ML20080G433

Monthly Operating Rept for Aug 1983

ML20080G433
Person / Time
Site:	Salem
Issue date:	09/10/1983
From:	Miller L, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8309200273
Download: ML20080G433 (17)

Text

,.

AVERAGE DAILY UNIT POWER LEVEL Dpcket No. 50-272 Unit Name Salem # 1 Date Sept. 10, 1983 Completed by L. K. Miller Telephone 609-935-6000 E:: tension 4455 Month August 1983 Day Average Daily-Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1076 16 1066

2. 1070 17 1079 3 1074 18 1051 4 1062 19 1049 5 1069 20 1065 6 1063 21 1061 7 1007 22 463 8 969 23 0 9 1024 24 0 10 1039 25 0 11 283 26 694 12 0 27 1057 13 0 28 1064 14' 102 29 1079 15 1001 30 1075 31 1066 P. 8,1-7 R1 8309200273 830910 Page 2 of 17 DR ADOCK 050002l

OPERATING DATA REPORT Docket No. 50-272 '

Date Sept. 10, 1983 Telephone 935-6000

Completed by L. K. Miller Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes l 2. Reporting Period August 1983

3. Licensed Thermal Power (MWt) 3338

4. Nameplate Rating (Gross MWe) 1133

5. Design Electrical Rating (Net MWe)_ TOT 6

6. . Maximum Dependable Capacity (Gross MWe)1124

7. - Maximum Dependable Capacity (Net MWe) T679

8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last

- Report, Give Reason l

N/A t

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 5831 54840 12.1No.'of Hrs. Reactor was Critical 608.0 2566.0 30291.1

13. Reactor Reserve Shutdown Hrs. 0 2033.4 3006.5

14. Hours Generator On-Line 578.1 2302.4 28950.3

15. Unit Reserve Shutdown Hours 0 0 0

i. 16. Gross Thermal Energy Generated (BHGI) 1870906 7409224 86579415 i

17. Gross Elec. Energy Generated 4 . (MWH) 619760 2488200 28453050

18. Net Elec. Energy. Generated (.MWH) 589725 _ 2341823 26936676

19. Unit Service Factor 77.7 39.5 53.5 20.-Unit Availability Factor 77.7 39.5 53.5 j 21.' Unit Capacity Factor (using MDC Net) 73.5 37.2 46.1

22. Unit Capacity Factor l (using DER Nat) 72.7 36.8 45.6-23._ Unit Forced Outage Rate 22.3 53.1 30.9

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):

4' 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 17

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UNIT SHUTDOWN AND POWER . REDUCTIONS Docket No. 50-272 i

REPORT MONTH AUGUST 1983 Unit NamelSnlcm No.1 Date Sept. 10, 1983 L.K. Miller Telephone 609-935-6000

$ Completed by Extension 4455 Method of I

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 Traveling Screens /

Trash Rack -

f HF FILTER Canal Screens 1 83-196 8/2 F 4.8 B 5 -

I 83-198 8/5 " 10.5 " " HF-i t

i

!83-200 8/6 3.9 i

i 83-202 8/6 6.0

" " " " " Circ Water System'83-204 8/7 36.4 Traveling Screens /

l Trash Rack

" " " " " Screens i 83-206 8/7 32.6

" " " " = a a =

4 83-208 8/8 5.7 J " " a = a = =

!83-210 8/8 2.7 k " " " = a = =

l 83-212 8/8 "

43.2 Condenser Tube and

" " " " HH HTEXCH Waterbox Cleaning i 83-214 8/9 5.0 I

4 i 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 A-Equipment Failure-explain 1-Manual Instructions Salem as i F: Forced Source 4 S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara-C-Re fueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets  !

j .E-Operator Training & Licensing Exam Previous Outage for Licensee

' F-Administrative 5-Load Reduction' Event. Report -

G-Operational Error-explain 9-Other (LER) File i H-Other-explain (NUREG 0161) i Page 4 of 17 i

UNIT SHUTDOWN AND POWER. REDUCTIONS- Dock t No. 50-272 -

' REPORT MONTH AUGUST 1983- Unit Nam 3 Salem No.1 Date Sept. 10, 1983 Completed by LL.K. Miller Telephone 609-935-6000 l

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 Traveling Screens /

Trash Rack .

