ML20214B213

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Monthly Operating Rept for Oct 1986
ML20214B213
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/31/1986
From: White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8611200382
Download: ML20214B213 (20)
v • d • e


Text

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AVERAGE DAILY UNI'2 POWER LEVEL Docket No. 50-311

Unit Name Salem # 2 Date November 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month October 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 642 17 0 2 631 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 Pg. 8.1-7 R1 Y,

8611200382 861031 PDR ADOCK 05000311 R PDR .

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

1. Unit Name Salem No. 2 Notes
2. Reporting Period October 1986
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) ITTE
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 This Month Year to Date Cumulative
11. Hours in Reporting Period 745 7296 44281
12. No. of Hrs. Reactor was Critical 47.88 5323.5 25649.4
13. Reactor Reserve Shutdown Hrs. 0 0 0 i 14. Hours Generator On-Line 47.88 5247.5 24783.9 l 15. Unit Reserve Shutdown Hours 0 0 0 j 16. Gross Thermal Energy Generated l (;MWH) 110662 6105990 25682470
17. Gross Elec. Energy Generated (MWH) 32450 5510130 25086610
18. Net Elec. Energy Generated (MWH) 23832 5247776 23782620
19. Unit Service Factor 6.4 71.9 56.0 l 20. Unit Availability Factor 6.4- 71.9 56.0 l 21. Unit Capacity Factor l (using MDC Net) 2.9 65.0- 48.6
22. Unit. Capacity Factor (using DER Net) 2.9 64.5 48.2
23. Unit Forced Outage Rate 0 19.2 35 l 24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A i

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

12/10/86

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 8-1-7.R2 i

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH OCTOBER 1986 Unit Name salem rio. 2 Date November 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 Station Service Transformer Station 532 0930 F 11.6 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 536 10-01 F 9.0 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 540 10-01 F 17.1 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 542 10-02 F 6.7 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 544 10-02 F 13.9 B 5 ----

EG TRANSF Power Auxiliary Nuclear Normal 546 10-02 S 697.1 C 1 ----

ZZ ZZZZZ Refueling 1 2 Reason 3 Method 4 Exhibit G S 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)

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH OCTOBER 1986 UNIT NAME: Salem 2 DATE: November 10, 1986 COMPLETED BY: L. Miller TELEPHONE: 609/339-4497

  • DCR NO. PRINCIPAL SYSTEM SUBJECT 2EC-1532 Post Accident Sampling Install redundant waste System gas oxygen analysis capability.

2EC-1615 Reactor Coolant Provide an insulation box System around the safety valve loop seals by modifying the pressurizer insulation.

Install additional supports on the safety valve discharge piping on the safety valve discharge piping and modify supports as required.

  • Design Change Request l

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.A e MAJOR PLANT MODIFICATIONS DOCKET NO: 50-311 REPORT MONTH - OCTOBER 1986 UNIT NAME: SALEM 2 DATE: November 10,1986 COMPLETED BY: L. Miller TELEPHONE: (609)339-4497

  • DCR SAFETY EVALUATION 10 CFR 50.59 2EC-1532 This design change does not affect the function of any system or component required to safely shutdown the Unit nor does it affect the ability to maintain the Unit in a shutdown condition.

This design change enhances the oxygen analysis capability of the Waste Gas System. This modification does not alter any plant process or discharge. No unreviewed safety or invironmental questions are involved.

! 2EC-1615 The temperature indications are not being used as a basis for any control function. There is no impact on any station operating methods or safety related systems. This modification does not alter any plant process or discharge. No unreviewed safety or environmental questions are involved.

  • Design Change Request l

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8501120154 2 21CCl4 RELIEF VALVE FAILURE DESCRIPTION: PERFORM LIFT SET TEST ON RELIEF VALVE 21CC14. TEST REQUIRED DUE TO FAILURE ON 2ND REFUELING OUTAGE PER DISPOSITION OF DR # MT-85-006.

CORRECTIVE ACTION: FOR 3RD REFUELING OUTAGE - PRETESTED FOUND LEAKING BY DISASSEMBLED AND FOUND LEAKING BY LAPPED DISC AND NOZZLE, RETESTED & SET TO PROPER SET PRESSURE.

