ML20207P898

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Monthly Operating Rept for Dec 1986
ML20207P898
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/31/1986
From: White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8701200384
Download: ML20207P898 (15)
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v AVERAGE DAILY UNIT POWER LEVEL:

Docket No. 50-311 Unit Name Salem # 2 Date Uanuary 10,1987 Completed by' Pell White Telephone 609-935-6000 Extension 4451 Month December 1986 Day. Average DailyLPower Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0- 17 0 2 0 18 0 i

. 3- 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0

  • 7 0 23 37

.8 0 24 0 9 0 25 345 l 10 0 26 436 11 0 27 657 12 0 28 133 13 0 29 265 l 14 0 30 732 15 0 31 833 16 0 Pg. 8.1-7 R1 l

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\/l 8701200384 861231

! PDR ADOCK 05000311 R PDR

OPERATING DATA REPORT .

Docket *No. 50-311 Date January 10,1987 Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period _

December 1986

3. Licensed Thermal Power (MWt) 3411 4.- Nameplate Rating (Gross MWe) IT75
5. Design Electrical Rating (Net MWe) ITT3
6. Maximum Dependable Capacity (Gross MWe)TTTY
7. Maximum Dependable Capacity (Net MWe) ITDT
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) Variable
10. Reasons for Restrictions, if any Variable power restrictions due to Station Power Transformer This Month Year to Date Cumulative
11. Hours in Reporting Period 744 8760 45745
12. No. of Hrs. Reactor was Critical 290.5 5614 25939.9
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 154.5 5402 24938.4
15. Unit Reserve Shutdown Hours 0 ~-

0 0

16. Gross Thermal Energy Generated (MWH) 326002 5836132 26008472
17. Gross Elec. Energy Generated (MWH) 90530 5600660 25177140
18. Net Elec. Energy Generated (MWH) 69945 5312561 23847405
19. Unit Service Factor 20.8 61.7 54.5
20. Unit Availability Factor 20.8 61.7 54.5
21. Unit Capacity Factor

-(using MDC Net) 8.5 54.8 47.1

22. Unit Capacity Factor (using DER Net) 8.4 54.4 46.8
23. Unit Forced Outage Rate 23.6 19.4 35.0
24. Shutdowns scheduled over next 6 months (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

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.-50-311' REPORT MONTH DECEMBER 1986 Unit Name salem No.z Date January 10,1987 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 .,

Nuclear Normal 546 10-02 S 1465.1 C 1 ----

ZZ' ZZZZZ Refueling Service Water 548 12-02 F 175.8 A 5 ----

WA PIPEXX Piping Salt Water Closed Cooling .

550 12-10 S 318.0 B 5 ----

WA HTEXCH Water Heat Exchanger Other Nuclear Reactor-Problems-552 12-23 F 22.4 B 3 ----

CC VALVEX Miscellaneous Feedwater Regulating Boiler Level 556 12-28 F 25.3 A 3 ----

CH VALVEX -Control Valve Station Service Transformer' Station 558 12-29 F 55.2 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 560 12-31 F 8.0 B 5 ----

EG TRANSF Power Auxiliary Station Service Transformer Station 562 12-31 F 2.0 B 5 ----

EG TRANSF Power Auxiliary

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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)

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH DECEMBER 1986 UNIT NAME: Salem 2 DATE: January 10, 1987 COMPLETED BY: L. Miller TELEPHONE: 609/339-4497

  • DCR NO. PRINCIPAL SYSTEM SUBJECT There were no DCRs reported completed during the period.
  • Design Change Request a

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 0099049589 2 2VC4 (OVRHD BD TANKS)

FAILURE DESCRIPTION: RESTROKE 2VC4. VALVE FAILED LEAK RATE TEST.

CORRECTIVE ACTION: REMOVED AND REPLACED OPERATOR TO REPLACE SHEARED, SHEAR-KEY STROKED VALVE AND ADJUSTED SEAT.

0099171180 2 REACTOR TRIP BREAKERS FAILURE DESCRIPTION: PERFORM REACTOR TRIP BREAKER SURVEILLANCE PROCEDURES 24 HOURS PRIOR TO START-UP, 2IC-18.1.006,2IC-18.1.007, 2IC-18.1.010, 2IC-18.1.011.

CORRECTIVE ACTION: PERFORMED 2IC-18.1.006, 18.1.007, 18.1.010 AND 18.1.011 TRIP BREAKER A UU =7 CYCLES TRIP BREAK A SHUNT = 6 CYCLES TRIP BREAK B UU = 7 CYCLES TRIP BREAKER B SHUNT = 6 CYCLES.