" " " " EF FILTER- Canal Screen

!83-216 8/10 .5 i Condenser Tube and

" " " HH HTEXCH Waterbox Cleaning 83-218 8/11 2. 4 - B Condensate Tube and HH HTEXCH Waterbox Cleaning 83-220 8/11 F 2.5 B 5 ---

Auto Trip l

83-222 8/11 F l81. 2 A 3 --- HF FILTER Traveling Screen Traveling Screens / ~

}

i Trash Rack

" " Canal Screen 83-224 8/16 F 8.0 B 5 ---

J f

j 83-226 8/18 "

3.0 "

9~ HF FILTER i

83-228 8/18 3.1 Turbine Governing 83-230 8/18 " 91.E " 5 " HA MECFUN System Control l

4 Traveling Screen /

Trash Rack Canal 83-232 8/18 " 16.2 "

9

" HF FILTER Screen l 83-234 8/20 9.4 i

i i 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as l B-Maintenance or Test 2-Manual Scram. for Prepara- Source

S: Scheduled

' 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 l

H-Other-explain (NUREG 0161)

} Page 5 of 17

UNIT SHUTDOWN AND POWER REDUCTIONS Docket'No. 50-272 REPORT MONTH AUGUST'1983 . Unit N me Salca No.1 Date Sept. 10, 1983 Completed _'by 'L.K. Miller Telephone 609-935-6000 Extension 4455 Method of Duration ,

Shutting License Cause and Corrective Date Type Hours' Reason Down , Event System Component Action' to No.

1 2 Reactor Report Code 4 Code 5 Prevent Recurrence

" " " " HH HTEXCH Water Box Cleaning 83-236 8/21' 2.5 7rbine Governing 83-238 8/22- "

92.8 "

5 HA MECFUN Sy gem Controls Auto Trip-Turbine

"' " " " Governing Controls83-240 8/22 84.7 A 3 Traveling Screen /-

Trash Rack Canal

" FILTER Screen 83-242 8/27 "

3.7 B 5 -

HF 83-244 8/27 4.9'83-246 8/29' "

.5' HA MECFUN Turbine Valve Test 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-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 _ (NUREG 0161)

Page 6 of 17

a DOCKET NO3 50-272 MAJOR PLANT MODIFICATIONS UNIT NAME: SALEM 1 REPORT MONTH AUGUST 1983 DATE: SEPTEMBER 10, 1983, COMPLETED BY: L. K. MILLER TELEPHONE: (609) 935-6000 Ext. 445'5

• DCR NO. PRINCIPLE SYSTEM SUBJECT lEC-1533 Building and Equipment Change nuclear classification of Drains, Flood and Sump Pumps containment sump pumps from Nuclear Class III to Non-Nuclear Safety.

ISC-0776 Structural Administration Building El. 116.5' -

Redesign locker room on second floor to be a new office area for Operations staff.

O o

• DESIGN CHANGE REQUEST 8-1-7.R1 Page 7 of 17

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH AUGUST 1983 UNIT NAME: Salem 1 DATE: September 10, 1983 COMPLETED BY: L.K. Miller TELEPHONE: 609/935-6000 X4455

• DC R NO . 10CFR50.59 SAFETY EVALUATION 1EC-1533 The Containment sump pumps themselves are not part of a safety related system and do not affect the safe shutdown of the plant. This DCR has no effect on the plant discharge. No unreviewed safety or environmental questions are involved.

1SC-0776 This DCR covers work in an area not related to safety related buildings or equipment. This DCR does not affect any releases from the structure. No unreviewed safety or environmental questions are involved.

• Design Change Request l

Page 8 of 17 1

PSE&G SALEM GENERATING SDLTION '

SAFETY REIATED WORC CRDER IOG ,

SAI2M LMIT 1 No no orrr wrr ny1wezer umrint.Ar1m 922302 m 1 12SW237 PIPE IEAK FAILURE DE. h. rim: PIPING (3/4") IEINEEN VALVE Ato 30" HEADER HAS A HOW IN IT. Wrm THAT BAY IN SERVICE LEAKAGE EFFmS SWP PLEP CAPACITY. 830516 00RRECTIVE ACTIN: GRCIRO CED PIPE MO FIANGE CUT W SYSTEM. FITTED Wrm AIL NEN PARTS. 83061"6 931038 m 1 ID VTL INST INVRTR s FAIIURE DESCRIPTIW: TROUBLE SHOOT PNER SPIKES FRCN 1D VITA $ INSTRLNENT INVERTER. 830428 CCRRBCTIVE ACTICN: REPIACED K1 REIAY W/REIAY FBCN 2D VITAL IN ST. INVERIER. CHECKED TIMER CAL AIO OPERATICN CF A/C CUTPUT BKR. PERIVINED M4J. 830505 933794 m 1 12 BAT PLNP i

FAIIURE DESCRIPTIW: 12 BAT PLNP FAILED SP(0) 4.0.5-P. NX7UST PtNP EDR FICW AND PRESSURE. 830731  !

