ML20072M833
| ML20072M833 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/10/1983 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8307150105 | |
| Download: ML20072M833 (21) | |
Text
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-311 Unit Name Salem # 2 Date July 10, 1983 Completed by L.
K. Miller Telephone 609-935-6000 Extension 4455 Month June 1983 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
16 0
2 0
17 0
3 0
18 0
4 0
19 0
5 0
20 0
6 0
21 0
7 0
22 0
8 0
23 0
9 0
24 0
10 0
25 0
11 0
26 0
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
31 0
Pg. 8,1-7 R1 Page 2 of 21 p t{
Ifl F307150105 830710 PDR ADOCK 05000311 R
OPERATING DATA REPORT Docket No. 50-311 Date July 10, 1983 Telephone 935-6000 Completed by L.
K.
Miller Extension 4455 Operating Status 1.
Unit Name Salem No. 2 Notes 2.
Reporting Period June 1983 3.
Licensed Thermal Power (fdit) 3411 4.
Nameplate Rating (Gross MWe) 1162 5.
Design Electrical Rating (Net MW'e) 1115 6.
Maximum Dependable Capacity (Gross MWe)1149 7.
Maximum Dependable Capacity (Net MWe) 1106 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) O
- 10. Reasons for Restrictions, if any SERVICE WATER PIPING PROBLEMS This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 4343 15049
- 12. No. of Hrs. Reactor was Critical 0
470.3 10925.9
- 13. Reactor Reserve Shutdown Hrs.
0 3.3 38.9
- 14. Hours Generator On-Line 0
459.4 10796.6
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 1109383.2 31625932.2
- 17. Gross Elec. Energy Generated (BMGI) 0 257340 10273590
- 18. Net Elec. Energy Generated (MWH)
(4477) 222553 9796200
- 19. Unit Service Factor 0
10.6 71.7
- 20. Unit Availability Factor 0
10.6 71.7
- 21. Unit Capacity Factor (using MDC Net) 0 4.6 58.9
- 22. Unit Capacity Factor (using DER Net) 0 4.6 58.4
- 23. Unit Forced Outage Rate 0
8.6 3.5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each) l N/A l
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
July 14, 1983
- 26. Units in Test Status (Prior to Commercial Operation) :
Forecast Achieved Initial Criticality 6/30/80 8/2/80 l
Initial Electricity 9/1/80 6/3/81 l
Commercial Operation 9/24/81 10/13/81 8-1-7.R2 l
Page 3 of 21 L
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311
~
REPORT MONTH JUNE 1983 Unit Name Salem No.2 Date July 10, 1983 Completed by L.K. 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 Reactor Report Code 4 Code 5 Prevent Recurrence Nuclear Service WA PIPEXX Water Problems Other 83-048 6/28 F
408.0 B
1 83-050 6/27 372.9 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)
Page 4 of 21
DOCKET NO 50-311 1
MAJOR PLANT MODIFICATIONS ikEPORT MONTH JUNE 1983 UNIT NAME:
arru 2 DATE:
JULY 10, 1983 COMPLETED BY:
L. K. MILLER TELEPHONE: 609/935-6000 EXT 4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT 2EC-0638 Fuel Handling Cranes Modify fuel handling cr.ane.
2EC-0769 Waste Disposal-Liquid Addition of electric operators to allow remote operation of three-way valves of waste holdup and waste monitor holdup tanks and operator for cross tie (lWLll5).
2EC-0839 Containment Samp Pump Add break flanges to the discharge lines of #21 and 22 containment sump pumps.
2EC-0967 4kV Buses Design of an additional level (approximately 90%) of undervoltage protection for the vital buses over the existing. protection level of 70%.
2EC-1039 Auxiliary Annunciators Add RA848A modules to the auxiliary annunciators.
2EC-1066 21 & 22 SGFP Iow Suction Remove from existing time delay relay and Pressure Alarm rewire to the SGFP low suction pressure trip time delay relay.
2EC-ll38 Station Computer Disconnect computer outputs presently transmitting RCS Delta TSAT and Delta PSAT from recorder TA-703 mounted in 2RP7 and reconnect to new recorder to be mounted in the console.
2EC-1259 480V Unit Substation Add ventilation fans to unit substation Transformers transformers 2EP-460V and 2GP-460V.
