ML20099M166

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Monthly Operating Rept for Feb 1985
ML20099M166
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/28/1985
From: Ronafalvy J, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8503210250
Download: ML20099M166 (20)
v • d • e


Text

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AVERAGE DAILY UNIT POWER LEVEL ,

Docket No. 50-272 Unit Name Salem # 1 Date March 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000

- Extension 4455

' Month February 1985 Day Average Daily Power: Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1- 1109 17 1092 2 1102 18 1107 3 1115 19 1112 4 -1108 20 1108 5 1105 21 856 6 1100 22 964 7 __

1083 23 1101 8 1104 24 1106 9 1091 25 __

1103 10 1097 26 1104 11 1115 27 1104 12 1071 28 1101 13 1107 29 14 1116 30 15' 1114 31 16 1092 P. 8,1-7-R1 8503210250 850228 PDR ADOCK 05000272

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I OPERATING DATA REPORT Docket No.50-272 Date March. 10, 1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. . Unit Name Salem No. 1 Notes
2. Reporting Period February 1985
3. Licensed Thermal Power (MWt) 3338
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1090 6.. Maximum Dependable Capacity (Gross MWe)1124
7. Maximum Dependable Capacity (Net MWe) 1079
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A
9. P$wer. 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 672 1416 67225
12. No. of Hrs. Reactor was Critical 672 , 1398.6 37222.1
13. Reactor Reserve Shutdown Mrs. 0 0 3088.4 ,
14. Hours Generator On-Line 672 1395.7 35554.3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (BUGI) 2220055 4602077 107370074

-17. Gross Elec. Energy Generated (MWH) 761150 1576540 35492590

18. Net Elec. Energy Generated (MWH) 731713 1514577 33612559
19. Unit Service Factor 100 98.6 52.8
20. Unit Availability Factor. 100 98.6 52.8
21. Unit Capacity Factor (using MDC Net) 100.9 99.1 46.3
22. Unit Capacity Factor (using DER Net) 99.9 98.1 45.8
23. Unit Forced Outage Rate 0 1.4 32.4
24. Shutdowns scheduled cver 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 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of

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UNIT SHUTDOWN AND POWER REDUCTIONS .DockSt No.50-272 REPORT MONTH Februnry 1985 . Unit Nrme Selem No.l.

Date. March 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 Reactor ~ Report ' Code-4 Code 5 Prevent Recurrence Intercept Valves85-130 2-21 F 24.5 A 5 -

un va r uwv '

-~~

Turbine Intercept Valves85-136 2-22 F 9.0 A 5 -

un unruov Turbine 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced .A-Equipment Failure-explain 'l-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Refueling 3-Putomatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exan 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.: 50-272 REPORT MONTH February 1985 UNIT NAME: Salem 1 DATE: March 10, 1985 x COMPLETED BY: - J. Ronafalvy TELEPHONE: 609/339-4455

  • DC R NO . : PRINCIPLE SYSTEM SUBJECT t

..- 1EC-1304 Chemical & Volume -Buttwelding of valves to the Control' header making each of them a "one piece connection".

1EC-1447 Fresh Water Connect one end of the former concrete plant 4" water supply line into the station potable water system and connect the other end, at No. 1 Well House, to lines feeding Nos.

901, 902 and other buildings.

'lEC-1588. Cable Trays Retag, repull various cables throughout the plant to~ match changes made to wiring diagrams prior to-implementation of the DCR system.

lEC-1619B Reactor Coolant-Wide Replace existing recorders Range RTD Recorders with seismically qualified-recorders. Revise cable designation numbers on wide range RTD cables to reflect vital channels.

f lEC-1716 Environmental Replace existing transmitter Qualification with ' environmentally qualified Rosemount 1153D model (PA-227, PA7461) ;' . (S.I. pump discharge pressure and PA-211 bit pressure.

l 1EC-1749 Aux Building Replace existing cooling coils ventilation of all pump room coolers with new cooling coils made of AL-6X tubes and copper tins.

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  • DCR NO. -PRINCIPLE SYSTEM SUBJECT 1 EC-17 75 Circulating Water Replace the inlet expansion joints of Unit 1 Main Condensers, additionally replace the remaining outlet expansion joints not changed during the main condenser retubing in 1980.

lEC-1819 Radiation Monitoring Relocate sample line connections for main steam line RMS from the MS131 valves to the MS130 valves.