0099171236 2 REACTOR TRIP BREAKERS FAILURE DESCRIPTION: PERFORM BREAKER SURVEILLANCE TESTING 24 HOURS PRIOR TO START =U

P. PROCEDURE

S IC-18.1.010,18.1.011,18.1.006 AND 18.1.007.

CORRECTIVE ACTION: PERFORMED 2IC-18.1.006, 18.1.0907, 18.1.010 AND 18.1.011.

U SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 0099186985 2 START AIR RECEIVE CHECK VALVE FAILURE DESCRIPTION: 2B DIESEL GEN. STARTING AIR RECEIVE CHECK VALVE LEAK THRU. PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED SPRING AND GASKET, LAPPED PLUG TO SEAT, BLUE CHECK SAT.

8511280014 2 FCU OUTLET VALVE FAILURE DESCRIPTION: THE VALVE WAS CLOSED FROM THE' CONTROL ROOM AND WILL NOT RE-OPEN. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: ADJUSTED VALVE LINKAGE AND LIMIT-SWITCH. VERIFIED CORRECT OPERATION WITH CONTROL ROOM OPENING AND CLOSING VALVE.

8609180018 2 2A D/G LO COOLER FAILURE DESCRIPTION: THE DRAIN PLUG FOR THE LUBE OIL COOLER IS STRIPPED.

PLEASE REMOVE AND REPLACE WITH NEW PLUG. NOTIFY SHIFT SUPERVISOR PRIOR TO REMOVING PLUG.

CORRECTIVE ACTION: RETHREADED PLUG AND INSPECTED FOR BELZONA CHIPS, FOUND NONE, REASSEMBLED OIL COOLERS.

SALEM UNIT 2 i WO NO UNIT EQUIPMENT IDENTIFICATION 8609240746 4 2 2CV59

  • 6 1

i FAILURE DESCRIPTION: -WHEN THE VALVE IS OPENED UP, THE VALVE LEAKS FROM THE DIAPHRAGM AREA. THE DIAPHRAGM IS PROPERLY CUT.

! PLEASE REPAIR.

! CORRECTIVE ACTION: TIGHTENED BONNET NUTS, NO SIGN OF LEAKAGE.

8611030575 j 2 24 CFCU DAMPER FAILURE DESCRIPTION: DAMPER LINKAGE IS BROKEN, PLEASE REPAIR.

CORRECTIVE ACTION: WELDED NEW THREADED ROD ON LINKAGE ARM, INSTALLED ARM AND PAINTED.

, 8611101201 j 2 CC FLOW METER i

FAILURE DESCRIPTION: 22 RHR HX CC FLOW INDICATION IS FAILED LOW.

CORRECTIVE ACTION: CALIBRATED INDICATOR HAD CONTROL ROOM INCREASE FLOW TO 22 CC HX TO PROVE OPERABILITY. '

8611110030

, 2 MSIV HYDRAULIC SNUBBER FAILURE DESCRIPTION
REPLACE THE O-RING BETWEEN THE 90 DEGREE ELBOW FROM THE MAKE-UP RESERVOIR SUPPLY PIPING TO THE CONTROL VALVE ASSEMBLY. VISUALLY INSPECT FOR LEAKS 1 AFTER RESERVOIR HAS BEEN FILLED.

CORRECTIVE ACTION:. INSTALLED NEW 0-RING BETWEEN THE 90 DEGREE ELBOW l FROM THE MAKE-UP' RESERVOIR SUPPLY PIPING TO THE l CONTROL VALVE ASSEMBLY, VISUALLY INSPECTED, i REVEALED NO LEAKS.

i SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION-8611160134 2 23 CFCU SW ISOLATION.

VALVE FAILURE DESCRIPTION: VALVE DOES NOT STROKE FREELY, AIR MUST:BE FAILED TO KEEP VALVE OPEN. PLEASE REPAIR.

1 CORRECTIVE ACTION: CHECKED' VALVE STROKE, NOT. STARTING TO CLOSE UNTIL 9 PSI. SET POSITIONER 3-15 PSI. FOUND A/M STATION IN SEAL POSITION,. SHIFTED TO MANUAL AND STROKED-VALVE FROM STATION.- REPAIRED DAMAGED TUBING IN REDUNDANT AIR PANEL. '

8611170547 2 CS P1 .7M COOLER CONTTVau?-R

FAIL'I'i ;15CRIPTION
VALVE IS STUCK HALFWAY OPEN, PLEASE'RE'P AIR.. VALVE 4

NEEDED TO PERFORM 4.0.5V.

