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Monthly Operating Rept for Jul 1985
	ML20134D139
Person / Time
Site:	Salem
Issue date:	07/31/1985
From:	Ronafalvy J, Zupko J; Public Service Enterprise Group
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NUDOCS 8508190109
	Download: ML20134D139 (16)
	v • d • e

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OPERATING DATA REPORT Docket No. 50-311 Date August 10,1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period July 1985

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) 114 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 5087 33312

12. No. of Hrs. Reactor was Critical 501.7 2221.4 17316

13. Reactor Reserve Shutdown Hrs. 0 0 3533.6

14. Hours Generator On-Line 468 1959.2 16571.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1515847 6001904 49728940

17. Gross Elec. Energy Generated (bnm) 497780 1967980 16245630

18. Net Elec. Energy Generated (MWH) 469089 1833560 15351396

19. Unit Service Factor 62.9 38.5 49.7 l

20. Unit Availability Factor 62.9 38.5 49.7

21. Unit Capacity Factor (using MDC Net) 57.0 32.6 41.7

22. Unit Capacity Factor j (using DER Net) 56.5 32.3 41.3 l 23. Unit Forced Outage Rate 37.2 58.7 40.8 l 24. Shutdowns scheduled over next 6 nonths (type, date and duration of each)

N/A

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 G508190109 050731 '7g 7i PDR ADOCK 05000311 #

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- AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date August 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month July 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 1100 2 0 18 1087 3 0 19 1075 4 0 20 332 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 539 9 84 1 25 792 10 1086 26 1102 11 1101 27 1080 12 1073 28 1096 13 1004 29 1089 14 1111 30 1090 15 1057 31 1076 16 1079 Pg. 8.1-7 R1

f UNIT SHUTDOWN AND POWER REDUCTIONS Docket No..50-311 REPORT MONTH July 1985 Unit Name Salem No.2 -

Date August 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 Nuclear Nonpower Operated Safety Valves Reactor 85-130 6-28 F 219.0 A 4 -

CJ VALVEX Coolant Nuclear Other Steam 85-132 7-07 F 25.6 A 3 -

CC GENERA Generator Problems Reheat Stop 85-138 7-09 F 0.1 B 5 -

CD VALVEX Valves Turbine Reheat Stop 85-146 7-12 F 1.4 B 5 -

CF VALVEX Valves Turbine Reheat Stop 85-148 7-13 F 3.4 B 5 -

CD VALVEX Valves Turbine Other Reactor 85-164 7-20 F 34.1 B 1 -

CJ VALVEX Coolant Valves Control Rod 85-166 7-21 F 31.0 A 1 -

RA CONROD Assemblies Nuclear Tanks Reactor Water 7-23 F 21.5 B 1 -

CG ACCUMU Cleanup 85-168 Control Valves 8.5-172 7-24 F 1.5 B 1 -

HB VALVEX Turbine 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 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)

F MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH JULY 1985 UNIT NAME: Salem 2 DATE: August 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

DCR NO. 10CFR 50.59 SAFETY EVALUATION 2EC-2081 The replacement of the pump requires different supports, however, the structural integrity is not being compromised. This modification does not alter any plant discharge or process and will not affect the existing plant impact. No unreviewed safety or environmental questions are involved.

2EC-2149 This design change does not involve any field work. It provides a margin of safety for the RHR heat removal requirements during a LOCA. Details of the analysis is addressed in Engineering Safety Evaluation S-C-N210-MSE-0317. No unreviewed safety or environmental questions are involved.

Design Change Request L _

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH JULY 1985 UNIT NAME: Salem 2 DATE: August 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-2081 Aux Feed Water Present B-J Aux Feed Pump No.

22 is damaged. Replacement with an equivalent pump from Ingersoll Rand is required.

2EC-2149 Component Cooling Revise the coraponent cooling flow rate to the RHR heat exchangers during cold leg recirculation from 2000 GPM to 4000 GPM per heat exchanger.