8501120227

) 2 22CCl4 RELIEF VALVE FAILURE DESCRIPTION: PERFORM LIFT SET TEST ON RELIEF VALVE 22CC14. TEST REQUIRED DUE TO FAILURE ON THE 2ND REFUELING OUTAGE PER DISPOSITION DR # MT-85-007.

CORRECTIVE ACTION: FOR 3RD REFUELING OUTAGE - PRETESTED VALVE, VALVE LEAKED BY DISASSEMBLED VALVE AND LAPPED DISC AND NOZZLE, RETESTED AND SET TO PROPER SET PRESSURE, PUT VALVE BACK IN SYSTEM.

8501120545 2 2RH3 RELIEF VALVE FAILURE DESCRIPTION: PERFORM LIFT SET TEST ON RELIEF VALVE 2RH3. TEST REQUIRED DUE TO FAILURE ON THE 2ND REFUELING OUTAGE PER DISPOSITION OF DR # MT-85-008.

CORRECTIVE ACTION: FOR 3RD REFUELING OUTAGE - PRETESTED VALVE, FOUND '

VALVE LEAKING BY DISASSEMBLED VALVE, INSPECTED AND LAPPED NOZZLE AND DISC REASSEMBLED, TESTED AND SET TO PROPER SET PRESSURE.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8610210651 2 MOTOR FAILURE DESCRIPTION: WHILE PUMP WAS INSERVICE, MCTOR SMOKED AND SEIZED.

PUMP IS COOL AND SUCTION LINES ARE COOL. CANNOT TURN MOTOR / PUMP BY HAND. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REMOVED PANTLEG WASHER PROM IMPELLER AREA AND REASSEMBLED.

8610150500 2 2SJ4 MOTOR OPERATOR FAILURE DESCRIPTION: REWORK 2SJ4 LIMITORQUE OPERATOR IN ACCORDANCE WITH DEFICIENCY REPORT SMD IE-86-309.

CORRECTIVE ACTION: REPLACED SPRING PACKING IN ACCORDANCE WITH ABOVE DR, TESTED VALVE IAW M3L-1 PROC VALVE SAT.

8610141616 2 UNIT 2 REACTOR HEAD PAILURE DESCRIPTION: INSPECT UNIT 2 REACTOR HEAD FOR POSSIBLE DAMAGE PER DR SMD-M86-0475.

CORRECTIVE ACTION: INSPECTED REACTOR VESSEL HEAD FLANGE VISUALLY WHILE IT WAS SUSPENDED WITH POLAR CRANE APPROX 12" ABOVE STAND IAW DR SMD ,86-0474, INSPECTION WAS SAT, NO VISUAL SIGNS OF DAMAGE, FOUND O-RING SEALING SURFACE AND FLANGE SURFACE FREE OF DEFECTS.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8610130045 2 UNIT 2 RING DUCT FAILURE DESCRIPTION: PERFORM INSPECTION OF FAN COIL RING DUCT PER ENGINEERING RECOMMENDATIONS.

CORRECTIVE ACTION: INSPECTED RING DUCT AND BACK DRAFT DAMPERS, FOUND EVERYTHING IN GOOD CONDITION AND OPERATING NORMALLY.

NO ENLONGATION OF CRACKS THAT HAD BEEN REPAIRED INSIDE RING DUCT.

8610091201 2 HYDRAULIC SNUBBER FAILURE DESCRIPTION: HYDRAULIC SNUBBER S/N 90057-18A FAILED FUNCTIONAL TEST. (SEE WORK ORDER 86-09-04-0887) REPLACE WITH SPARE STEAM GENERATOR SNUBBER S/N 90057-31A/B PER PROCEDURE M9-IYP-74T.

CORRECTIVE ACTION: REMOVED FAILED HYDRAULIC SNUBBER S/N 90057-18A INSTALLED TESTED (SEE W.I. 8610090914) HYDRAULIC SNUBBER S/N 90057-31A/B.

8610091023 2 MECHANICAL SNUBBER FAILURE DESCRIPTION: FUNCTIONALLY TEST MECHANICAL SNUBBER IN ACCORDANCE WITH THE FOLLOWING: 1) REMOVE SNUBBER TO BE TESTED

2) REPLACE REMOVED SNUBBER WITH THE SAME SIZE SNUBBER. 3) FUNCTIONALLY TEST REMOVED SNUBBER.

