ML20080T128

Monthly Operating Rept for Sept 1983

ML20080T128
Person / Time
Site:	Salem
Issue date:	10/10/1983
From:	Miller L, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8310200174
Download: ML20080T128 (16)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date Oct. 10, 1983 Complet'ad by- L. K. Miller Telephone 609-935-6000 Extension 4455 Month September 1983 D y Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) l' 1090 16 1086 2 1090  :

• 17 1089 3 1089 ,18 1084 4 1057 19 1085 5 1090 20 1083 6 1086 21 672 7 1085 22 210 8 1079 23 884 9 592 24 1086 10 513 25 1090 11 1082 26 1086 12 1073 27 1090 13- 1089 28 1090 14 1090 29 1090 15 1090 30 1090' P. 8,1-7 R1 8310200174 831010 PDR ADOCK 05000272 R PDR Page 2 of 16

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j. -l OPERATING DATA REPORT l

Docket No. 50-272 )

Date Oct 10, 1983 Telephone 935-6000 Connpleted by L. K. Miller Extension 4455 Operating Status 1.- Unit Name Salem No. 1 Notes

2. Reporting Period August 19n3

3. Licensed Thermal Power (MWt) 33fE

4. Nameplate Rating (Gross MWe) 1135

- 5. . Design Electrical Rating (Net MWe) I653

. -6. Maximum Dependable Capacity (Gross MWe) TTY 4

7. Maximum Dependable Capacity (Not MWe) T67T

8. If Changes Occur in Ccpacity 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 720 6551 55560

12. No. of Hrs. Reactor was Critical 699.7 3265.7 _ 30990.8

13. Reactor Reserve Shutdown Hrs. 0 2033.4 3006.5 ,

14.-Hours Generator On-Line 681.9 2984.3 29632.2

15. Unit Reserve Shutdown' Hours 0 0' O

16. Gross Thermal Energy Generated (MWH) 2212915 9622139 08792330

17. Gross Elec. Energy Generated (MWH) 751820 3240020 29204870

18. Net Elec. Energy Generated (MWH) 720199 3062022 27656875

19. Unit Service Factor 94.7 45.6 53.3

20. Unit hvcilability Factor 94.7 45.6 53.3

21. Unit Capacity Factor (using MDC Net)- 92.7 43.3 46.1

22. Unit Capacity' Factor

, (using DER Net) 91.8 42.9 45.7

23. ' Unit Forced Outage Rate 5.3 47.0 30.4

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 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 3 of 16 ,

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 GEPORT MONTH SEPTEMBER 1983 Unit Name Salem No.1 ,

Date Oct 10, 1983 Completed by L.K. Miller Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause ar.d Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Traveling Screens /

Trash Racks83-248 9/03 F 3.3 B 5 -

HF FILTER Canal Screens83-250 9/03 2. 4 .

" " " " " = = =

83-252 9/06 6.5 Condenser Tube and 83-254 9/08 "

2.5 " " "

HH HTEXCH Water Box Cleanidg Nuclear Steam 83-256 9/09 "

14.9 A 3 WB HTEXCH Generator Control Shorted Motor Circuit on

" " Traveling Screen 83-258 9/12 "

3.4 5 HF MOTORX Condenser Tube and 83-260 9/17 "

8.8 B " "

HH HTEXCH Water Box Cleaning Traveling Screeps/

Trash Racks HF FILTER Canal Screens83-262 9/18 3.4 83-264 9/18 "

3.2 HF 83-266 9/20 3.3 83-268 9/20 3.3 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit l' F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Re fueling 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 Page 4 of 16 (NUREG 0161) l

9 UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 REPORT MONTH SEPTEMBER 1983 Unit Name Salem No.1 .

Date Oct. 10, 1983 Completed by L.E. Miller 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 ctor Report Code 4 Code 5 Prevent Recurrence Reactor Trip System Incluc ing Sensors /

83-270 9/21 F 23.3 B 3 -

IA CKTBRK Logic / Actuators 83-272- 9/23 "

2.7 5 CH FILTER Clean SGFP Strainer Traveling Screens /

Trash Racks83-274 9/23 "

5.0 HF Canal Screens83-276 9/24 2.1 83-278 9/24 10.4 83_280 9/24 4.7 83-282 9/25 5.6 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-Re fueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licer.see F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

Page 5 of 16

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UNIT SHUTDOWN.AND POWER REDUCTIONS Docket No. 50-272 REPORT MONTH SEPTEMBER 1983' Unit Name Salem No.1 Date '

Oct 10, 1983 Completed by L.K.-Miller Telephone 609-935-6000.