Design Change Request

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1 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099006081 SMD 2 26 SW PUMP FAILURE DESCRIPTION: HOLE IN DISCHARGE CASING.

CORRECTIVE ACTION: FABRICATED PATCH, WELDED PATCH OVER HOLE.

0099159449 SMD 2 2CV44 FAILURE DESCRIPTION: REACH ROD IS NOT CONNECTED.

CORRECTIVE ACTION: PUT KEY IN BACK IN KEYWAY. SLID THE KEY OVER THE KEY AND TIGHTENED SET SCREW.

0099164710 SIC 2 FIRST STG TURBINE PRESS FAILURE DESCRIPTION: COMPARATOR FOUND TRIPPING OUT OF SPEC. DURING CHANNEL ChLIBRATION PROCEDURE.

CORRECTIVE ACTION: REPLACED CAPACITORS C2 AND C3. ADJUSTED TO SPEC.

COMPLETED 2PD-2.2.024.

0099176653 SIC 2 22BF40 FAILURE DESCRIPTION: BLOWN DIAPHRAGM ON ACTUATOR, CORRECTIVE ACTION: TIGHTENED NUT INSIDE DIAPHRAGM HOUSING, STROKED VALVE.

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SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099177081 SIC 2 2CV179

-FAILURE DESCRIPTION: THE VALVE SWAPS TO MANUAL WHEN ADJUSTING THE INCREASE / DECREASE PUSH BUTTON.

CORRECTIVE ACTION: REPLACED 1000 MFD, 50 VDC CAP ON 2HClllC.

0099177111 SIC 2 21BF19 FAILURE DESCRIPTION: WHEN SWAPPED FROM AUTO TO MANUAL THE DEMAND SWUNG FROM 28% TO 70% AND THE VALVE JUMPED OPEN.

CORRECTIVE ACTION: CHANGED CAPACITORS C21 AND C26 ON POWER SUPPLY BOARD OF 2FC-500A.

0099177544 SIC 2 2 SA2 1RPl FAILURE DESCRIPTION: INDICATE 16 STEP LOWER THAN DEMAND.

CORRECTIVE ACTION: FOUND SIGNAL MODULE IN SPEC. BUT KEPT DRIFING DOWNWARD AT TOP VALUE. REPLACED MODULE AND CALIBRATED. RETURNED TO SERVICE.

0099177579 SIC 2 21CCHX FAILURE DESCRIPTION: 21SW122. WILL NOT WORK IN AUTO.

CORRECTIVE ACTION: CALIBRATED INDICATING CONTROLLER, FA-3891C, FOUND VALVE POSITIONER DEFECTIVE; REPLACED POSITIONER.

VERIFIED PROPER MANUAL AND AUTO OPERATION FROM CONTROLLER. RETURNED TO SERVICE.

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SALEM UNIT 2

- WO NO DEPT UNIT EQUIPMENT IDENTIFICATION O'099177587 .

SMD 2 21MS167 FAILURE DESCRIPION: ._ THE VALVE WILL NOT GO CLOSED.

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CORRECTIVE ACTION: REPLACED FAILED 3-2N/1 RELAY AND PARTIALLY SHORTED CONTACTOR COIL. OPERATED VALVE.

0099177641 .

SIC 2- 22 SGFP

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FAILURE DESCRIPTION: #22 SGFP WILL RESET LOCALLY BUT WILL NOT RESET FROM CONSOLE.

CORRECTIVE ACTION: ADJUSTED CLOSE LIMIT ON LP CONTROL VALVE.

8504101622 .-

SIC 2 S/G SAFEfY VALVE FAILURE DESCRIPTION: 21MS10 IS LEAKING QUITE A BIT OF STEAM. THE DEMAND l ON THE VALVE REMAINS AT ZERO EVEN WHEN THE VALVE IS ~

OPENED IN AUTO. _

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CORRECTIVE ACTION: REPLACED POTS R1 - R2 IN 2HC-516B. _

8504292240 SMD 2 21 CC HEAT EXCHANGER FAILURE DESCRIPTION: THE OUTLET VALVE 21 SW 127 HAS WATER COMING FROM l UNDER THE INSULATION.