1EC-1832 Steam Generator Upgrade piping and valves at Blowdown the condenser via the following changes: 1) Replace sch. 80 carbon steel piping between GBl&5 valves and condenser with type A312 TP316, 2) Install isolating valves (Mark D-8) on both sides of control valve numbers 11-14GB185.

1EC-1843 Neutron Flux Install a non-safety related Monitoring source range neutron flux monitor at the remote hot shutdown panel.

1EC-1874A Service Water Revise 8" SW emergency supply line to Aux Feedwater from #12 SW nuclear header; revise 4" SW supply line to room and oil coolers from #12 SW nuclear header; line or replace SS SW supply and return piping to

  1. 12 CC Hx; add break flanges in SW supply and return piping to #12 CC Hx.

1EC-1880 Incore Instrumentation Restore bent thermocouple column A5.

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT 1EC-1904 Aux Feedwater Relocate the 4 aux feedwater flow transmitter square root extractors and power feed switches to the Relay Room which is a benign environment area.

1EC-1939 Main Generator Stator Rewire auxiliary scanner Water Cooling terminal rack in the Relay Room.

1ET-1996 Chilled / Service Water Test application of Garlock

" Turbo-Star" cartridge type mechanical seal in Chiller Condenser Recirc Pumps (#11 and #13 only) 1ET-2021 Main Generator Monitor various generator parameters during start of generator / turbine.

1SC-0363 Condensate Modify condensate heater drain and circulating water pump motors to allow filling of oil reservoirs. (#12 Condensate Pump only)

ISC-0636 Well #1 Remove temporary structure and install smaller permanent enclosure for production well

  1. 1.

1SC-0913 Circ Water Traveling Revise shear pin sprockets on Screens circulating water traveling screens.

1ST-1243 Circ Water Bearing Change pumps to some other Lube Pumps type pump, such as a submersible trash pump.

1SC-1312A Containment Air Lock Install an alarm system to warn personnel of inadvertant air lock pressurization in the event seals leak into the air lock.

L

  • E R NO. PRINCIPLE SYSTEM SUBJECT e

IMD-0087 Vital Heat Trace for Vital' heat trace for ICV 145 CVCS boric acid batch tank sample valve.

E 1

,c MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH FEBRUARY 1985 UNIT NAME: Salem 1 DATE: March 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: -609/339-4455

,

  • DCR NO. - SAFETY EVALUATION 10 CFR 50.59 1EC-1304 This DCR increases conservatism and thereby reduces the possibility of' future occurrence.of cracks / breaks at the test, vent and drain connections. In addition, the section modulus of the connection will be significantly e ' increased which will improve the resistance to undetected shock load. No unreviewed safety or environmental questions are involved.

1EC-1447 The installation of piping to bypass production well #1 does not affect any previously performed safety analyses.

No unreviewed safety or environmental' questions are involved.

1EC-1588 The intended function of the system remains the same. No unreviewed safety or environmental questions are involved.

1EC-1619b This DCP provides for the redesignation of existing "non-vital" associated cables to vital channels. No cable rerouting or installation is involved. No unreviewed safety or environmental questions are involved..

1EC-1716 The replacement transmitters perform the same function'as- '

the original ones. No unreviewed safety or environmental questions are involved.

1EC-1749 The intended function of the system remains the same. No unreviewed' safety or environmental questions are involved.

1EC-1775 The expansion joints to be installed do not perform any safety related function.- No unreviewed safety or environmental questions are involved.

1EC-1819 The relocation of the Main Steam Line RMS Sample Lines will not affect any safety analyses previously done. _The function for both affected systems remains unchanged. No

. unreviewed safety or environmenta) questions are involved.

  • DCR - Design Change Request

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_ 1EC-1832' _This DCR upgrades the piping material used on the Steam

. Generator Blowdown Lines._ No unreviewed safety or environmental questions are involved.

' 1BC-1843 This DCR meets a' commitment to Appendix R of 10CFR50.

This installation of the source ~ range neutron flux monitor at the remote shutdown panel is an enhancement of the capability of the station to safely shut down in the event 4

of a fire emergency. No unreviewed safety or environmental questions are involved.

1EC-1874A This DCR upgrades existing Service Water System piping.

The new piping will prevent the build-up of marine growth on the pipe wall and will prevent corrosion. No unreviewed safety or environmental questions are involved.