CORRECTIVE ACTION: REMOVED VALVE BONNET, STEM WAS NOT BENT, REMOVED DEBRIS.FROM PIPING, REPACKED' VALVE WITH CHESTERTON-4 PACKING AND REINSTALLED VALVE, VALVE'IN OPEN-l POSITION.

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T SALEM UNIT 2 *. .

WO NO UNIT EQUIPMENT IDENTIFICATION

@611300157 2 22 CC.HX CONTROL FAILURE DESCRIPTION: THE 22SW127 WILL NOT CLOSE ALL THE WAY. IS STILL OPEN 1/8 OF THE WAY. PLEASE VERIFY THE STROKE IS CORRECT.

1 CORRECTIVE ACTION: FOUND VALVE NOT TRAVELING TO FULL CLOSED POSITION.

REMOVED VANE ARM OFF SHAFT AND SET BACK OF TOOTH TO GET FULL STROKE. STROKED VALVE THRU POSITIONER ,

TO VERIFY PROPER OPERATION.

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l j 8612010012 2 CONT IODINE MONITOR j FAILURE DESCRIPTION: THE CHANNEL IS INITIATING CONTAINMENT VENTILATION ISOLATION ALTHOUGH INDICATING NO PROBLEM. PLEASE INVESTIGATE. i CORRECTIVE ACTION: PERFORMED CHANNEL CALIBRATION CHECK PROCEDURE 2IC-4.5.017 UNDER IO #405921.M(D W.O. #86-12-09-051-2 PERFORMED CHANNEL CA

L. PROCEDURE

2IC-4.1.017'UNDER IO #405887 AND W.O. #86-09-15-097-6, PERFORMED CHANNEL l FUNCTIONAL PROCEDURE 2PD-4.2.017 UNDER IO #405885 W.O.

J #8612100437.

j 8612040876 2 2B 125 VDC GROUND 4

FATLURE DESCRIPTION: 2B 125 VDC BATTERY BUS HAS A GROUND INDICATION.

4 THE GROOUND HAS BEEN ISOLATED TO' BREAKER 2BDC2AX29.

22 CFCU' FILTER DAMPERS, PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: FOUND WATER IN CONDUIT ON 22 CFCU DRAIN WATER DRIED OUT.

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SALEM UNIT 2 1

WO NO UNIT EQUIPMENT IDENTIFICATION 8612070228 2 2CV8 LETDOWN FROM RHR FAILURE DESCRIPTION: VALVE LEAKS THRU APPROXIMATELY 80 : GRPM WITH CV18 WIDE OPEN AND SYSTEM PRESSURE AT 3009. PLEASE CHECK STROKE ON VALVE AND VERIFY IT IS SEATING PROPERLY.

CORRECTIVE ACTION: READJUSTED BAILEY POSITIONER ON VALVE FOR PROPER OPERATION.- STROKED VALVE. .

8612110068 -

2 21 FUEL OIL TRANSFER PUMP FAILURE DESCRIPTION: 21 FUEL OIL TRANSFER PUMP IS LEAKING FROM THE PUMP CASING. PLEASE REPAIR.

CORRECTIVE ACTION: TIGHTENED CASING.

8612120063 2 22 RCP SEAL WATER TEMP FAILURE DESCRIPTION: INLET TEMPERATURE INDICATION FOR SEAL WATER TO 22 RCP IS INDICATING ABNORMALLY LOW ON THE CONSOLE.

COMPUTER INDICATION IS NORMAL. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: VERIFIED THERMOCOUPLE READING LOW IN RACK WITH TEMP FLUKE. FOUND THERMOCOUPLE FOR 63 DEG. F.

BEZEL INDICATOR SWAPPED. REVERSED LEADS'AND VERIFIED PROPER INDICATION. BEZEL 79 DEG. F.

COMPUTER 81 DEG F.

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 8612140099 2 22 RCP SEAL OUTLET TC FAILURE DESCRIPTION: OUTLET TC IS READING LOWER THAN OTHER PUMPS. VERY.

SMALL TEMP CHANGE FROM INLET TO OUTLET. PLEASE INVESTIGATE.

CORRECTIVE ACTION: LIFTED LEADS IN RELAY ROOM AND VERIFIED SIGNAL FROM FIELD 2000 THE SAME AS INDICATED.ON CONTROL ROOM .

AND COMPUTER. CALIBRATED NEW THERMOCOUPLE.