2EC-1288 Auxiliary Feedwater Aux Feedwater Pump trip initiated by low pump suction pressure.
2EC-1322 Safety Injection Replace motors on valves 21, 22 23, 24SJ54.
2EC-1336 Waste Disposal-Gas (N510)
Install two Texas Instruments recorders on RPl to monitor the pressure in the gas decay tanks.
2EC-1338 Waste Disposal-Liquid (N530 ) Install a Texas Instruments recorder on RPl to monitor the levels of reactor coolant l
drain and the Aux. Building sump tanks.
l 2EC-1340 Boric Acid Recovery (N120)
Install a Texas Instruments recorder on RPl to monitor the levels of the CVC holdup tanks.
- DESIGN CHANGE REOUEST 8-1-7.R1 Page 5 of 21
DOCKET NO3 50-311 MAJOR PLANT MODIFICATIONS UNIT NAMEg SALEM 2
' REPORT MONTH JUNE 1983 o
DATE:
JULY 10, 1983 COMPLETED BY:
L. K. MILLER TELEPHONE:
609/935-6000 EXT. 4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT 2EC-1371 Fire Barriers Modify existing vertica.1 fire barriers on El. 64' in the vital 4kV Switchgear Room by raising the top elevation to El.
79'-4".
2EC-1456 TGA-Structural Steel Install structural steel monorails to facilitate removal of condenser outlet piping and outlet waterboxes.
2EC-1458 Control Air System Reroute control air piping in TGA discharge side of the main surface condenser to facilitate condenser retubing.
2EC-1464 Heating Steam & Condensate Install break flanges and reroute piping, in TGA, discharge side of condenser to facilitate main condenser retubing.
2EC-1468 Building & Structures Remove permanently receiving area concrete overhang and levelator from west wall of TGA and north wall of Service Building.
Receiving area has previously been moved to Clean Facilities Building.
2EC-1502B Circulating Water Replacement of expansion joint between the inlet waterbox and transition piece of #21B
& 23A water circuits. The change will involve replacement of the present chlorobutyl-duck reinforced expansion joint with a chlorobutyl-polyester reinforced expansion joint. The new joints are flexible. No reinforcing rod as in the present design is necessary.
2ET-1508 Electrical Penetrations Remove plugs, caps and ferrules from 4 each spare ports on electrical penetration 2-51 and 2 each spare ports on electrical penetration 2-53 to permit passing electrical cables for eddy current testing on steam generator tubing. After testing replace new plugs, caps and ferrules.
2EC-1511 Building Drains & Vents Relocate 10" roof drain header to remove interference with the installation of the monorails.
2EC-1586 Fire Protection Install pressure test connection in gate valve 2FP275 upstream of gate in boss provided.
- DESIGN CHANGE REOUEST 8-1-7.R1 Page 6 of 21 l
DOCKET NO8 50-311 MAJOR PLANT MODIFICATIONS UNIT NAME:
SALEM 2 REPORT MONTH mmy,qn, DATE:
JULY 10, 1983 COMPLETED BY:
L. K. MILLER TELEPHONE:
609/935-6000 EXT. 445'S
- DCR NO.
PRINCIPLE SYSTEM SUBJECT 2EC-1642 Reactor Coolant Revise setpoints of #24 RCP locked rotor protection relaying.
2SC-0153 Nuclear Instrumentation Provide permanent implementation permanent spare source range detector to be used during refueling.
2SC-0608 Miscellaneous AC Supply Supply feeds to the thermocouple reference boxes from a power supply that is fed off the vital power supply.
2SC-0716A Main Turbine Auto Stop Oil Provide a backup for the auto stop oil supply pressure.
2SC-0798 Structural (Component Design areas of lifting for removal and Cooling) installation of #21 and 22 Component Cooling Heat Exchanger heads.
2SC-0813 Penetrations (Electrical)
Install drains in electrical penetration cannister termination boxes in Containment.
2SC-0831 Structural Provide a rack for spare fan coil units on containment slab at El. 130'.
2SC-0901 Containment Sump Install a containment sump pump start alarm on the overhead annunciator. This would assure operator knowledge of containment sump pump operation.
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 7 of 21 l
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-311 REPORT MONTH JUNE UNIT NAME:
Salem 2 DATE:
July 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION
-2EC-0638 Increasing the trolley rail from 25# to 80# does not affect any presently performed safety analysis or change any plant discharges.