CORRECTIVE ACTION: FUNCTIONAL TEST PERFORMED 10/13/86. TEST RESULTS

. UNSATISFACTORY. SNUBDER SHOWS EXCESSIVE BINDING IN DRAG TEST. (EXCEEDS ACCEPTANCE CRITERIA)

REPLACED IN KIND INSTALLED S/N 36715.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8610090973 2 2R12B FAILURE DESCRIPTION: FAILED, INITIATED CONT. VENT ISOLATION.

CORRECTIVE ACTION: FOUND BAD CONTROLLER REPLACED WITH CONTROLLER SN 268.

PERFORMED CHANNEL FUNCTION PROCEDURE 2IC-4.2.017 RESULTS SAT.  ;

8610080579 2 HYDRAULIC SNUBBER FAILURE DESCRIPTION: THE PISTON TO ROD EYE THREADS ARE GALLED ON HYDRAULIC SNUBBER MS-SN-24 S/N .010. PLEASE REPAIR THREADS.

(SEE DR MT86-124)

CORRECTIVE ACTION: PISTON TO ROD EYE THREADS WERE REPAIRED AND A VISUAL INSPECTION PERFORMED ON 10/10/86.

8610080501 2 22 SW PUMP FAILURE DESCRIPTION: REPLACE #22 SERVICE WATER PUMP.

CORRECTIVE ACTION: REPLACED PUMP AND REPLACED FLEX HOSE TO STUFFING BOX.

8610070522 2 21SW305 FAILURE DESCRIPTION: REMOVE AND REINSTALL 21SW305 AIR OPERATOR.

CORRECTIVE ACTION: MAINT WO 8610070514 - FOUND AIR ACTUATOR INSTALLED.

VALVE END BELL NOT INSTALLED. FOUND THE POSITIONER CASE DAMAGED. REPLACED POSITIONER CASE WITH A

. NEW UNIT FROM STOCK. REPLACED ALL PARTS FROM OLD POSITIONER AND INSTALLED AND CALIBRATED.

SALEM UNIT 2 WO NO UNIT EOUIPMENT IDENTIFICATION 8610010783 2 RMS FAILURE DESCRIPTION: 2R12B IS FAILED. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: RESET CHANNEL (CHANNEL WAS FAILED BECAUSE OF BUS SWAP)

VERIFIED SETPOINTS AS PER PAGE 17 OF PROCEDURE 2IC-4.1.017.

8609290085 2 2R16 FAILURE DESCRIPTION: THE CHANNEL IS NOT INDICATING PROPERLY. IT IS INTERMITTANTLY GOING INTO AND OUT OF WARNING.

PLEASE RESTORE.

CORRECTIVE ACTION: COPIED CHARTS FOR 2R16, 2R41A, 2R41C AS WASTE GAS COMPRESSOR HAS A SEAL LEAK. WHEN COMPRESSOR IS OUT OF SERVICE, THE WARNING CLEARS FOR 2R16 AND READINGS ALSO DECREASES ON 2R41A, AND 2R41C.

8609200370 2 2A DIESEL FAILURE DESCRIPTION: 2A DIESEL HAS A EXHAUST LEAK, WHICH IS GETTING WORSE.

THE EXHAUST FUMES ARE LINGERING IN THE ROOM. PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED GASKETS ON EXHAUST LINE WHICH WAS FIXED WITH A WELD REPAIR WO 8607231154.

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SALEM UNIT 2 1 '

WO NO UNIT EQUIPMENT IDENTIFICATION j 8607301446 2 21 S/G "J" NOZZLE EXAM t

FAILURE DESCRIPTION: PERFORM AN UPPER INTERNAL AND "J" NOZZLE EXAM INSIDE 21 STEAM GENERATOR.

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CORRECTIVE ACTION: J-NOZZLE EXAM AND UPPER INTERNALS EXAMS WERE COMPLETED AND WERE SATISFACTORY. TEN (10) SAMPLES 3 3 IF THE J-NOZZLES WERE TAKEN AND SENT TO WESTINGHOUSE -

j FOR EVALUATION.

i l 8607291271 j 2 DEBRIS SEARCH 24 S/G I FAILURE DESCRIPTION: PERFORM ANNUAL DEBRIS SEARCH IN 24 STEAM GENERATOR.