CORRECTIVE ACTICN: SET IMPFIJER CLEARANCE 'ID .012. 830731 933805 m 1 15 SW IMP STRAINER  !

FAIIURE DESCRIPTIW: 15 SW PLNP STRAINER HAS A BBWEN SHEAR PIN. 830806 ,

CORRECPIVE AC"'ICN: REPU CED SHN S AND SHEAR KEY. 830808 933829 m 1 14 FAN COIL INIT FAILURE DESCRIPTICN: BACK DRAET DAMPER S'IUCK CIOSED. 830809 ,

CORRECTIVE ACTICN: GREASED DAMPERS AND NORKED THEM FREE. 830810 i t

Page 9 of 17

PSE&G SMJ!M GENERATING SDLTIN SAFE 1T REEJmiD WORK CEDER IOG ..

l, SAIJiM LNIT 1 WD ND urrr UruT nyins:ar nnwnr1 CATION 937852 m 1 1 AEW PMP EM COGER FAIIURE DESCRIPTIN: 1 AUX FEED PMP M CIR IS LEAKING BADIX. HAS BEEN ISGMED FOR SHIET SUPERVIS@.

830721 CORRBCTIVE ACTICN: REPAIRED & REPIKED 'IiBE 'IURNS. 830812 i

937854 m 1 '12 BCRIC ACID XFRPMP i

FAIIIEE DESCRIPTIW:- 12 BORIC ACID TRANSFER INP HAS A BAD SEAL LEAK. 830721 CCRRBCTIVE ACTICE: REPIKED MBCHANICAL SEAL, REINSTALTID & REALIWED PLMP. 830730

!- 937903 m 1 1C D/G SW 'IO COOLERS FAIIURE DESCRIPTIW: INLET LIKE LEAKING SERVICE WIR FRCM UPPER FIANGE & 13SW39. 830727 CNRBCTIVE ACTICN: REPAIRED EKLE IN LINE. 830809 i

i 938125 m 1 15 CCN ECU SW IJC 1

! FAIIURE DESCRIPTIN: CUTLET EM LINE BEFORE 15SW223 APPROK " HOG IN PIPE. 830728

) CORRBCTIVE ACTICN: PAD WRrmn OLTfSIDE T SW LINE, BELZCNA INSIDE. REM 0d!D 'IUBE BUtOLE FRCM 15SW23 E PEREGMED SNfISFACICRY Mr & INSERVICE HYDRO. 830909 l

I 919676 PD 1 BMS R11 & 12 APD l FAIIERE DESCRIPTICN: . IACK T DETECITE RESPCNSE MEN DETBCIOR PIACED IN PIANf VENT MCEE. 821017

CORRBCTIVE ACTICE

SENSING LINE ACCIDENTLY DISCNNE[TED AND PIDGGED DURING DCR 1ED-0014. AISO

! RELIEF VALVE IJiAKING. REPAIRED RRLTw VALVE A10 RBCCBNBCTED SUCTICE LINE. 830324 1

4 i

Page 10 of 17 1

i 1

L _m.

PSE&G SALEM GENERATING STATICN SAFEIY RELATED WORK GOER IOG .

SAIIM UNIT 1 WO NO DEPT UNIT EQUI 1HENE IDENTIFICATIN 922016 m 1 VALVOP, ISJ67 FAIwRE DESCRIPTIW: VALVE CPERA'KR BROKEN. 830116 CuceLnVE ICTIW: REPLACED MANUAL HANDWHEEL BEAR AND 'IOBOUE SWIIGl. TESTED SAT. 830117 922275 m 1 13 CC PWP FAIwRE DESCRIPTICN: Cw BOARD SEAL LEAKING. 830525 CuoeA;nVE ICf1CN: REPIACED QJfBOARD SEAL AND THRUST BEARING. 830526 922373 10 1 13 C PWP FAIwRE DESCRIPTICN: PUMP HAS BAD SEAL LEAK. 830518 1

CuoeL'nVE PCfICN: REPIACED INBOARD SEAL. 830526 922522 ID 1 PRZR ILVEL 4 FAIw RE DESCRIPTIW: PZR LEVEL INITIATES IIM ALABM CN OVERHEAD, GIVES LEIDWN ISOIATICN WITH NO INDICATED LEVEL CHANGE. CCNDITION 00 CURS WITH ANY CHANNEL SELECfED. 830505 i

CORRECTIVE PCTIW: REPLACED LEAKING CAPACTIURS C8 MO C9 IN ISOLAIOR IIM-459E S/N 584. TEST SAT.