No unreviewed safety or environmental questions are involved.
2EC-0769 This change should result in a decrease or radiation exposure to plant personnel and cause no increase of the amount of radioactive material discharged from the plant.
Ilo unreviewed safety or environmental questions are involved.
2EC-0839 The containment sump pumps are not a safety related item and do not affect the safe shutdown of the plant.
No unreviewed safety or environmental questions are involved.
2EC-0967 This design change provides an additional level of undervoltage protection for the vital busses.
No unreviewed safety or environmental questions are involved.
2EC-1039 This change is not safety related and does not affect safety related equipment.
No unreviewed safety or environmental questions are involved.
2EC-1066 This change is to improve the reliability of the system.
No unreviewed safety or environmental questions are involved.
2EC-ll38 This change is to make the Reactor Coolant System Delta "T"
sat and Delta "P"
sat information more available to the operator.
No unreviewed safety or environmental questions are involved.
- Design Change Request Page 8 of 21 L1 I
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-311 REPORT MONTH JUNE UNIT NAME:
Salem 2 DATE:
July 10, 1983 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/935-6000 X4455
- DC R N O.
10CFR50.59 SAFETY EVALUATION 2EC-1259 Provision of cooling for the 2EP and 2GP Pressurizer Heater Transformers does not involve any change to the FSAR or Technical Specifications.
Implementation of this DCR does require the penetration of a fire barrier, however instructions are incorporated for resealing to maintain the original fire rating.
No unreviewed safety or environmental questions are involved.
2EC-1288 This change enhances the reliability of the Auxiliary -
Feedwater System in the postulated event of a tornado.
No unreviewed safety or environmental questions are involved.
2EC-13 22 The motor function remains the same.
No unreviewed safety or environmental questions are involved.
2EC-1336 This change provides additional information to the operator and does not affect the function of the system.
No unreviewed safety or environmental questions are involved.
2EC-1338 This change provides additional information to the operator and does not affect the safe shutdown of the plant.
No unreviewed safety or environmental questions are involved.
2EC-1340 This change provides additional information to the operator and does not affect the function of the system or the safe shutdown of the plant.
No unreviewed safety of environmental questions are involved.
2EC-1371 This modification provides an acceptable alternate means of protecting the vital cable tray, as defined in Appendix R.
No unreviewed safety or environmental questions are involved.
- Design Change Request Page 9 of 21 L_
j
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-311 REPORT MONTH JUNE UNIT NAME:
Salem 2 DATE:
July 10, 1983 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/935-6000 X4455
- DC R N O.
10CFR50.59 SAFETY EVALUATION 2EC-1456 The monorails required by this DCR are in a non-safety related building and will not affect the safe shutdown of the plant.
No unreviewed safety or environmental questions are involved.
2EC-1458 This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
2EC-1464 This change does not affect any presently performed safety analysis nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
2EC-1468 The concrete canopy was removed in such a way as to not jeopardize any of the main steam line and it was not carried over any safety related equipment.
No unreviewed safety or environmental questions are involved.
2EC-1502B Replacement of the rigid type expansion joints with flexible joints does not affect any presently performed safety analysis.
No unreviewed safety or environmental questions are involved.
2ET-1508 Implementation of this change requires the opening of a fire barrier.
However, instructions for its resealing to maintain the required hourly fire rating are included.
No unreviewed safety or environmental questions are involved.
2EC-1511 This change to the 10" roof drain header does not affect any presently performed safety analysis nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
Design Change Request Page 10 of 21 L
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-311 REPORT MONTH JUNE UNIT NAME:
Salem 2 DATE:
July 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DC R NO.
10CFR50.59 SAFETY EVALUATION 2EC-1586 Addition of a pressure test connection does not affect any presently performed safety analysis, nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
2EC-1642 This change allows the relay to operate in the manner originally designed.
No unreviewed safety or environmental questions are involved.
2SC-0153 The installation of a permanent source range detector provides for redundant indication of neutron flux.
No unreviewed safety or environmental questions are involved.
2SC-0608 This change makes the thermocouples available for indication for verifying reactor stability during a loss of offsite power.
No unreviewed safety or environmental questions are involved.
2SC-0716A Installation of a new auto-stop relief valve improves the reliability of the Turbine Control System.