1EC-1880 This DCR provides replacement of the seal housing assembly and the installation of thirteen new thermocouples. The new seal assembly is fabricated with the conoseal shoulder intentionally high to permit height adjustment through in place machining eliminating the concern that the proper height could not be regained if permanent bends' exist in the column after restoration. Since no changes are to be made that would affect the system, previous safety and accident analysis do not' change'nor.is the margin of safety reduced. If all thirteen thermocouples are lost, the quadrant minimum requirement of three (3) will not be violated. Three areas of safety concern were looked at in extensive detail. These areas were Post Accident Core Assessment, Subcooling Margin Monitoring, and Prediction-of Rod Cluster Control Assembly Misalignment. No unreviewed safety or invironmental questions are involved.

1EC-1904 This change supports the requirements of NUREG 0737. The installation will meet all the. requirements of seismic I.

No unreviewed safety or environmental questions are involved.

1EC-1939 This DCR does not affect the safe shutdown characteristics of the plant. No unreviewed safety or environmental questions are involved .

~1ET-1936 This test does not affect any presently performed safety analysis, nor does it create any new hazards. The basis for the Tech. Specs. remains unchanged. No unreviewed i safety or environmental questions are involved.

  • DCR - Design Change Request y ~ r-r- eme w re -e - m *-wr--,--re---wrm n- -swe m + w , m- e m-s -r*+we- r.~m--re- +-+-ew--w-a-*+em ,-r-rre*--eew-a- --e--m---e w- - - - - - + + *
  • DCR NO. SAFETY EVALUATION 10 CFR 50.59 1ET-2021 No safety systems are affected by this DCR. No unreviewed safety or environmental questions are involved.

1SC-0363 The change in the upper and lower bearing oil fill piping will not affect the operation of the motors. No unreviewed safety or environmental questions are involved.

ISC-0636 The demolition of well #1 structure, as well as the installation of the small temporary shed for one (1) booster pump does not affect any previously performed structural safety analysis. No unreviewed safety or environmental questions are involved.

1SC-0913 This system does not affect presently performed safety analyses nor does it create any new hazards. This modification will not alter any plant discharge or process. No unreviewed safety or environmental questions '

are involved.

1Fr-1243 This system does not affect presently performed safety analyses nor does it create any new hazards. This modification will not alter any plant discharge or process. No unreviewed safety or environmental questions are involved.

1SC-1312 A The intended function of this system remains unaffected.

This modification will not alter any plant discharge or process. No unreviewed safety or environmental questions are involved.

IMD-0087 This DCP will not affect any safety function of the system involved. No unreviewed safety or environmental questions ae involved.

  • DCR - Design Change Request

s PSE&G -SALEM GENERATING STATION '.

SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099156539 SMD 1 13 CHARGING PUMP FAILURE DESCRIPTION: LINE GOING TO THE PUMP SEAL WATER TANK HAS A WELD LEAK CORRECTIVE ACTION: CUT AND REWELDED WELD 85-01-16-036-5 SMD 1 13CFCU FAILURE DESCRIPTION: SW LEAK IN SUPPLY HEADER CORRECTIVE ACTION: WELD REPAIRED 85-01-04-040-1 PMD 1 12 ACCUMULATOR LEVEL INDICATOR AND ALARM

-FAILURE DESCRIPTION: COMPARATOR TRIPPING OUT OF SPEC.

CORRECTIVE ACTION: REPLACED CAPACITORS 0099162113 SMD 1 12 SW10 FAILURE DESCRIPTION: VALVE STEM IS DISCONNECTED FROM VALVE DIAPHRAGM CORRECTIVE ACTION: REPLACED VALVE AND GASKET 009901204-9 SIC 1 1TE-431A/B LOW LEVEL AMP.

FAILURE DESCRIPTION: UNABLE TO CALIBRATE CORRECTIVE ACTION: REPLACED THE LOW LEVEL AMPLIFIER

SALEM UNIT 1 .

. WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-10-28-038-8 SMD 1 1C' DIESEL GENERATOR PRE-LUBE PUMP-FAILURE DESCRIPTION: PUMP LEAKS ,

CORRECTIVE ACTION: SEAL REPLACED ,

84-10-18-018-9 SMD 1 13 RCP SEAL / STANDPIPE FAILURE DESCRIPTION: SEAL IS LEAKING EXCESSIVELY CORRECTIVE ACTION: REMOVED .100" OF SHIM FROM #3 SEAL 84-07-25-863-61 SIC #11 RCL DT/TAVG FAILURE DESCRIPTION: CHANNEL OUT OF SPEC CORRECTIVE ACTION: REPLACED CAPACITOR AND ISOLATOR; ADJUSTED TO SPEC.