VERIFIED PROPER LEAD CONNECTION FOUND T/C NOT COhPLETELY IN WELL BOTTOMED T/C IN WELL AND -

VERIFIED PROPER.

8612190843 2 TURBINE TRIP INDICATION FAILURE DESCRIPTION: THE OVERHEAD FOR MANUAL TURBINE TRIP INITIATED IS UP WITH THE TURBINE LATCHED. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: CLEANED POOR CONNECTION IN BEZEL PB, REPLACED 3 RELAYS WHICH WERE IN POOR PHYSICAL CONDITION.

8612200202 2 24MS7 FAILURE DESCRIPTION: 24MS7 IS FAILED CLOSED, CANNOT BE OPENED FROM CONSOLE. PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION: REBUILT SOLENOID VALVE.

SALEM UNIT 2 WO NO UNIT EOUIPMENT IDENTIFICATION ,

8612260949 2 21 SGFP FAILURE DESCRIPTION: SPEED DEMAND WILL NOT INCREASE.

CORRECTIVE ACTION: VERIFIED VOLTAGES ON CONTROLLER FOUND CONTROLLER 2FC-500F SATURATED LOW. TRIPPED FEED PUMP RAN'

. DEMAND UP AND DOWN TO VERIFY-PROPER OPERATION LEFT DEMAND AT +1.000 VDC. RETURNED TO OPS.

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT'NO. 2 DECEMBER 1986 The Unit began the period shutdown as the refueling outage continued.

Radiography of the service water piping ?.o the containment fan coil units was performed. Weld repairs and piping replacements were performed as necessary. A service water flow. test of the No. 21 Component Cooling Heat Exchanger (CCHX) indicated a low flow condition.- A subsequent investigation found extensive damage to the division plate and has been attributed to a build up of pieces of.

-epoxy which broke loose from the previous repair work and caused a high differential pressure across the division plate. The other heat exchangers in the No. 21 Service Water Header were subsequently evaluated to determine the need for inspection and cleaning of debris.

Repairs to No. 21 CCHX were completed and the Unit changed to Mode IV on December 13, 1986. An analytical program for monitoring the Reactor Coolant System (RCS) chemistry during heat up was developed and implemented, including limits for by-product concentration, because of the reactor cavity resin intrusion encountered during refueling. As expected, resin by-products were discovered in the RCS during heat up; however, the purification demineralizers maintained the chemistry within the specified limits. Mode III was achieved on December 15, 1986. The Main Steam Safety Valve and the Hot Rod Drop tests and RTD cross calibrations were satisfactorily completed.

Ultrasonic testing of selective random condensate and feedwater piping has been performed as a result of the Surry pipe failure incident. No corrosion-erosion problems were discovered. The reactor achieved criticality, Mode II, on December 18, 1986. On December 23, 1986, low power physics testing was completed and the Unit was synchronized.

Power was subsequently held at 25% to complete a " soak period". The Unit was removed from service the same day to perform an overspeed test. Problems encountered with the Turbine Electro-Hydraulic Control System caused an inadvertent overspeed turbine trip / reactor trip.

Test equipment installed in anticipation of the test allowed sufficient data to be recorded to determine that the trip setpoint is satisfactory. On December 24, 1986, following repairs to the Electro-Hydraulic Control System, the unit was synchronized. A power escalation was initiated on December 26, 1986 following completion of the 47% physics testing. The Unit was at 77% power on December 28, 1986, when a reactor trip occurred due to a feedwater control valve malfunction and subsequent closure. The Unit was restored to service j on December 29, 1986, and continued a power escalation throughout the l remainder of the period.

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4e REFUELING INFORMATION'

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DOCKET NO.: 50-311

COMPLETED BY:~ L.K. Miller UNIT NAME: Salem 2 DATE: January 10, 1987 TELEPHONE:- 609/935-6000 EXTENSION: 4497

- Month December =1986

' 1. 1 Refueling information has' changed;from last month:-

YES X NO i :2 . - Scheduled date for next refueling:- ' April 9, 1988

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'3. Scheduled date for restart following refueling:

June-8, 1988,

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

YES NO -X B) Has the-reload fuel design been reviewed by the Station

. Operating Review-Committee?-

- YES- NO X

-If no, when is it scheduled? - February,'1988

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

February 1988 if required, 6.- Important licensing considerations associated with refueling:

NONE:

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7. Number of Fuel-Assemblies:

A) Incore 193 B) In Spent Fuel Storage -224-

8. Present licensed spent fuel storage capacity: 1170 F

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 fr .

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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 12, 1987 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 December 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. . pko, Jr.

Ge eral 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

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