! CORRECTIVE ACTION: REVIEW OF FOSAR TAPE REVEALED FIVE PIECES OF SLAG l TYPE MATERIAL ALL OF WHICH WERE DETERMINED TO BE l LESS THAN .405" IN DIAMETER. THREE PIECES WERE -

REMOVED. TWO PIECES WERE IN A LOCATION WHERE I

RETRIEVAL WAS NOT FEASIBLE. GEN COMPLETE 10-26-86.  !

j 8607290762 i i 2 DEBRIS SEARCH 21 S/G

) FAILURE DESCRIPTION: PERFORM ANNUAL DEBRIS SEARCH IN 21 STEAM GENERATOR.

1 l CORRECTIVE ACTION: DEBRIS SEARCH REVEALED ONE SMALL PIECE OF SLAG TYPE l MATERIAL WHICH WAS REMOVED AND A 12" TUBE APPROX.

1/4" DIAMETER WHICH WAS ACCIDENTLY DROPPED IN  !

DURING SLUDGE LANCE WHICH WAS ALSO REMOVED. GEN.

1 WAS SIGNED OFF COMPLETED ON 10-25-86.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8607242245 2 21 THROUGH 26 SERVICE WATER PUMP BAYS FAILURE DESCRIPTION: SILT LEVEL INSPECTION. INSPECT 21 THROUGH 26 PUMP BAY SILT LEVELS. DIVING CONTRACTOR TO BE ARRANGED BY SENIOR MAINTENANCE SUPERVISOR.

CORRECTIVE ACTION: PERFORMED SILT INSPECTION OF 21-26SW BAYS IAW M11J, REPORT TO BE FORWARDED TO M. COCKING.

8607231154 2 DG 21 DIESEL ENGINE ,

FAILURE DESCRIPTION: PERFORM FOUR REFUELING MAINTENANCE PER PROCEDURE (DIESEL AND TURBO)

CORRECTIVE ACTION: REPLACED EXCHANGER GASKETS AROUND TURBO EXP JOINTS.

REMOVED BROKEN BOILTS, PERFORMED CAM SHAFT 4 HOUR READING, WELDED EXH PIPING.

8607231332 2 2 ABS 008 FAILURE DESCRIPTION: CLEAN DAMPER AND LINKAGE. CHECK BOLT AND SCREW TIGHTNESS. MANUALLY OPERATE DAMPER TO CHECK FOR FREE MOVEMENT.

CORRECTIVE ACTION: CLEANED AND LUBED DAMPER. MANUALLY OPERATED DAMPER - SAT.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8607173391 2 22 RCP FAILURE DESCRIPTION: CHANGE SEALS IN 22 REACTOR COOLANT PUMP.

CORRECTIVE ACTION: PROCEDURE PSE-PMS-Pl.60 REV. 2 COMPELTE. REPORT FILED FOR HISTORY UNDER ABOVE # PROCEDURE.

8607173405 2 24 RCP FAILURE DESCRIPTION: CHANGE SEALS IN 24 REACTOR COOLANT PUMP.

CORRECTIVE ACTION: PROCEDURE PSE-FMS-Pl.60 REV. 2 COMPELTE. REPORT FILED FOR HISTORY UNDER ABOVE # PROCEDURE.

8607090852 2 21 CSS LIFT SET TEST FAILURE DESCRIPTION: PERFORM LIFT SET TEST ON VALVE 21 CSS DURING 3RD REFUELING OUTAGE.

CORRECTIVE ACTION: PRETESTED VALVE, VALVE FOUND LEAKING BY DISASSEMBLED VALVE, LAPED NOZZLE AND DISC, RETESTED AND SET TO PROPER SET PRESSURE. RETURNED VALVE TO SYSTEM.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8609040887 2 HYDRAULIC SNUBBER FAILURE DESCRIPTION: PERFORM FUNCTIONAL TEST ON STEAM GENERATOR HYDRAULIC SNUBBER S/N 90057-18A. SNUBBER IS CONNECTED TO THE "NW" CORNER OF #23 STEAM GENERATOR. (FAILED SNUBBER)

CORRECTIVE ACTION: FUNCTIONAL TEST PERFORMED 10/7/86. TEST RESULTS UNSATISFACTORY. BLEED RATE IN TENSION EXCEEDED THE ACCEPTANCE CRITERIA. WO 8610091201 WRITTEN TO REPLACE FAILED SNUBBER. RETEST PERFORMED 10/11/86 -

SATISFACTORY.