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CORRECTIVE ACTION: REMOVED SPOOL PIECE AND MADE WELD REPAIR ON GASKET SURFACE.

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SALEM UNIT 2 WO NO- DEPT UNIT EQUIPMENT IDENTIFICATION 8506220041 SMD 2- 2B DIESEL LUBE OIL-STRAINER FAILURE DESCRIPTION: TWIN STRAINER LEAKS OIL FRCE BMTOM PLUG AND VENT VALVES.

CORRECTIVE ACTION: REMOVED. VENT VALVES, CLEANED THREADS AND REINSTALLED.

REMOVED PLUG, CLEANED THREADS AND REINSTALLED. __

8506220050 SMD 2 2C DIESEL LUBE OIL STRAINER FAILURE DESCRIPTION: TWIN STRAINER LEAKS OIL FROM BMTOM PLUG AND VENT l VALVES. .

CORRECTIVE ACTION: REPLACED WORN PIT COX.

8506281504 SMD 2 21SJ13 7 FAILURE DESCRIPTION: THERE IS A LEAK AT THE FLANGE OF THE FLOW METER 981.

CORRECTIVE ACTION: TIGHTEN UP ON FLANGE.

8506300151 SIC 2 2CVS FAILURE DESCRIPTION: VALVE DOES NOT GO CLOSED WHEN ALL CHARGING PUMPS ARE TAKEN OUT OF SERVICE. PLEASE CHECK AND REPAIR.

CORRECTIVE ACTION: REPLACED AUX. RELAY 52Z3. FOUND RESET COIL OPEN ON OLD RELAY.

8507010997 * ~ - -

SMD 2 26 SW PUMP FAILURE DESCRIPTION: PLEASE REPAIR PACKING. .

CORRECTIVE ACTION: REPACKED PUMP.

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SALEM UNIT 2 WO NO DEPT- UNIT EQUIPMENT IDENTIFICATION 8507060366 SIC 2 23 ACCUM DRAIN FAILURE DESCRIPTION: PLEASE REPAIR THE AIR REGULATOR TO THIS VALVE.

REGULATOR IS LEAKING VERY BADLY.

CORRECTIVE ACTION: REPLACED REGULATOR SEAL WITH MISC. SHOP SPARE.

8507100651 SMD 2 2B DIESEL j

FAILURE. DESCRIPTION: 3L CYLINDER FUEL INJECTION TUBE HOLDER LEFT STUD IS BROKEN OFF. l CORRECTIVE ACTION: REMOVED STUD, RETAPED HOLE ADD NEW STUD AS PER ,

D.C.R. #MD853582.

8507110011 SMD 2 2B DIESEL GENERATOR j FAILURE DESCRIPTION: THERE IS A BAD FUEL OIL LEAK ON CYLINDER 3L.

CORRECTIVE ACTION: TIGHTENED LOOSE FITTING.

8507130461 SIC 2 2R13A FAILURE DESCRIPTION: CHANNEL IS FAILED.

CORRECTIVE ACTION: POWERED CHANNEL DOWN AND RESEATED PROMS. CLEARED RAM AND REENTERED AND SETPOINTS.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8507011047 SIC 2 21 S.I. PUMP FAILURE DESCRIPTION: THE THRUST BEARING TEMPERATURE INDICATION ON THE BORIC AND P 250 FOR #21 SI PUMP ARE SHOWING FAILED.

CORRECTIVE ACTION: REPLACED BROKEN TC WITH A NEW CALIBRATED ONE AS PER PROCEDURE 14.2.012.

8507050051 SIC 2 PASS SAMPLE VALVE 1

FAILURE DESCRIPTION: VALVE STROKES, NO LIMIT INDICATION.

I CORRECTIVE ACTION: LIMIT SWITCH ARMS WERE MOVED BACK INTO CORRECT POSITION. HAD CHEMISTRY STROKE VALVE AT PASS ROOM.