830527 922600 MD 1 CCNP AIR IOCK EL 100 FAIwRE DESCRIFFICN: FAILED SEAL GECK. 830513 Cueel;nVE ACTICN: REPIACED SEALS AND NkTUSTED DOOR. 830514

! 922621 MD 1 15 SW PUMP STRAINER FAIwRE DESCRIPTIW: STRAINER HAS 25 PSI DIFFERENTIAL. 830510 CuoeL'nVE ICfICN: CLEANED 'IUBES AND REPIACED SH&S. 830510 3

Page 11 of 17

____ _ _ -. __ _ _ _ - _ - _ _ - - . - - _ _ - - - . -. _ . __ ~. .. ,

4 PSE&G SALEM GENERATING STATION SAFETY RE1ATED WORK WDER IIG. ,

SAIJiM WIT 1 WO NO DPEr UNIT EQU1M1ENT 1UtNnY1 CATION -

922659 m 1 16 SW PWP STRadNER FAIw RE DESCRIPTIm: STRAINER HAS BRNEN SHETJ1 PIN. 830525 CNRECPIVE ACTICN: REPLACED UPPER DISTRIBUrIN PIATE AND UPPER WEAR SH&S. 830526 922917 PD 1 VALVOP, 121E18 i FAIIURE DESCRIPTIW: VALVE HAS SHUR DOICATICN CN CCNTHOL BOARD. 830316 i

CNRECTIVE ACTIN: REPLACED BAILEY POSITI N ER, CALIBRATED AND STR NED SAT. 830322 f

i 922924 PD 1 BMS 1R21

]

i FAIIURE DESCRIPTIW: 1R21 HAS FAII2D. 830316 i L

C@RECTIVE ACTICN

REPIACED DEFECIDR AND CALIBRATED. 830316

922934 PD 1 VALVE llSW305 FAIIURE DESCRIPTIW: VALVE DTS NOT WORK PROPERLY IN AUIO. 830315 i

i CORRECTIVE ACTIW: THE PRESSURE CCNrRnrJRR SEPPOINT WAS SET AT 142 PSI INSTEAD OF 130 PSI. RESET

! 'IO 130 PSI Ato CHECKED (PERATIN SAT. 830315 923072 PD 1 VAINOP, 13MS18 l FAIIURE DESCRIPTIN: AC'IUATOR DIAPHRAW BION OUT. 830310 CORRECTIVE ACTIN: REPIACED DIAPHRACE AND ACIUA'IOR PACKING. STROKE CHECKED SAT. 830301 f

! 923100 PD 1 RMS 1R41B l r

FAIIURE DESCRIPTIW

GAbNEL TAII2D HIGH. 830306 CORRECTIVE ACTICN: REPIACED AICA'S IN IOCAL CCNrRarIER. 830307 i

Page 12 of 17 t

i

P S E &' G ' SALEM GENERATING SMTION SAFE 1Y REIATED NORK OEOER IOG ,

SAIDI WIT 1 WD NO Derr NIT EGnH4ENT TnmnrICATIN 923133 PD 1 RMS APD (R11 & 12)

FAILURE DESCRIPTICN: APD BREAKER KEEPS 'IRIPPING. 830226 CuwFcriVE ACTICN: INSTAT.Tm NEW CODE APD PLMP. 830228 923179 PD 1 VALV0P, 1PS1 FAIIURE DESCRIFfICN: VALVE WILL N0f CCNTROL IN M710. 830217 CCRRECTIVE ACTIN: REPIACED MAN /AUID MTULE AND CCNTRNIRR IPC-455F. 830222

923199 PD 1 12 ACCUMUIA'IOR PRESS FAILURE DESCRIPTIN

PRESSURE ATARM CHB IN AIARM. PRESSURE INDICATICN IN SPEC. 830220 CORRECTIVE ACTIN: REPIACED CCMPARA'IOR S/N 60-232 WITH S/N 624. 830221 923206 PD 1 VALVT, ICV 35 l

FAILURE DESCRIPTIN: VALVE CXNrRnrIRR IS 'IRIPPED 'IO MANUAL MO WIIL NOP GD INTO MTIO. 830220

CORRBCPIVE ACTIW: REPIACED CAPACITORS C21, C26 AND TRANSISIM Q13 IN POWER SUPPLY & CCNfRnrIER 11C-114B S/N 277. 830221 i

j 923512 m 1 VALVE 12MS175 FAILURE DESCRIPTICN: VALVE HAS BRNEN SPEM. 830318 CORRECTIVE ACTICN: CUT OUT BCNNET, REPIACED DISC AhD STEM AND RE-NEIDED BOWETf. 830402 i.

i .