8609040186 2 MECHANICAL SNUBBER FAILURE DESCRIPTION: FUNCTIONALLY TEST MECHANICAL SNUBBER IN ACCORDANCE WITH THE FOLLOWING: 1) REMOVE SNUBBER TO BE TESTED

2) REPLACE REMOVED SNUBBER WITH THE SAME SIZE SNUBBER 3) FUNCTIONALLY TEST REMOVED SNUBBER AND REFURBISH IF NECESSARY. (FIRST SAMPLE)

CORRECTIVE ACTION: WHEN SNUBBER WAS RECEIVED FOR TEST IT WOULD NOT HAND STROKE. THE FUNCTIONAL TEST WAS NOT ATTEMPTED TO AVOID FURTHER DAMAGE TO THE FROZEN SNUBBER. TEST RESULTS UNSATISFACTORY.

8608220113 2 CHARGING PUMP FAILURE DESCRIPTION: THERE IS A BAD OIL LEAK ON THE MOTOR SIDE OF THE SPEED INCREASER ON #21 CHARGING PUMP. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REPLACED GASKETS ON BEARING CAPS.

SALEM UNIT 2

$ WO NO UNIT EQUIPMENT IDENTIFICATION j

8607090861 2 22CS5 LIFT SET TEST

! FAILURE DESCRIPTION: PERFORM LIFT SET TEST ON VALVE 22 CSS DURING 3RD l REFUELING OUTAGE.

CORRECTIVE ACTION: PRETESTED VALVE, VALVE FOUND LEAKING BY DISASSEMBLED, LAPPED NOZZLE AND DISC, RETESTED AND SET TO PROPER

> SET PRESSURE. RETURNED VALVS TO SYSTEM.

i 8607010301 i 2 2B VITAL BUS FAILURE DESCRIPTION: BREAKER FAILURE. RELAY DEPARTMENT TO MAINTAIN 2B i VITAL BUS BREAKER FAILURE RELAYS.

l CORRECTIVE ACTION: INSTALLED NEW STEADY. BEARING. REPACKED PUMP.

8604150013 2 2A DIESEL

FAILURE DESCRIPTION: WHEN OPERATING ABOVE 2000 KW, THE DIESEL IS CREATING  ;

A CONSISTANT HIGH PITCH NOISE FROM THE TURBOCHARGER.

PLEASE INVESTIGATE AND REPAIR.

! CORRECTIVE ACTION: REPLACED BROKEN BOLTS AND GASKETS ON TURBO EXHAUST JOINT.

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SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8602280459 2 2B VITAL 230 VOLT TRANSFORMER FAILURE DESCRIPTION: 2B VITAL 230 VOLT TRANSFORMER / CAL TEMP INDICATOR.

VERIFY OUTPUTS FUNCTION AS REQUIRED. VERIFY THE DEVICE GIVES A REASONABLE READING WHEN RETURNED TO SERVICE. DOCUMENT INSERVICE READING ON REVERSE SIDE.

CORRECTIVE ACTION: CALIBRATED TEMPERATURE INDICATION AND SET TEMP SWITCHES.

8602101341 2 23SJ54 LIMITORQUE FAILURE DESCRIPTION: REPACK WITH CHESTERTON. DWG 205334 SHT 4 (E-7)

CORRECTIVE ACTION: REMOVED ALL PACKING LOWER LANTERN RING TO BOTTOM OF STUFFING BOX, INSTALLED 1 SET OF CARBON BUSHING, INSTALLED 6 PIECES OF PACKING, TORQUED TO 86 FT.

ONLY 2 PARALLEL 4 SERIES FIT, CLEANED AREA.

8601270191 2 24 RCP THREE WAY VALVE FAILURE DESCRIPTION: LEAKING AT A RATE OF APPROX. 4 DROPS MINUTE.

REPAIR LEAK PRIOR TO OPERATION OF PUMP FOR FILL AND VENTING OF RCS.

CORRECTIVE ACTION: TOOK 3 WAY VALVE FROM 21 MOTOR AND INSTALLED ON 24 MOTOR, LEAKING VALVE PLACED ON 21 MOTOR.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8601080138 2 INCORE THIMBLE TUBES FAILURE DESCRIPTION: CLEAN THE SALEM UNIT 2 FLUX THIMBLES DURING THE 3RD REFUELING OF SALEM UNIT 2 PRIOR TO THE EDDY CURRENT INSPECTION TEST.