OPEN AND CLOSED INDICATION OKAY.

I 8507060056 SIC 2 21 RHR HEAT EXCHANGE CCW FLOW FAILURE DESCRIPTION: 21 RHR HEAT EXCHANGER COMPONENT COOLING FLOW INDICATION ON CONTROL CONSOLE IS CURRENTLY INDICATING 2000 GPM WITH 21CC16 SHUT.

CORRECTIVE ACTION: CALIBRATED TRANSMITTER. FLOW BROUGHT TO O INDICATION BY MANUALLY CLOSING 21CC16. VALVE CLOSED BY OPERATIONS MANUALLY SINCE IT WOULD NOT SEAT WITH PUSH BUTTON FROM CONSOLE.

8507060064 SIC 2 1D4 IRPI FAILURE DESCRIPTION: ALL RODS ON BOTTOM, ID4 INDICATES ABOUT 12 STEPS ON IRPI.

CORRECTIVE ACTION: REPLACED AMP CARD. RECALIBRATED INDICATOR 1D4 ALSO IND 1D3.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8507140181 SMD 2 2A SEC CABINET FAILURE DESCRIPTION: 2A SEC CABINET HAS BEEN CONSTANTLY ALARMING. THE ALARM CAN BE RESET, HOWEVER IT RE-ALARMS AFTER ANYWHERE FROM 3 TO 40 MINUTES. TEST #24 IS UP IN THE TEST INDICATOR WINDOW. TEST #12 ALSO CAME UP 2X.

CORRECTIVE ACTION: REPLACED FILE CARDS CHASSIS.

8507151485 SMD 2 BIT SAMPLE LINE

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FAILURE DESCRIPTION: PLEASE UNCLOG #2 BIT SAMPLE LINE BY VALVES 2SJ277 AND 2SJ278.

CORRECTIVE ACTION: UNCLOGGED SAMPLE LINE WITH DM WATER. CLOG WAS AT OPEN END OF LINE ON DISCHARGE SIDE OF VALVE.

8507160930 SMD 2 2PS 8 FAILURE DESCRIPTION: VALVE APPEARS TO BE LEAKING THROUGH PACKING.

CORRECTIVE ACTION: INVESTIGATED PROBLEM, TIGHTENED PACKING, LEAK STOPPED DISCREPANCY ON VALVE GEN. NO. VALVE TAG IS 2PR8.

8507161219 SIC 2 21 SAFETY INJECT, PUMP FAILURE DESCRIPTION: DORIC POINT 509 FAILED ON PUMP INBOARD BRG TEMPERATURE.

COMPUTER POINT READS GOOD.

CORRECTIVE ACTION: FOUND LOOSE CONNECTION IN DORIC SATALITE BANK POINT 509.

TIGHTENED CONNECTION AND RECHECKED DORIC POINT READING 90 DEGREES F.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8507210457 SIC 2 DRIVE MECHANISM FAILURE DESCRIPTION: DURING A REACTOR START-UP, CONTROL ROD 2B4 DROPPED FROM APPROXIMATELY 150 STEPS DURING ROD WITHDRAWL.

CORRECTIVE ACTION: CHECKED ROD CONTROL CABINET. FOUND STATIONARY COIL OPEN FROM FIELD FOUND PIN CONNECTOR WAS RECESSED.

PULLED PIN OUT. RECONNECTED PLUG AND VERIFIED PROPER RESISTANCE READING ON ALL COILS FROM RELAY ROOMS.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 JULY 1985 SALEM UNIT NO. 2 The Unit began the period in Mode 5. The flange leakage on Pressurizer Safety Valve 2PR-4 was repaired. Additional work completed during this forced outage included repacking various secondary valves, replacement of valve 22MS14 (Main Steam Safety Valve) and repair of minor hydrogen leakage from the Generator. On 7/6/85 #2B Diesel Generator experienced a non-valid test failure as a result of a malfunctioning field ground relay. On 7/7/85 at 1859 hours0.0215 days 0.516 hours 0.00307 weeks 7.073495e-4 months , the Unit was returned to service. At 1926 hours0.0223 days 0.535 hours 0.00318 weeks 7.32843e-4 months (the same day), the Unit tripped on No. 21 Steam Generator (S/G) Hi-Hi Level due to operator error. On 7/8/85 at 0321 hours0.00372 days 0.0892 hours 5.30754e-4 weeks 1.221405e-4 months , the Unit entered Mode 2.