943627 SMD 1 VALVE 11GB4 FAILURE DESCRIPTION: VALVE FAILED LEAK RATE TEST CORRECTIVE ACTION: REPLACED PLUG, SEAT, PACKING AND '

00995688 SMD 1 16 SW24 FAILURE DESCRIPTION: LEAKI.N G CORRECTIVE ACTION: REPLACED DIAPHRAGM 009901592-7 SIC 1 ILC-934B/F #12 ACCUMULATOR LEVEL INDICATOR AND ALARM FAILURE DESCRIPTION: COMPARATOR TRIPPING OUT CORRECTIVE ACTION: REPLACED CAPACITORS AND ADJUSTED SETPOINTS

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  • SALEM UNIT 1 .

)

i wo NO DEPT UNIT EQUIPMEU?-IDENTIFICATION

+

009910634-6 '

j SIC 1 1BS-540B #14 S/G STEAM FLOW PROTECTION CHANNEL I i

$ FAILURE DESCRIPTION: CAPACITOR. TRIPPING OUT OF SPEC.

I

[ CORRECTIVE ACTION: REPLACED CAPACITORS AND ADJUSTED TO SPEC. ,

009911902-1 SIC 1 CONTAINMENT PRESSURE RECORDER FAILURE DESCRIPTION: WIDE RANGE INDICATES LOW (DOES NOT MATCH OTHER j CHANNELS)

CORRECTIVE ACTION: REPLACED SERVO AMPLIFIER i 0099120097 i SIC SV1144 EMERGENCY CONTROL AIR COMPRESSOR FAILURE DESCRIPTION: BLOWING THROUGH TO ATMOSPHERE 3

CORRECTIVE ACTION: REPLACED SOLENOID VALVE 5

04-11-23-015-5 SIC 1R41 APD UNIT I

j FAILURE DESCRIPTION: PUMP HI/LO FLOW ALARM IS UP CORRECTIVE ACTION: REPLACED PUMP i

0099121735

, SIC 1 VALVE 1CC131 RCP THERMAL BARRIER FLOW i FAILURE DESCRIPTION: NO LOW FLOW ALARM WITH VALVE CLOSED J

1 1 CORRECTIVE ACTION: REPLACED SWITCHES AND CALIBRATED ,

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SALEM UNIT 1 .

WO NO DEPT UNIT EQUIPiv.;nT IDENTIFICATION 85-01-17-006-2 SIC 1 VALVE.1Ct.'li.7 iROOM COOLER CONT. VALVE)

{ T l FAILURE DESCRIPTION: VALVE WILL NOT CLOSE CORRECTIVE ACTION: REBUILT SOLENOID VALVE ~

85-01-18-066-1 l SIC 1 VALVE 11SW24 j FAILURE DESCRIPTION: AIR SUPPLY TO VALVE BROKEN OFF

. CORRECTIVE ACTION: REPLACED TUBING FROM SOLENOID VALVE TO 11SW24 DIAPHRAGM 84-12-31-073-0 j SIC 1 13 S/G LEVEL CHANNEL IV -

FAILURE DESCRIPTION: CHANNEL DRIFTING l

CORRECTIVE ACTION: REPLACED LOOP AND RECALIBRATED l

) 85-02-15-068-5 SMD 1 BAE HEAT TRACE - DORIC POINT 195 4

FAILURE DESCRIPTION: INCORRECT THERMOSTAT READING i

l CORRECTIVE ACTION: REPLACED HEAT TRACE AND RESET PROBES i 85-01-03-120-81 SIC 1R19 C i

FAILURE DESCRIPTION: SPIKING INTO ALARM i

CORRECTIVE ACTION: CLEANED CONNECTOR

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SALEM UNIT 1- '.

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.WO NO DEPT UNIT EQUIPiu.esT IDu1IFICATION . .

84-12-25-004-4

.1 13 CHARGING-PUMP FAILURE DESCRIPTION: LOSS OF-SPEED CONTROL CORRECTIVE ACTION: FREED JAMMED 1TN. AGE ON MOTOR COUPLING 84-12-26-039-2 1 VALVE INT 31 FAILURE DESCRIPTION: VALVE IS NOT STROKING PROPERLY ,

CORRECTIVE ACTION: ' INSTALLED NEW REGULATOR 85-01-19-159-1 1 #12 WASTE GAS COMPRESSOR ,

FAILURE DESCRIPTION: . VALVE 12WG10 WILL NOT OPEN UPON START OF COMPRESSOR CORRECTIVE ACTION:- REPLACED MOTOR DIAPHRAGM 84-08-31-040-2 NCS 1 HANGER #1A-SIS-160 FAILURE DESCRIPTON: SPRING CAN INOPERABLE 7..

