ML20097F423
| ML20097F423 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1984 |
| From: | Ronafalvy J, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8409180514 | |
| Download: ML20097F423 (18) | |
Text
...
g; AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date Sept. 10,1984 Completed by-J.
P.
Ronafalvy Telephone 609-935-6000 Extension 4455 Month.
August 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
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
P.
8,1-7 R1 Page 2 of 18
(%
8409180514 840831
//
POR ADOCK 05000272
'[/
R pm
OPERATING DATA REPORT Docket No.50-272 0
Date.
Sept. 10, 1984 Telephone 935-6000 Completed by.
J.
P.
Ronafalvy Extension 4455 Operating Status 1.
Unit Name Salem No. 1 Notes
-2.
Reporting Period August 1984 3.
Licensed Thermal Power (MWt) 3338 4.-
Nameplate Rating (Gross MWe) 1135
-5.
Design Electrical Rating (Net MWe) 1090 6.
Maximum Dependable Capacity (Gross MWe)ll24 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.
Power Level to Which Restricted, if any. (Net MWe)
N/A 10.-Reasons for Restrictions, if any N/A 1
This Month Year to Date Cumulative
- 11. Hours in Reporting Period.
744 5855 62880
- 12. No. of Hrs. Reactor was Critical 0
1237.6 34388.8
- 13. Reactor Reserve Shutdown Hrs.
0 54.5 3088.4
- 14. Hours Generator On-Line 0
1197.8 32975.7
- 15. Unit Reserve Shutdown Hours 0-0 0
- 16. Gross Thermal Energy Generated (bnGI) 0 3800023 99619394
- 17. Gross Elec. Energy Generated (bOGI) 0 1281380 32896480
- 18. Net Elec. Energy Generated (MWH)
(5029) 1201036
'31172348
- 19. Unit Service Factor 0
20.5 52.4
- 20. Unit Av:ilability Factor 0
20.5 52.4
- 21. Unit Capacity Factor (using MDC Net) 0 19.0 45.9
- 22. Unit Capacity Factor (using DER Net) 0 18.8 45.4
- 23. Unit Forced Outage Rate 100 65.8 31.8
- 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:
9-15-84
- 26. Units in Test Status (Prior to Commercial Operation) :
Forecast Achieved Initial Criticality 9/30/76 12/11/76 j
Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of-Page 3 of 18
UNIT SHUTDOWN AND POWER REDUCTIONS DockSt No.50-272 REPORT MONTH August 1984
- Unit Name Sulea No.1 Date_
Sept. 10,1984 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 Generator Liquid j
j 84-176 7-9 F
744 A
4 HA GENERA Cooling System I
I 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 j
D-Regulatory Restriction 4-Continuation of ' Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report 4
G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) i i
Page 4 of 18 i
l a
r
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH August 1984 UNIT NAME:
Salem 1 DATE:
September 10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT i
1EC-0884 Cable Trays Reroute various cables from i
cable tray 1C003.
1EC-1437 Reactor Vessel Revise design to incorporate use Internals Lifting of an integral work / access Rig platform and integral tools for engaging / disengaging the lift rig to reactor vessel internals.
1EC-1613 Reactor -Vessel Level Add capacitors to DT1842-4 board Instrumentation on the reactor vessel-level microprocessor.
l l
1EC-1649 Safety Injection Modify the existing 1SJ4 and ISJ5 valve leak-off' connections to facilitate visual inspection of valve stem leakage.
{
lEC-1672 Steam Generator Replace valve Nos. 11/12/13/14 Drains and Blowdown GB918 (D3) with new Mark F53 valves.
1EC-1686 Service Water Remove caviatation control tube bundles from 11, 12, 13, 14, 15 SW57 and SW223 valves.
1EC-1791 Fire Protection Install smoke detectors in areas.
designed PIC-1, PIC-3, PIC-4, PIC-5, PlF1, PIG-1.
. Condensate Polishing Reline embedded floor drain l
piping using corrosion / erosion resistant material' provide necessary core bores in floor for access.
1EC-1822 Safety Injection Provide an encapsulation around Weld No. RH-2246-148 for housing Furmanite.
Page 5 of 18
DOCKET NO.:
50-272 MAJOR-PLANT MODIFICATIONS.
. REPORT MONTH
-August-1984 x UNIT NAME:
Salem 1 DATE:
September-10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DCR NO.