I I Page 13 of 17 l 4

4

. - ~ . PSE&G SALEM GENIRATING STATION SAFEIY REIATED WOflK GtDER IOG .

SAI2M LNIT 1

~

WD NO DEPT UNIT FQUIPMENT lurNTIFICATION 923536 PD 1 BMS 1R41A FAIIURE DESCRIPTIN: CHANNEL HAS HIN AND IIM FIIN AIAIM SIMLTANE00 SLY. 830320 CORRBCTIVE ACTIN: APD PUMP SEIZED. REPIKED PtNP S/N 95024 WrIH PUMP 81557.A117USITD FILN.830321

923616 PD 1 INS 1R41 APD l FAIIURE DESCRIPTIN

APD WIT SEIZED. '830321 CORRECTIVE ACTIN: REPIEED PLNP S/N 95024 WITH NEW PLEP S/N 81557. 830321 t

4 I

1 J

f 4

i

• j i

Page 14 of 17 4

SALEM UNIT 1 OPERATIONS

SUMMARY

REPORT AUGUST 1983 Unit No. 1 began the month at 100% power and continued full power operation until the reactor tripped on August 11. Excessive amounts of grass had accumulated at the Circulating Water Screens, causing a rapid loss of five of six circulators. During the rapid load reduction, No. 11 Steam Generator Feedwater Pump tripped on low suction pressure which resulted in a steam flow / feed flow mismatch on No. 13 Steam Generator, causing a reactor trip. Following the trip, when the Group Busses transferred to the Station Power Transformers, a blackout loading of the Vital Busses was initiated by the Second Level Undervoltage Protection.

Subsequent investigation revealed that the initiation of the blackout loading occurred because the large addition of load to the tranformers caused a momentary reduction of the transformer output to 89% of the rated voltage. In accordance with an engineering recommendation, the no load tap settings on all four Station Power transformers have been raised from position 4 to position 5. Also, the balance voltage on the Load Tap Changers (LTC) has been increased. The change in tap positions and LTC balance voltages elevated the voltage of the Station Power Transformers. This elevated voltage provides an additional margin for transients encountered during a fast transfer of load initiated by a unit isolation.

The Circulating water screens were cleared and a unit startup was commenced. Unit No. I was returned to full power operation on August 15, and continued full power operation until August 18, when power was reduced to approximately 96%, due to problems encountered with the Electro-Hydraulic Control System (EHC) during turbine valve testing.

Investigation revealed that a short in the valve test circuit of No.

13 East Interceptor and Reheat Valve had caused overheating of the EHC circuitry. This, in turn, caused ll5VAC to be applied to the -15V logic circuitry causing failure of logic cards.

Unit No. 1 continued to operate at reduced power when the reactor tripped on August 22, during surveillance testing of the Solid State Protection System. During the testing, when the "B" Reactor Trip Breaker was closed, and the "B" Reactor Trip Bypass Breaker was opened, the reactor tripped. Several trip breaker open and close operations had been performed during the testing. Investigation revealed that due to a missing right hand guardrail guide latch, the breaker moved slightly out of its normal position. The misalignment caused the cell switch on the "B" Reactor Trip Breaker to close without the breaker being racked out. Upon opening the bypass breaker, the position of the trip breaker cell switch gave indication to the turbine control Page 15 of 37

system that the "B" Reactor Trip Breaker was racked out with the "B" Bypass Breaker open. Therefore, the turbine control system tripped the turbine as per design. When the turbine actually tripped, reactor power was still greater than permissive setpoint P-7. This caused the Solid State Protection System to trip the reactor.

Due to the problems associated with the "B" Reactor Trip Breaker, an inspection was conducted to determine the condition of the other reactor trip and bypass breakers. On the Unit No. I breakers, three of the four right side guardrails were found to have missing rail stops. Functional testing was performed on all the breakers after the repairs were completed. During the subsequent testing the "B" Reactor Trip Breaker failed to close on two occasions. In this case the left side-rail stop was found to be the problem. The problem was corrected and all the breakers were tested satisfactorily.

In the interim, because Unit No. 2 had shutdown on August 19, for investigation and repair of a stator cooling water leak, the Unit No.

2 EHC console waa placed in Unit No. 1 to allow full power operation of the unit. Unit No. 1 was restored to full power operation on August 26, and continued to operate at full power for the remainder of the month.

{

Page 16 of 17

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

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: May 31, 1984

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

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

YES NO NOT DETERMINED TO DATE 9/1/83 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 17 of 17

.~ ^

O PSLEG Public Service Electric and Gas Cornpiny P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 10, 1983 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET 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 August 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 - Salem 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 l of l7 8-1-7.R4 The Energy People '$l mm .