No unreviewed safety or environmental questions are involved.
2SC-0798 Installation of lifting rigs for the removal of No. 21 and 22 Component Cooling Heat Exchanger end plates does not affect building integrity or the safe shutdown of the plant.
No unreviewed safety or environmental questions are involved.
2SC-0813 This change prevents accumulation of water and prevents corrosion buildup inside the electrical penetration terminal boxes.
No unreviewed safety or environmental questions are involved.
I 2SC-0931 The structural frame is designed to support the spare fan coils and prevent them from becoming a missile in the event of a siesmic condition.
No unreviewed safety or environmental questions are involved.
l 2SC-0901 This change adds additional indication to the system.
No unreviewed safety or environmental questions are involved.
- Design Change Request i
l Page 11 of 21 k
PSE&G SALEM GS M ING STATION
.l SAFEIY REIATED WORK ORDER IOG SAIEM UNIT NO. 2 WO NO Drrr th1T EGJIPMENT IDiNrirICATIN 901648 MD 2
S/G & MSlV SNUBBERS FAILURE DESCRIPTIN:
IO200780-SAMPLE HYDRAULIC FIDID AND GIVE SM1PLES '10 PD-CHEM EOR ANALYSIS.
820722 CORRECPIVE ACPIN:
ALL S/G StEBRS SENT CUT FOR REPAIR BY CAT. MSlV OI L SAMPLED AND SENT 'ID f
CHEM-NO#m931083. 830504 901689 m
2 23 BC PLNP
' FAILURE DESCRIPTI W:
IO 200862, PERFORM BEARING INSULATIN GECK.
820723 CNRECFIVE ACTION:
PERFORMED BEARING INSUIATION CHECK IAW M8A. SAT.
830502 901690 m
2 22 BC PLMP FAIIURE DESCRIPTIW:
IO 200860, PERFORM BEARING INSUIATIN CHECK. 820723 CORRECTIVE ACTION:
PEREORMED BEARING INSUIATI N CHECK IAW M8A. SAT.
830502 901691 m
2 21 BC PLMP FAILURE DESCRIPTIN:
IO 200861, PEREORM BEARING INSUIATIN CHECK CORRECTIVE ACTION:
PERE 0RMED BEARING INSUIATIN CHEN IAW M8A. SAT. 830502 905580 m
2 INOORE INS'lWNfA' ION FAIIURE DESCRIPTIW:
REMV K2&K4 POS FIUX 'IH4BLS & REPL W/ SPARES. DEIETE K2 & CHNG 'IO GS.
REMV l
'IMEL FOR ANALYSIS. 820823 CORRECTIVE ACTIN:
C01PLETED AS PER T-89 PROCEDURE. 830427 908653 MD 2
26 SER WrR SCREEN FAILURE DESCRIPTIW:-
PULL AND INSPECP 820910 CORRECTIVE ACTION:
REBUILT SCREEN 830502 Page 12 of 21
PSE&G SALEM GENERATING STATION SAFETY RELATED NORK ORDER LOG SALEM UNIT NO. 2 WO NO DEPT UNIT BDUIPMENT IDENTIFICATION 916827 MD 2
21 RHR SUMP LEL WA FAILURE DESCRIPTICN:
ALARM UP WITH NO LEVEL IN SUMP. 821017 CURREL'nVE JCTICN:
FUND CCNIUTS CORRCDED & STICKING ON MAGNATROL DEV. FIIRTS BROKN. REPIACED W/NEW LVL DEVICE. 830503 922571 MD 2
VALVE 2PR6 FAILURE DESCRIPTI W:
CANNor CLOSE VALVE FRm CONTROL ROOM. 830509 CORRECTIVE JCTION:
FOUND OPERATE / RESET RELAY STICKING. REPIACED RELAY TESTED VALVE OPEN 'IU GME - 9.9 SEC. 830510 922793 MD 2
21 CHARGING P W P FAILURE DESCRIFFICN:
PUMP MAY HAVE RUN WITH AN ENPlY OIL RESERVOIR. 830322 CORRECTIVE 1CTION:
'IHRUST BRG DAM BUT NOT WIPD. CLEAND SUMP, LINES REP SHOES 830322 922866 MD 2
MANIPUIA'IOR CRANE FAILURE DESCRIPTICN:
GRIPPER ENGAGE LIGff WILL NOT ENERGIZE. SUSPECT LIMIT SWTIGI CN MAST.