. PRINCIPLE SYSTEM SUBJECT lEC-1869 Steam Generator Feed Upgrade the material of the Pump ik). 11 impeller to CA6NM utilizing the j
spare rotating assembly.
1EC-1882 Pressurizer Safety Replace insulation on the 6" Valve Piping-RCS locp seal piping off pressurizer with cerablanket insulation.
1EC-1889 Steam Generator Replace existing four "Rexnord" Hydraulic Snubbers hydraulic snubbers attached to steam generator with four new
" Paul Monroe" hydraulic snubbers.
1SC-0313 Service Water Modify service water pump motors to allow filling of oil reservoirs.
ISC-0363 Condensate Modify #12 Heater Drain Pump motor to allow filling of oil reservoirs.
ISC-0650 Steam Generator Modify new bearing _ retainers Feed Water Pumps per Franklin Institute Research
- 11 & 12-Pump Lab Report F-A5477.
Journal Bearings 1SC-0896 Turbine Aux Cooling Change material of tubing in Unit 1 Turbine Aux Heat Exchangers from type 90-10 copper nickel to a material more suited to our system.
1SC-0965A Reactor Head
. Design temporary shielding in accordance with Proto-Power Management Corp. proposal
- 7612000-A009.
Shielding would be installed prior to stud detensioning and removed after tensioning completed.
Page 6 of 18 L
r.-
. MAJOR PL' ANT MODIFICATIONS DOCKET NO.:'
50-272
^ REPORT MONTH
' August 1984 UNIT NAME:. Salem 1 DATE:
September 10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT ISC-ll24 Containment Spray /
Provide a hard pipe.for the Refueling Cavity containment spray cavity fill line.
Also designate a storage area for the pipe when not in use.
1SC-1231 Control Air Install in the control air system two blocking valves and two vent valves.
1SC-1239 Stator Water Install discharge isolation Cooling valves on 11 and 12 Stator Water Cooling Pumps.
ISC-1268 Hydrogen Monitoring Install ladder and platform in Unit 1 Containment to gain access to 11 and 12 Hydrogen Monitor System sensor assembly to perform maintenance.
1SC-1285 Fresh Water Replace temporary water' supply line to QA toilet facilities.
1SC-1330 Structural "B"
Install a wall and doorway in Building the old TSC to provide conference space and office space.
Page 7 of 18 I
, ~
w J. -
}
- MAJOR = PLANT MODIFICATIONS DOCKET NO.
50-272
- REPORT-MONTH AUGUST 1984 UNIT-NAME:
Salem 1 DATE:
September 10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DCR NO..
SAFETY EVALUATION 10 CFR 50.59 lEC-0884 This cable reroute does not affect the operation of any safety related equipment..No unreviewed safety or environmental questions are involved.
{-
lEC-1437 This change affects.only the Internals Lifting Rig which is not a safety related component.
This change ~is to Westinghouse specifications.. The modifications-do not modify or alter any load carrying member of the lift rig nor do they alter in any way the function of the lift rig.
No unreviewed safety or' environmental questions are involved.
1EC-1613 This change modifies circuitry installed under the RVLIS package.- No unreviewed safety or environmental questions are involved.
lEC-1649.
This change does not alter any of the Safety Injection System original design functions nor of any related components or systems.. This change does not increase the consequences of an event nor the likelihood of an-occurrence.
Therefore, no unreviewed safety or-environmental questions are involved.
1EC-1672 This change upgrades the valves used.
No unreviewed safety or environmental questions are involved.
1EC-1686 This change removes bundles allowing the valve to operate without interference.
No unreviewed safety or environmental questions are involved.
1EC-1791 This change expands the fire protection capabilities of the plant.
No unreviewed safety or environmental questions are involved.
1EC-1813 This change involves piping repair in a non-safety related I
building.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request Page 8 of 18 I'
- I-
___m.
- DCR NO. -
SAFETY EVALUATION 10 CFR 50.59 1
~
1EC-1822 This change does not alter'the original design, function,
~
or intent of the Safety Injection System..This-change does not increase.the likelihood o; an occurrence, nor the consequences of an event.
Therefore, no unreviewed safety-i l'
or environmental questions are involved.
.lEC-1869 This change in.the material of the impeller of No. 11 Steam Generator Feed Pump does not affect any presently performed safety analysis nor does it create any new
. hazards.