CORRECTIVE ACTION: SPRING CAN RENORKED 85-02-066-9 SMD 1 BAE HEAT TRACE - DORIC POINT 195 FAILURE DESCRIPTION: -SECONDARY HEAT, TRACE READS HIGH CORRECTIVE ACTION: REPLACED HEAT TRACE AND RESET PROBES

SALEM UNIT 1. '

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 009901651-6 SIC 1 RVLIS FAILURE DESCRIPTION: MONITORS NOT FUNCTIO;iING PROPERLY ,

CORRECTIVE ACTION: REPLACED POWER SUPPLIES 85-01-31-057-3 SIC 1 TS 632 FAILURE DESCRIPTION: OUTPUT POSITION LIGHT TOOK TOO LONG TO ENERGIZE CORRECTIVE ACTION: CLEANED CONTACTS; INSTALLED NEW MICRO SWITCH; AND RESET LATCH COIL 85-01-17-004-6 SIC 1 VALVE ISW205 (ROOM COOLER VALVE)

FAILURE DESCRIPTION: VALVE DOES NOT SHUT OFF AUTOMATICALLY CORRECTIVE ACTION: SV-608 RE-ENERGIZED, REPLACED COIL 85-01-20-011-5 SMD 1 #12 AREA SPACE HEATER FAILURE DESCRIPTION: HEATING COIL IS NOT ENERGIZING CORRECTIVE ACTION: REPLACED SHORTING BAR 85-02-02-010-2 SMD 1 BREAKER FOR PRESSURIZER HEATERS FAILURE DESCRIPTION: BREAKER IS TRIPPING CORRECTIVE ACTION: REPLACED BREAKER

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SALEM UNIT 1 I WO NO DEPT UNIT EQUIEiv,wr IDENTIFICATION 009911916-1 SIC 1 1R41B (PLANT VDIT IODINE , . RMS)

FAILURE DESCRIPTION: MONITOR READOUT IS INDICATING A LARGE SWING'IN READINGS WITH NO,OTHER MONITOR INDICATIONS CORRECTIVE ACTION: REPLACED PONER SUPPLY MODULE l

85-01-25-097-0 SIC 1 APD UNIT (Rll A AND R12A)

FAILURE DESCRIPTION: PUMP IS SEIZED CORRECTIVE ACTION: INSTALLED NEW VACUUM PUMP l 942536 SIC 1 1R46A-D l FAILURE DESCRIPTION: STEAM ISOLATION VALVES LEAKING THROUGH l

CORRECTIVE ACTION: REPLACED SHORTED COIL AND REBUILT VALVE (A);

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REPLACED BROKEN PISTON ASSEMBLY AND REBUILT VALVE (S) l (B AND C); AND REPLACED CRACKED PLUNGER HOUSING AND l REBUILT VALVES (D)

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c-SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 t FEBRUARY 1985 SALEM NO. 1 The Unit began the period operating at full' power. On 2/21/85 at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, the Unit power was reduced to 79% as a result of 12E Turbine Intercept Valve failing to reopen af ter. completion of a routine turbine ~ valve surveillance test. The valve failed to reopen as a result of a false closure signal generated from the Electro-Hydraulic Control circuitry due to a failed resistor. On 2/22/85 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, with the completion of repairs, the Unit was returned to 100% power where it remained for the rest of the period.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J.'Ronafalvy UNIT NAME: Salem 1 DATE: March lu, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month February 1985

1. Refueling information has changed from last month:

YES NO X

. :2 . . Scheduled date for next refueling: February 22, 1986 ,

3 '. Scheduled date for restart following refueling:' May 4,1986 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? January 1986 5'. Scheduled date(s) for submitting proposed licensing action:

January 1986 if required

6. Important licensing considerations-associated with refueling:

NONE

7. ' Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 296

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: September 2001 ,

8-1-7.R4 i ,

9-li-V ,a'. ' -

O PSEG

.) Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC -20555

Dear . Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 HDOCKET NO. 50-272 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 February 1985 are being sent to you.

Average Daily-Unit Power Level Operating Data Report c 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 l

Regional Administrator USNRC f- 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 Enclosures Page of 8-1-7.R4 7

fe bY The Energy Peopk) bf as2wnwwe//

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