Extension 4455 Method of .

_m Duration Shutting License Cause~and Corrective No. Date 1Ype Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Condenser Tube and 284 9/30 F 3.3 B 5 - HH HTEXCH Waterbox Cleaning Traveling Screens /

Trash Racks83-286 9/30 "

6.2 " " "

HF FILTER- Canal Screen 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit R 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-Automa? tic Scram. tion of Data 4 D-Regulatory Restriction 4-Continuation of ' Entry Sheets E-Operator. Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report i G-Operational Error-explain 9-Other (LER) File j H-Other-explain (NUREG 0161) i i

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DOCKET NO3 50-272 MAJOR PLANT MODIFICATIONS I I SALEM 1

- REPORT MONTH SEPTEMBER 1983 OCTOBER 10, i983 DATEt COMPLETED BY: L. K. MILLER TELEPHONE: (609) 339-4455 PRINCIPLE SYSTEM SUBJECT

• DCR NO.

lEC-1592 Main Steam G210 Modify flow transmitter sensing lines for #12 Flow Transmitter Narrow Range Instrument FA-3472.

1SC-ll84 Potable Water and Install a lateral in the 4" CW Ventilation riser entering the Controlled Facilities Building. Lateral to be 5'-0" above finished floor with a shut-off valve inside the building turning through the wall and a shut-off valve with a 2-1/2" fire hose coupling outside the building.

LOD-0040A Service Water Modify service water travelling screen housing.

• DESIGN CHANGE REQUEST Page 7 of 16 8 7 . R1

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 -

REPORT MONTH SEPTEMBER 1983 UNIT NAME: Salem 1 DATE: October 10, 1983 COMPLETED BY: L.K. Miller TELEPEONE: 609/935-6000 X4455

• DC R NO . 10CFR50.59 SAFETY EVALUATION lEC-1592 Installation of this DCR will correct tubing that is run to flow transmitters. No unreviewed safety or environmental questions are involved.

1SC-1184 Implementation of this DCR will not affect any safety related systems or prior analyses. No unreviewed safety or environmental questions are involved.

10D-0040 This DCR does not affect any safety analysis performed nor does it create any new safety hazards. No unreviewed safety or environmental questions are involved.

• Design Change Request i

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P S E '& G " SALEM GENERATING SMTION SAFEIT REIATED WORK 3 DER IOG ,

SALEM UNIT 1 e

WO NO DEET LNIT EQUIPMiNF TF='NnnCATIN 923587 PD 1 . VALV0P,13SW57 I FAIIURE DESCRIPTIW: 13 OtU DTS N0f MAKE REQUIRED FICW IN IN SPEED. .830324 CuwkunVE ACTION: REPIACED SEENOID VALVE N 13SW57. FIN GBCKED OLTP SAT. 830325 923005 PD 1 RMS R41 SAMPLE PLMP

' FAIIURE DESCRIPTIN: PULLEY W SAMPLE PtNP HAS BROKEN IOOSE A10 BELT IS TF. 830608 CNRECTIVE ACTIN: REPIACED PUMP AND REASSD4 RTE / REALIGNED PUMP AND MDIOR. VERIFIED PROPER FIOW ATO

.i IN FION ALARM CLEARED. 830706 4 924338 PD 1 REACP PRCTIECTICN SYS -

9 FAILURE DESCRIPTIW: ENTER 'INE EDIICWING VAIUES OF DELTA-T RID. T-AVE 571.7, IOOP 11 - 59.6, IOOP 12 3 59.1, IOOP 13 - 62.7, IOOP 14 - 57.6. 830620 t

j CORRECTIVE ACTICN: CALIBRATED l'IC-441A/441E, 411A/411E, 421A/ 421E, 431A/431E AtO (XMPLETED -r FUNCTIWALS. 830708 l

924358 PD 1 NIS AFD TARGEP BAND l

i FAILURE DESCRIFFIN: GANGE 'INE SETPOINTS m AFD EDR A TARGEP VALUE & -20 AT 100% RTP AS DETERMINED 4 BY REPC'IOR ENGINEERING. 830715 i

! CORRECTIVE ACTIN: OCNPLETED PROCEDURE l'IC-16. 1.008. 830719 h

1, 924666 MD 1 RX TRIP & dYPASS 1

FAILURE DESCRIPTIW: RENOVE 1A RK 'IRIP BKR & IB RX TRIP BYPASS BKR FOR INSPECTIN BY FRANKLIN i -INurnvrs REP. 830317 CORRECP1VE ACTIm: REMNED & REINSTAT.Tm BKRS AS PER RBuumf FRCM NRC EDR FRANKLIN INSTI'IUIE. NO FURTHER TEErfING REQUIRED DUE TO NO DISASSDELY OR AD3US'INENPS BEING MADE. 830318 l