No unreviewed safety or environmental questions are invovled.
1EC-1882 The insulation being installed. restores 4the original inculation on the piping.
The insulation meets the requirement of Nonmetallic Thermal Insulation for Austenitic Stainless Steel as outlined'in Reg. Guide 1.36.
No unreviewed safety or environmental questions,are involved.
lEC-1889 The new snubbers have the same design load capacity and perform ~the same function.
However, the new snubbers are fitted with "tefzel" seals.which has a life expectancy of forty years.
No unreviewed safety or environmental questions are involved.
ISC-0313 The change in the upper bearing oil fill piping will not affect the operation of the motors.
No unreviewed safety or environmental questions are involved.
1SC-0363 The change in the lower bearing oil fill piping will not affect ~the operation of the motors.
No unreviewed safety or environmental questions are involved.
1SC-0650 The change is in accordance with the Franklin Institute Research Lab.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request i
i Page 9 of 18
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59 ISC-0896 This change does not alter the design, performance, or operation of the Turbine Aux. Control-System.
No unreviewed safety or environmental questions are involved.
ISC-0965A The lead blankets are used only in~ Mode-5.
The RV Head Lift rig design meets the guidelines of NUREG 0612,
" Control of Heavy Loads at Nuclear Power Plants."
The head lift rig is not safoty related.
This DCR introduces plastic material into the containment.
Its use is acceptable because it is used with the plant in cold shutdown only, the material is not permanently installed and will be removed prior to startup, fire extinguishing materials are available in the. area, and the area _is patrolled by a roving fire watch.
No unreviewed safety or environmental questions are involved.
1SC-1124 The installation of the support structure, angles, plates, anchor bolts and washers does not affect any presently applied safety feature.
It also does not create-any new safety / fire hazards.
No unreviewed safety or environmental questions are involved.
1SC-1231 The new valves make the Type "C" and Type "A"
leak tests simpler to perform on CA 330 valves.
No unreviewed safety or environmental questions are involved.
1SC-1239 This modification does not alter any plant process or discharge and will not affect the existing plant impact.
No unreviewed safety or environmental questions are involved.
1SC-1268 This modification does not alter any plant process or dischargo and will not affect the existing plant impact.
No unreviewed safety or environmental questions are involved.
The telescoping ladders,and platforms conform to ANSI Standard A92.3 - 1980 and seismic restraints are used to negate seismic events effects.
1SC-1285 This change involves the Potable Water System which is outside the limits of the Safety Related Structures.
No unreviewed safety or environmental questions ard involved.
1SC-1330 This change involves electrical work from non-safety related' buses.
No unreviewed safety or environmental-questions are involved.
- DCR - Design Change Request Page 10 of 18
~
'ALEM GENERATING. STATION
?
ELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-07-30-033-1 SMD 1
13 CHILLER RELIEF VALVE FAILURE DESCRIPTION:
VALVE LEAKS CORRECTIVE ACTION:
REPLACED VALVE 943754 NCS 1
VALVE.1FPl47 FAILLRE DESCRIPTION:
VALVE FAILED CORRECTIVE ACTION:
REPACKED AND REPLACED BONNET GASKET 943629 NCS 1
VALVE 13GB4 FAILURE DESCRIPTION:
VALVE FAILED LEAK RATE TEST CORRECTIVE ACTION:
REPLACED PLUG, SEAT, PACKING, AND BONNET GASKET 943628 NCS 1
VALVE 12GB4 FAILURE DESCRIPTION:
VALVE FAILED LEAK RATE TEST l
CORRECTIVE ACTION:
REPLACED PLUG, SEAT, PACKING, AND BONNET GASKET 84-07-29-992-8 SMD 1
100' CONTAINMENT AIRLOCK FAILUPE DESCRIPTION:
EXTERIOR DOOR BALL VALVE LEAKr.4G CORRECTIVE ACTION:
RENEWED ALL SEALS ON VALVE Page 11 of 18
UNIT'1 WO NO DEPT UNIT EQUIPMENT IDENTlFICATION 84-06-22-306-5 SMD 1
BREAKER 326 IN PANEL 1CCDC FAILURE DESCRIPTION:
GROUND INDICATED ON NOS. 11.- 14-MAIN STEAM ISOLATION VALVES CORRECTIVE ACTION:
WIRE 3 OF 1MS208CT GROUNDED, IT WAS CUT AND REPULLED 84-07-18-518-3 SMD 1
12 RCDT PUMP l
FAILURE DESCRIPTION:
PUMP-DOES NOT RUN CORRECTIVE ACTION:
FOUND 2 PHASES SHORTED,TO GROUND; REPLACED DAMAGED LEAD OF CABLE 9900129-2 SMD 1
10 0' ELEVATION AIRLOCK DOOR FAILURE DESCRIPTION:
WELD REPAIR REQUIRED AS PER DR #MD-84-3235 CORRECTIVE ACTION:
WELD REPAIRED THREE (3) AREAS 009910291 SMD 1
1C SEC FAILURE DESCRIPTION:
TEST 18 WILL NOT RESET l
CORRECTIVE ACTION:
REPLACED CARD ASSEMBLY WITH SPARE ASSEMBLY AND RELAY K76 REPLACED 84-06-02-804-1 MT 1
VALVE lWL-96 FAILURE DESCRIPTION:
VALVE FAILED RETEST
. CORRECTIVE ACTION:
REPLACED STEM, O-RINGS, COMPRESSOR, AND D1APHRGAM Page 12 of 18
UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-05-26-399-3 MT 1
VALVE 12CA330 FAILURE DESCRIPTION:
VALVE FAILED LRT CORRECTIVE ACTION:
MACHINED SEAT AND PLUG; REPLACED BONNET GASKET AND PACKING 943761 MT 1
1SA264 FAILURE DESCRIPTION:
VALVE FAILED LRT CORRECTIVE ACTION:
REPACKED AND REP _ LACED THE BONNET SEAT 924477-8 RE 1
INCORE FLUX MAPPING SYSTEM FAILURE DESCRIPTION:
FAILED INCORE DETECTOR ON DRIVE "E" AND DETECTOR "F" IS INTERMITTENT CORRECTIVE ACTION:
REPLACED "E" DRIVE CABLE AND TIGHTENED LOOSE CONNECTION ON "F" DRIVE GLEASON REEL 84-06-24-340-6 SMD 1
12 BORIC ACID TRANSFER PUMP FAILURE DESCRIPTION:
INBOARD SEAL LEAKING CORRECTIVE ACTION:
REPLACED MECHANICAL SEAL 0099101254 SMD 1
11 CV PUMP AUX. OIL PUMP CHARGING FAILURE DESCRIPTION:
RUNS INTERMITTENTLY IN AUTO WHEN 11CV PUMP IS IN SERVICE' CORRECTIVE ACTION:
INSTALLED A NEW RECALIBRATED PRESSURE SWITCH Page 13 of 18
UNIT 1
. WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 9900139-0 SMD 1
12 CHARGING PUMP FAILURE DESCRIPTION:
SMOKE FROM MOTOR, PUMP WON'T TURN CORRECTIVE ACTION:
CHANGED OUT ROTATING ELEMENTS 009910271 SMD 1
12 CHARGING PUMP FAILURE DESCRIPTION:
OUTBOARD BEARING LEAKS CORRECTIVE ACTION:
REPAIRED SEAL HOUSING 0099101076 SMD 1
VALVE 1CV259 FAILURE DESCRIPTION:
BAD DIAPHRAGM LEAK CORRECTIVE ACTION:
REPLACE DIAPHRAGM 0099028514 SMD 1
VALVE llCV150 FAILURE DESCRIPTION:
BONNET LEAK CORRECTIVE ACTION:
REPLACED BONNET 0099028506 SMD 1
VALVE llCV151 FAILURE DESCRIPTION:
BAD DIAPHRAGM LEAK i
1 CORRECTIVE ACTION:
REPLACE DIAPHRAGM 0099101114 SMD 1
VALVE llCV156 FAILURE DESCRIPTION:
BLOWN DIAPHRAGM CORRECTIVE ACTION:
REPLACED BONNET GASKET Page 14.of 18
UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099001594 SMD 1
VALVE 1CV44 FAILURE DESCRIPTION:
VALVE LEAKING CORRECTIVE ACTION:
ROTATED DISKS 84-08-16-880-1 SMD 1
SW STRN. BACKWSH.