830325 CORREUPIVE ACTICN:
REPLACED DrnL:nVE LIMIT SWIICH. TESTED SAT.
830325 922868 MD 2
CCNf AIR LOCK 130 EL FAILURE DESCRIPTICN:
INNER DOOR UPPER RnTIRR IS BROKEN.
830326 CumEL'nVE ACTION:
INSTATJm NEW RarJRR BEARING.
830326 923710 MD 2
2C EMEFGENCY DIESEL FAILURE DESCRIPTION:
'IHE NATER JACKET IS LEAKING WT OF A CWDUIT. 830409 CutstL'nVE ACTION:
REPL BOTH JACKET WTR HTRS. APPRS IffRS ENRGZD W/ ION WPR LVL CAUSING IffRS 'IO BURN OUT & LEAK. 830421 Page 13 of 21
PSE&G SALEM GENERATING STATIN SAFEIY RELATED WORK ORDER IOG SALEM UNIT 2 NO E Derr thrr EUJ1H4ENr uwwnt'ICATIN 924922 m
2 VALVE 2SJ4 FAIIURE DESCRIPTICN:
OPEN AND INSPECT INTERNALS 830413 CORRECTIVE ACTION:
OPENED, INSPECTED, ETXND INTERNALS SAT. 830428 925569 10 2
VALVE 2SA118 FAILURE DESCRIPTIm:
FAILED LEAKRATE TEST. OPEN INSPECT RENCRK AS REQUIRED. IAPPING IS PERMISSABLE 830126.
CORRECTIVE ACTIN:
CLEANED, IAPPED, BIUE CHECKED, REPACKED, AND REPIACED BWNET GASKEr 830311.
925570 MD 2
VALVE 2SA119 FAILURE DESCRIPTICN:
FAILED LEAK RATE TEST. OPEN, INSPECT, REWORK AS REQUIRED. IAPPING IS PERMISSIBLE 830126 CORRECTIVE ACTIN:
CLEANED, IAPPED, BIUE CHECKED, REPIACED BCNNET GASKET.
-925707 MD 2
VALVE 2FP148 FAIIURE DESCRIPTIN:
FAIIED LEAK RATE TEST. RENORK AS REQUIRED. IAPPING IS PERMISSIBLE 830130 CORRECTIVE ACTION:
CIEANED, IAPPED, BLUE CHECKED, REPIACED BOREP GASKET 830309 925740 m
2 VALVE 22CA330 FAILURE DESCRIPTIN:
FAILED LEAK RATE. OPEN, INSPECT, REWORK AS REQUIRED. IAPPING IS PERMISSIBLE 830209 CORRECTIVE ACTICN:
MAGINED PIDG AND SEAT RING (REPACKED AND INSTATJFD NEW BCNNET GASKET) 830310 925800 MD 2
24 BC PLMP FAIIURE DESCRIPTION:
PERFORM BEARING INSUIATICN CHECK 830113 CuceLnVE ACTION:
PERFORMED BEARING INSUIATION CHECK IPW M*A SATISFACIORY 830502 Page 14 of 21
. - = - _ _ - _ -.. _ _
PSE&G SALEM GEhMING 9IATION SAFE 1Y RELATED WORK WDER LOG SAIIM UNIT 2 WO NO DEPT INIT EQUIPMENT IDDenrICATIN 926274
.MD 2
SPARE ELECT PEN FAIIURE DESCRIPTIW:
IUIE EDDY CURRENP CABLES INIO CNIMff 'IERU SPARE E[ECTRICAL PENETRATIN. 830105 CWRECTIVE ACTIN:
EDDY CURNr CABLES INSTALL CWPL. CABLES REMNED, PIEGS REINSTID, PEN REPRESSURIZED.
830307 926318 MD 2
VALVE 21PE46 FAIIURE DESCRIPTIW:
HANGR ARM DISTORTED. CHANGE CUT HANGER ARM & PERFORM INTRNL VISUL EXAM EOR OdIER ABNORMALTIES 830111 CORRECTIVE ACTICN:
REPL HANGER, HANGER PIN, 4 BUSHINGS, & NEW COITER PIN. DISC SETA GOOD.