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PSE&G SALEM GENERAT1NG SD& ION SAFErY REEATED NORK CEDER LOG ,

SAIEM UNIT 1 NO NO DEPT WIT EGJIPMENT E5MidICATIN

'924697 MD 1 FUEL TRANSFER SYSTEM FAIIERE DESCRIPTIW: RENOVE BRAKE SOLENOID COIL FROM UPENDER IN 1 FHB EOR INSTALIATIN IN 2 UNIT UPDOER CCNDONENT SIDE. REPIACE WTIH A COIL CF LIKE KIND. 830322 CORRECTIVE ACTIW: REMNED COIL FRN 1 UNIT FHB SIDE & PLACE IT IN 2 CCNIADMENT SIDE. - REPIACED GD COIL IN 1 EMB WTIH NEW COIL FRCH SPARES. 830525

, 824841 MD 1 RX 'IRIP & EYPASS BKR

! FAILURE DESCRIFfIN: ASSIST ENERGY IAB IN SPECIFIC TESTS VIA PROCEDURE T-94 FOR 'INE REACITR TRIP AND -

j BYPASS BREAKERS. 830331 3 CORRECPIVE ACPIN: ASSISTED ENERGY IAB IN TESTS - PROCEDURE T-94. REMOVED 3 OVERCURRENT TRIP PADS ON A & B TRIP & BYPASS BREAKERS. E30404 i

924852 FO 1 RX 'IRIP BKR A

.1 FAILURE DESCRIPTICN: REPIACE MISSING CLIP CN AUX CmTACP SWITCH. 830401 f

CORRECTIVE ACTIN: REPIACED MISSING SNAP RING ON AUX CCNPACT SWI'ICH CN RX TRIP BKR A WITH SNAP RING

- FR m RX BYPASS BER A UNIT 2. 830407 924970 MD 1 11 GG PMP LO COCLER i

FAIIURE DESCRIFFIW: OPEN AtO INSPECT COOIER EDR CI4XEING DUE TO SILT OR SHELL LIFE. 830419 CUKREL:nVE ACTION: OPENED COOLER AND CLEANED 'IUBES. NO SHELL LIFE, MOSTLY GRASS AND SHREDDED

. PLASTIC. 830426 j 925097 MD 1 1A DIESEL GENERA'IDR

! FAILURE DESCRIPTIW: CX2aAum TEST CF 'lURBO BOOST SOLENOIDS NHILE DIESEL NAS RUNNING. 'IAV2 DID NCyr OPERATE. 830310 i

4 CORRECTIVE ACPIW: INSTATJm NEW SOLENOID VALVE. 830722 i

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P;S E &'G SALEM GENERATING STATrm SAFETY RELMI1iD NWK NDER IOG - ,

SAIDI UNIT 1' WO NO Dt;rr UNIT EQUIINENT IDENTIFICATIN 925140 PD 1 1R13E-15CECU RAD MN FAILURE DESCRIPTION: . . MNITOR HAS FAIIED GF SCALE IIM. 830401 CORRECTIVE ACTIN: REPLACED DETECIOR AND DEFECTOR CABLE END.' AISO PERFORMED CHAtNEL CAL. 1PD4.1.022. 830420 925156 MD 1 11 BAT PtNP FAILURE DESCRIPTIW: HEAT TRACE: RNP HEATER NOT IN PIACE AND 1 TEMP DETEC10R LINE HAS BEEN PULLED OUT T PIACE AND IS LYING W THE FICOR. 830421 CORRECTIVE ACFION: REPLACED BorH STRIP HEATERS W #11 BNP PUMP MD INSULATED. ALSO REPAIRED SHCRP IN HEAT TRACE 120 P&S.~ 830426 .

925161 PD 1 14 NIXMERDR FAILURE DESCRIPfIW: ACCUPUIA'IXR PRESSURE IS BELN SPEC. YEr CHANNEL D IIM PRESSURE ALARM W BEZEL IS CLEAR. 830410 CORRECTIVE ACTIW: COMPARATOR IIC936D-H CUT T SPEC. AND BLINKING. MXN) CAPACITORS C2&C3 IDEING.