At 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months the same day, with the Unit at 10% power, the Unit tripped on #23 S/G Low-Low Level as the result of an operator error.

On 7/08/85 at 1154 hours0.0134 days 0.321 hours 0.00191 weeks 4.39097e-4 months , the Unit was brought critical and at 2101 hours0.0243 days 0.584 hours 0.00347 weeks 7.994305e-4 months was brought on line.

On 7/09/85 at 2011 hours0.0233 days 0.559 hours 0.00333 weeks 7.651855e-4 months Unit load was reduced to 80% due to an Electro-Hydraulic System leak from 22E reheat stop valve. Unit load was returned to 100% at 2105 hours0.0244 days 0.585 hours 0.00348 weeks 8.009525e-4 months the same day. On 7/11/85 2B Diesel Generator experienced a valid test failure due to a fuel leak caused by a loose fitting on number 3L cylinder fuel injector. On 7/13/85 at 1102 hours0.0128 days 0.306 hours 0.00182 weeks 4.19311e-4 months , Unit load was reduced to 79% to repair a pinched gasket leak from 22E reheat stop valve. Unit load was returned to 100% at 1623 hours0.0188 days 0.451 hours 0.00268 weeks 6.175515e-4 months the same day. On 7/20/85 at 1149 hours0.0133 days 0.319 hours 0.0019 weeks 4.371945e-4 months the Unit was taken off the line to support repair of valves 2PR9 (Pre.=surizer Safety Valve Loop Seal Drain Valve) and 2PS8 (Pressurizer Instrumentation Tap) which were leaking. During the approach to criticality on 7/21/85 at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , Control Rod 2B4 dropped. Startup was terminated until the malfunction of the drive mechanism for 2B4 was determined and corrected. A faulty connector for 2B4 was repaired.

On 7/22/85 at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months Unit startup commenced. At 0531 hours0.00615 days 0.148 hours 8.779762e-4 weeks 2.020455e-4 months on 7/23/85, a controlled shutdown to Mode 3 (Hot Standby) was initiated due to the Boron Injection Tank (BIT) and the Boric Acid Storage Tank (BAT) boron concentration being below the allowable Technical Specification limit. An Unusual Event was declared as a result of not meeting the Tech. Spec. limit. Unit startup recommenced at 1929 hours0.0223 days 0.536 hours 0.00319 weeks 7.339845e-4 months the same day upon completion of returning the boron concentration to the appropriate level. On 7/24/85 at 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months , the Unit was synchronized to the grid. On 7/24/85 at 2334 hours0.027 days 0.648 hours 0.00386 weeks 8.88087e-4 months , a Turbine shutdown commenced due to an Electro-Hydraulic (EH) System leak from 24 Governor Valve. The Unit was maintained at 7% power during repair of the leak. On 7/25/85 at 0129 hours0.00149 days 0.0358 hours 2.132936e-4 weeks 4.90845e-5 months , with completion of the EH System repair, the Unit was synchronized to the grid and brought to full power where it remained for the rest of the period.

REFUELING INFORMATION DOCKET NO. : 50-311 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: August 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month July 1985

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 6, 1986

3. Scheduled date for restart following refueling: November 16, 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 I

O PSIEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1985 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 Specifications, 10 copies of the following monthly operating reports for the month of July 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 ,

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

} Enclosure 8-1-7.R4 I

The Energy People 95 2189 (20M) '1-81 w

ML20134D139

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SUMMARY

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