'IORQUED BWNET 'IO 150#.830419 927050 MD 2
VLVS 21,22W 22 FAIIURE DESCRIPTIN:
MPOIINE VALVE DISC ASDIRECTED BY ROCN4 ELL PEP 830314 CWRECTIVE ACTION:
MACHINED VALVE SEATS 830412 927145 10 2
25 OFIMff ECU FAIIURE DESCRIPTIW:
REVERSE FLOW ELEMP F-3538 'IO PROVIDE CCERECT INSTL A'IN. CLEAN FOR INSP AND REPAIR AS REQD. 830428 CORRECTIVE ACTICN:
REF0VED FIDW ELEMENT AND F0lRO NO EROSIN OR DISIERTIN. 830503 927148 MD 2
VALVE 21AF23 FAILURE DESCRIPTIW:
MACHINE DISC SEATING SURFACE AT DIRECTIN T ROCNELL REP. 830502 CORRECTIVE ACTION:
MACHINED AS DIRECTED 830502 927149 20 2
VALVE 24AF23 FAILURE DESCRIPTIW:
MACHINE DISC SEATING SURFACE AT DIRECTICN T ROCNELL REP. 830502 CWRECTIVE ACTION:
MACHINED AS DIRECTED 830502 Page 15 of 21
PSE&G SALEM GENERATING STNTION SAEEf'l REIATED WORK @ DER ILG SALEM UNIT 2 WO NO DEPT UNIT ECUIPMENT IDENTIFICATIN 927302 MD 2
24 ICP MOIOR FAILURE DESCRIFfICN:
RENOVE 24 ICP MarOR FRW UNIT 2 AND INSTAIL IT IN 12 RCP POSITIN CN WIT 1.
CutmEL'nVE ACTICN:
MOIOR RENOVED AND TRANSFERRED TO UNIT 1.
M710R INSTAILED AND ALIGNED UtOER WO# 927300. 830131 927390 MD 2
2A VITAL 460V BKRS FAILURE DESCRIPTIW:
REMOVE AIL 2A 460V BREAKERS. CLEAN AND TEST PER M3 Q & M3Z. CLEAN ALL BREAKER CUBICLES. 830214 CORRELTIVE ACTIW:
RENOVED, CLEANED, A?O REPAIRED AS REQUIRED. 830909 927393 MD 2
2B VITAL 460V BKRS FAILURE DESCRIPTICN:
REMOVE AIL 2B 460V BUS BREAKERS CutmEL'nVE ACTION:
RENOVED, INSPECTED, AND CLEANED ALL 2B 460V BREAKEPS. TESTED AND REPAIRED AS REQUIRED. 830426 927465 MD 2
UNIT 2 DIESEL GENRTRS FAILURE DESCRIPTICN:
IO 20076. EXERCISE AND 111BRICATE NO 2 UNIT DIESEL GENERATOR DAMPERS. 830224 CORRECTIVE ACTION:
CWPLETED INSPECTICN AND IUBRICATICN OF DAMPERS. 830319 927496 MD 2
VALVE 2CV348 FAILURE DESCRIPTICN:
SAUNDERS VALVE DIAPHRAM LEAYS. 830301 Cumti;nVE ACTION:
REPLACED VALVE DIAPHRAM. 830302 990923 MD 2
21S/G MMER NOZZLE FAILURE DESCRIPTIW:
PERFORM RADIOGRAPH EXAM W WE N0ZZLE WELD 820606 CORRECTIVE ACTICE:
PERFORMED RADIOGRAPHY. NO RFJECTABLE IDENTIFICATION NOTED 830325 Page 16 of 21
. ~ _ -.