REPLACED CAPACITERS & VERIFIED SETPOINTS ON CWPARATOR W/OUT AIMUSPDENP. 830420 925216 PD 1 -A&B RK TRIP BREAKERS FAILURE DESCRIPTIm: #12 S/G ICW ICW LEVEL DIDN'T TRIP THE RX BKRS MIEN SIGNAL HAS RECEIVED. 830225

. Cuto<ta.;nVE ACTION: VERIFIED TRIP SIGNAL TO SSPS AND SSPS OUTPUTS TO UV COILS. A BKR TRIPPED 1 OUT T 3 TIMES, B BKR DIDN'T TRIP. REPLACED BKRS FIEM LNIT 2, VERIFIED TRIPS m.

830226 Page 11 of 16

PSE&G SALEM GENERATING S'IATION SAFEIT REIATED WOfE GDER IOG ,

SALEM UNIT 1 NO NO DEPT LNIT EQUIPMENE IDENTIFICATION 925217 MD 1 A&B RX TRIP & BYPASS FAILURE DESCRIPTION: #12 S/G IIM Im LEVEL DIDN'T TRIP RK TRIP BKRS WIEN SIGNAL NAS RECEIVED. REMOVE DUST COVERS FRCM ALL RX TRIP & BYPASS BKRS AS PER DR FO 83-1417. 830225 CORRECTIVE PCTIW: REMNED IBOER VOLTAGE RELAY FRCM REACTOR TRIP & BYPASS BREAKERS FOR INVESTIGATION. 830305 _

825420 PD 1 14S/G S'IM FID GN II l

FAILURE DESCRIPTICN: 'IHE ME7fER IN CWTROL ROOM INDICATES 15%. ICIUAL STEAM FIN IS 0. 830214

CutetL'nVE ACTION: USED 1PD.2.5.059 TO REMVE CHANL FRCM SERVICE EQUALIZED TRANSMITTER NHICH INDICATED 1.00 'IHIS PROVED CALIBRATIN W. RMVD INSUIATIN FRCH COND PCDS - FILM NORRL. 830217 925431 PD 1 1R45A-D FAILURE DESCRIPTIW: ALL E00R GANNELS FAILED. 'IHERE IS NO INDICATIN CN 'IHE METTERS IN CCNTROL ROOM.

830213 CORRECTIVE 7CTIN: FOUND BAD PARAT.TEL I/O BOARD. PLACED BACK IN STANDBY. FAILED BY INDICATI N W LY FRW I/O BOARD IN Cr-2. 830601 i

925975 MD 1 ISJ4 l FAILURE DESCRIFFIN: VALVE LEAKING. 830126 CumEL'nVE ACTION: INSPECTED AND REPAIRED VALVE AS PER DR bo 83-1396. 830128 927480 MD 1 13 CHARGING EtMP FAILURE DESCRIPTICN: INSPECT VALVE SEATS. 830226

! CORRECTIVE ACTICN: INSPECTED VALVE SEATS. DISKS & SPRINGS. REPLACED ALL SUCTI m & DISCHARGE VALVE ASSEMRT.TFS AS PER M6E. 'IOOK VIBRATION READINGS AS PER MllG. 830307 l

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- PSE&G SALEM GENERATING SIMION SAFE 1Y REIATED WORK WDER LOG ,

SAIDi UNIT 1 -

4 WO NO DEPT WIT EQUIPMENT IDENnrICATIN 927506 PD 1 1PC-455K PZR PRES CT

! FAILURE DESCRIFfICN: GANNEL CUT T CALIBRATIN. 830300 I

CORRECTIVE ACTION: REMOVED SIM1A'IOR S/N 570. INSTALLED SIM9GDR S/N 50-626. PERKEMED PROCEDURE PD2.1.082. 830308 927721 PD 1 BMS, IR46E I

FAILURE DESCRIPTIN: GANNEL IlOICATES HIGH ALARM WARNING AND FAIIURE. 830225 1

CORRELTIVE ACTION: FOUND 'IHE HIGH VOLTAGE CIRCUIT INOPERABLE. REPIACED STABOARD PARES R1&R6 l RESISIORS, Q1&Q2 'IRANSIS10RS & C2&C3 DIODES. - PEREORMED CEIBRATIN PROCEDURE 1PD4.1.082. 830305 .

l 1 927743 PD 1 13 S/G STEAM DUMP i

i FAILURE DESCRIPTICN: VERIFY 13MS10 00NIROL AND VALVE TERATIN. 830215 CORRECTIVE ACTION: TIGHTENED IOCKNUT ON POSITICNER. 1PC-536C S/N KO-105 FIMOVED FROM SERVICE.

]

CUPPUT JUMPS MIEN INCREASE / DECREASE. INSTALLED CCtf1 ROLLER S/N MD-104-UNIT 2 i 2PC-526C.

