling: November 26, 1986

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

YES NO 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 considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 140

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

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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, Now l~wy 09038 Salem Generating Station July 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 June 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 ,

Y . -

J. . ZQpko, J .

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.R9 j

The Energy People IE .W yd 25 mr. iiiw