FAILURE DESCRIPTION:
VALVE LEAKING CORRECTIVE ACTION:
REPLACED VALVE BODY AND DIAPHRAGM 0099027755 SMD 1
VALVE 11SW99 FAILURE DESCRIPTION:
VALVE DID NOT STOP FLOW OF WATER AS REQUIRED DURING USE OF PROCEDURE 4.0.5-V-SW2 CORRECTIVE ACTION:
ADJUSTyD SPRING AND CLEANED VALVE 84-08-02-208-3 SMD 1
NO. 13 SERVICE WATER PUMP FAILURE DESCRIPTION:
THE PUMP STRAINER PACKING APPEARS TO HAVE BLOWN CORRECTIVE ACTION:
REPLACE SHAFT AND REPACKED / REPLACED OIL SEAL ON 4
GEAR BOX 1
948901 OD 1
SERVICE WATER HEADER ISOLATION VALVE (12SW23) i FAILURE DESCRIPTION:
VALVE LEAKS
-CORRECTIVE ACTION:
REPAIRED RUBBER LINING Page 15 of 18 l
UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 922458 OD 1
VALVE 11SW17 "AILURE DESCRIPTION:
VALVE LEAKS CORRECTlVE ACTION:
REPAIRED RUBBER LINING 940707-3 OD 1
VALVE 14SW13 FAILURE DESCRIPTION:
CHECK VALVE DOES NOT HOLD CORRECTIVE ACTION:
NEW CHECK VALVE INSTALLED 922459 OD 1
VALVE 12SW17 FAILURE DESCRIPTION:
VALVE LEAKS CORRECTIVE ACTION:
REPAIRED RUBBER LINING 922463 OD 1
VALVE 12SW20 FAILURE DESCRIPTION:
VALVE LEAKS CORRECTIVE ACTION:
REPAIRED RUBBER LINING 009900189-6 SMD 1
NO. 12SW20 VALVE MOTOR FAILURE DESCRIPTION:
THE MOTOR MEGGERS BAD AND HAS WATER IN ITS BAY CORRECTIVE ACTION:
REPLACED MOTOR 947253 MD 1
FC-1-32 SW EXPANSION JOINT FAILURE DESCRIPTION:
EXPANSION JOINT LEAKS CORRECTIVE ACTION:
REPLACEO 30" EXPANSION JOINT Page 16 of 18
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 AUGUST 1984 Unit No. 1 remained shutdown as the fifth refueling outage continues.
The Unit began the month in Mode 5.
No. 1 generator reassembly work was completed'on August 15, 1984.
Work that was done in support of the generator reassembly included turbine bearing inspection, exciter
-reinstallation and placing the. Main Turbine on its turning gear.
The Reactor head insulation has been replaced.
No. 11 Charging Pump has been inspected, repaired and flushed.
No. 14 CFCU has been installed.
- In-core Thermocouple. cable upgrade was completed. -Limitorque valve modifications are in' progress.
Reactor Coolant System fill and vent has been completed.
Preparations were completed for the Type A Containment Integrated Leakage Rate Test.
The test commenced on August 11, 1984 and was successfully completed on August 12, 1984.
The recirculation line from the Boron Injection Tank to the Boric Acid Tank was found to be plugged.
Efforts have been successfull in clearing the line.
Preparations began for Unit Mode change from Mode 5 to Mode 4.
Surveillance testing for the Mode change is in progress.
ion August 23, 1984, a failure of a 30" expansion joint in Service Water Bay 1 resulted in minor flooding of the Bay area and subsequent equipment damage..The expansion joint has been repaired.
In attempting to isolate the expansion joint, valve 13SW20 leaked excessively.
The valve has been removed and is in the process of being repaired.
A spacer (blank) has been installed replacing 13SW20 in order to complete surveillance testing of the Service Water System in support of Unit Mode change.
t 4
Page 17 of 18
1.*
1 REFUELING INFORMATION DOCKET-NO.:
50-272 COMPLETED BY:
J.
Ronafalvy UNIT NAME:
Salem 1 DATE:
September 10, 1984
(
TELEPHONE:
609/935-6000 EXTENSION:
4455 Month August 1984 1.
Refueling information itas 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 X
B)
Has the reload ' fuel design been reviewed by the Station Operating Review Committee?
7ES 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 l
I Page 18 of 18 b
J
.qp O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 10, 1984 LDirector, 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 1984 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
M.
pko, 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 Ap6 Page lof 18'
,I 8-1-7.R4 The Energy Peopk)
% 2169 (20V) 118 f 1