CORRECTIVE ACTION: FLUX THIMBLES CLEANED TO WESTINGHOUSE PROCEDURE MP2.2.1 PNJ-2 0099171481 2 REACTOR TRIP BREAKER FAILURE DESCRIPTION: ASSIST WESTINGHOUSE FIELD REP IN VERIFYING BREAKER AND CUBICLE ALIGNMENT. REPLACE DAMAGED CONTACT #6 AND MAKE CUBICLE OR BREAKER ALIGNMENT ADJUSTMENTS IF REQUIRED.

CORRECTIVE ACTION: REPLACED #6 SECONDARY CONTACT, ADJUST LEFT SUPPORT RAIL IAW WESTINGHOUSE REP RECOMMENDATION RACKED BREAKER IN AND OUT 5 TIMES TO ENSURE THAT THE SUPPORT RAIL ALIGNMENT WAS CORRECT AND PROPER MATING ON THE SECONDARY CONTACT WAS PRESENT.

0099181355 2 R46A FAILURE DESCRIPTION: MONITOR FAILED. PLEASE REPAIR.

CORRECTIVE ACTION: FOUND DETECTOR SHORTED DUE TO MOISTURE, USED PROCEDURE 2IC-4.1.078 TO CALIBRATE DRAWER. USED 2IC-4.1.007 TO CALIBRATE A NEW DETECTOR.

RECALIBRATED USING PROCEDURE 2IC-2.4.007.

SALEM GENERATING. STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 OCTOBER 1986 The Unit began the period operating at sixty five percent (65%) power due to problems with No. 21 Steam Generator Feed Pump (SGFP). No. 21 SGFP was returned to service on October 1, 1986, and p>wer was increased to seventy percent (70%). Power was further increased to seventy six percent (76%) early on October 2, 1986, after No. 21 Heater Drain Pump was placed in service. Power was reduced later the same day due to high flow experienced on Nos. 22 and 23 Condensate Pumps. On October 2, 1986 at 2353 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.953165e-4 months <br />, Unit 2 was removed from service in preparation to commence the Third Refueling Outage. On October 4, 1986, a " Shutdown from Outside of the Control Room" was successfully performed. The test proved that the Reactor Coolant System cooldown could be controlled by the Operators from outside of the Control Room. The Unit entered Mode 5 (Cold Shutdown) on October 5, 1986. On October 11, 1986, the Unit entered Mode 6, and the Reactor Vessel Head was removed on October 14, 1986. A problem encountered with the Reactor Cavity water clarity caused a thirty six (36) hour delay in commencing the fuel movement. Fuel unload commenced on October 17, 1986 and was completed on October 21, 1986.

The fuel inspection was completed with the following results:

Three (3) elements have fuel rod leakage.

a. One (1) of these also has grid strap damage.

One (1) element has grid strap damage only.

Replacement elements of similar burnup will be substituted for this core load and the damaged elements will be reconstituted for use in Cycle 5. Resins were discovered on the floor of the refueling cavity and have since been removed. The source of the resins has not been identified and the investigation continues. The outage continues on schedule.

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. _ = _ . . - _ . - . _ - _ _ . . - . - - _ - . - _ - . -

P REFUELING INFORMATION i DOCKET NO.: 50-311 COMPLETED BY: L.K. Miller UNIT NAME: Salem 2 DATE: November 10, 1986 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month October 1986 l 1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: October 3, 1986
  • i 3. Scheduled date for restart following refueling:

l November 26, 1986*

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

} YES NO X  :

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

YES NO X If no, when is it scheduled? November 1986

5. Scheduled date (s) for submitting proposed licensing action:

None required l 6. Important licensing considerations associated with refueling:

NONE i

7. Number of Fuel Assemblies:

A) Incore 0 f B) In Spent Fuel Storage 417

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170 l 9. Date of last refueling that can be discharged i to spent fuel pool assuming the present j licensed capacity: March 2003 r

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  • Refueling currently in progress l

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O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Sta:;c" November 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 October 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, tA 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 cs'P,p The Energy People 2s mww w

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