928965 PD 1 1R16 PIANT VENT FAIIURE DESCRIPTIN: 1R16 READING 45K CN RPI & READING 63K IN BACK T CCNTROL BOOM. CHEMISTRY 100K IOCAL SAMPLE & NO APPRECIABLE READING WAS RECOBDED. 821225 I

i CORRECTIVE ACTIm: VERIFIED CHABNEL DRAW TS & PERFORMED PIATEAU PART CD 1PD.4.1.025. RETURNED DRAW 'IO TS. IN SERVICE READING 400 CPM. DID CAL & EDUND TRIGGER POINT TOO l HIN. 830105 il l 929599 PD 1 1E'It-542#14S/G SITID i

j FAILURE DESCRIPTION: 1EC-540 A/B CmPARAIOR RESET CUT T SPECIFICATIN - RECALIBRATE. 830316 i

I CORRECTIVE ACTIW: REPIACED C2, C3 & R39 IN POWER SUPPLY. ADJUSTED SETfPOINT & RESET ON OUTPUT i

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1. 2. Q/A VERIFIED. RECCEDED SAT AS LEE'r DATA. 830318 l

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t 'PSE&G SALEM GENERATING STATEW -

SAFEIY RELATED WORK CBDER IOG ,

SA12M UNIT 1 .

WO NO DEPT UNIT EQUIPMENT MNTIFICATIN 929640 PD. -1 BMS 1R41A FAILUIC DESCRIPTIN: SETPOINTS SCRAMBLED DURING POWER TF CYCLE T CALIBRATIN CHECKS. 830325 CORIN'r'IVE ACTION: BATTERY PACK REPLACED, VERIFIED VOLTAGE, AT 5.528 VDC. REEDADED SEPPOINrs.830330 929703 PD -1 ILT-517 11S/G LEVEL FAILURE DESCRIPTIN: GANNEL CUT T CALIBRATIN. 830406 CORRECTIVE ICTIN: . REPLACED CAPACITCPS R2&3 (OLD SERIES 39D) WPIE NEW CAPACI'ICRS. '(O[D WP:RE LEAKING) , 'IO CWPLETE FGK"IINAL IPD2.6,033 PAGE 11. VERIFIED BY Q/C. 830407' Page 14 of 16

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SALEM UNIT 1 OPERATIONS

SUMMARY

REPORT AUGUST 1983 Unit No. 1 began the month at full power and continued to operate at 100% power until the reactor tripped on September 9, 1983.

Investigation revealed that the trip was caused by failure of the Proportional Integral Derivative (PID) controller on No. 13 Steam Generator level control. The failure of the PID controller caused feedwater regulating valve 13BF19 to close. Closure of this valve resulted in a steam flow /feedwater flow mismatch condition which tripped the reactor. The PID controllar was replaced in kind and satisfactorily tested.

Unit No. I was restored to 100% power on September 10th, and continued to operate at full power until the reactor tripped on September 21st due to a blown fuse in one of the input bays to Train A of the Solid State Protection System.

Train A had been removed from service for the I&C Department to perform surveillance testing on the Reactor Trip Breakers. The fuse for No. 11 Reactor Coolant Pump (RCP) Breaker Open Indication blew during the course of another unrelated surveillance test, a condition which was undetectable at the time. Upon completion of the testing, Train A of the Solid State Protection System was returned to service.

The reactor tripped due to the false indication of the RCP breaker being open and reactor power greater than permissive setpoint P-8.

Unit No. I was returned to full power on September 23rd, and continued to operate at 100% power for the romainder of the month.

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REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: L.K. Miller UNIT NAME: Salem 1 DATE: October 10, 1983 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month September 1983

'1. Refueling information has changed ~from last month:

YES NO X' l2. Scheduled date for next refueling: May 31, 1984

3. Scheduled-date for restart following refueling: August 18, 1984 2

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

YES NO NOT DETERMINED TO DATE 10/1/83 B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is.it scheduled? April 1984

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

April 1984 ' (if required)

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 212

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 1996 8-1-7.R4 Page 16 of 16

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R g pggg Public Service Electric and Gas Company P.O. Box E Hancocks bridge, New Jersey 08038 Salem Generating Station October 10, 1983 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Gir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In Compliance with Section 6.9, Repcrting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of September 1983 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours ,

J. M. Zupko, Jr.

General Manager - Galem Operations LKM: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 Enclosures Page 1 of 16 8-1-7.R4  !

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The Energy People ,,, ,, ,