PSE&G SALEM GENERATING STATION SAFETY REIATED WORK NDER IOG SAIIM UNIT 2 WO NO DEPT WIT EQUIPMENT IDENTIFICATIm
'990924 MD 2
22S/G FDWrR NOZZLE FAILURE DESCRIPTIm:
PERFORM RADIOGRAPH EXAM N WE N0ZZLE NELD 820606 CNRECTIVE ACTIN:
PERFORMED RADIOGRAPHY. RESULTS ACCEPPABLE 830325 990925 PD 2
' 23S/G EINTR N0ZZLE FAILURE DESCRIPTION:
PERFORM RADIOGRAPH EXAM W WE N0ZZLE NEID. 820606 CCRRBCTIVE ACTICN:
PERFORMED RADIOGRAPHY. RESULTS ACCEPTABLE. 830325 990926 m
2 24S/G EDWTR NOZZLE FAILURE DESCRIPTIm:
PERFORM RADIOGRAPHIC EXAM N N0ZZLE WEIDS 820606 CORFfCPIVE ACTION:
PERFORMED RADIOGRAPHY. RESULTS ACCEPTABLE. 830325 990953 2
2 RFJC10R VESSEL FAILURE DESCRIPTIN:
WDCP IMP VISUAL EXAMINATIm m ACCESSBL AREAS DURING REMIELING AS PER ASME SECTION 11. 820606 CORRECTIVE ACPIN:
RENUTE VISUAL INSPECTIN WAS OCNDUCPED. REPORT IN ISI GFICE. 830325 993022 ND 2
21 STEAM GENERM10R FAIIURE DESCRIPTIm:
PERFORM ULTRASONIC EXAM T 21 S/G CHANNEL HEAD CIADDING IAW T/S 4.4.11.2 820606 CORRECTIVE ACTIN:
CLADDING INSPECPIm PEREORMED - RESULTS ACCEPTABLE. 830325 993203 MD 2
CCNT AIR IOC 130EL FAILURE DESCRIPTIN:
INNER DOOR HAS EXCESSIVE SEAL LEAKAGE. 821121 CNRBCTIVE ACTIN:
REMOVED AND REINSTALLED SAME SEAL. 821121 Page 17 of 21
PSE&G SAIIM GENERATING S'IATION SAFEIY REIATED NORK @ DER IOG SAIIM UNIT 2
'WO NO DEPT UNIT EQUIPMENT IDENTIFICATIm 994697 MD 2
22 CHIILER FAIWRE DESCRIPTIW:
RECIRC PWP PACKING LEAKS EKCESSIVELY. 820128 CORRECTIVE ACTION:
REPIKED MBCHANICAL SEAL 820324 919616 PD 2
VLVS 21,23MS169 FAILURE DESCRIPTIW:
REPLACE VALVEOP DIAPHRAMS AND STROKE. 830206 CORRECTIVE ACTION:
REPLACED DIAPHRAMS AND RESTROKED. SAT. 830413 919619 PD 2
VLVS 22,24MS171 FAILURE DESCRIPTIW:
REPIKE VALVEDP DIAPHRAM AND STROKE. 830208 CWRECTIVE ACTION:
REPLACED DIAPHRAM, REPAIRED LEAKING QUICK VALVE EXHAUST m 22MS171. STROKED SAT. 830322 919712 PD 2
2ET-520 FAILURE DESCRIPTIW:
CHANNEL CUT T CALIBRATIN IXJRING CALIBRATIW CHECK. 830216 CORRBCTIVE ACTION:
REPLACED C2,3,4,6, and 7 in 2EM-520C. RECALIBRATIN SAT. 830216 919714 PD 2
22S/G S'IM FID G 1 FAIwRE DESCRLDTION:
CALIBRATE CORRECTIVE ACTIN:
REPLACED MJLTIPLIER/ DIVIDER 2FM-522B 830220 919909 PD 2
VALVE 23MS10 FAILURE DESCRIPTIW:
VALVE CCNTROLLER HAS NO MANUAL CUTPUT. 830225 CNRBCTIVE ACTION:
REPIKED CCNTRarJER 2PC-536C. 8130301 Page 18 of 21
PSE&G SAIDI GENERATING S'MrION SAFETY REIATED NORK ORDER IOG SAIDI UNIT 2
' WO NO DEPT WIT EQUIINENT IDENTIFICATION 919925 PD 2
24S/G S'IM DUMP A'IMOS r
FAILURE DESCRIPTIW:
GANNEL OUT W CALIBRATIN DURING CALIBRATION GECK. 830331 i
CCRRECTIVE ACTIW:
REPIACED CCNTR(YJFR 2PC-546C. 830331 919930 PD 2
2'IE-411AlB FAILURE DESCRIFFIN :
OIANNEL FOWO OUT T C\\LIBRATIN DURING CALIBRATIW. 830405 CORRECTIVE ACTION:
REPIACED 2'IM-412F, 21C-412C &D, AND 21C-411A. 830406 t
925027 PD 2
PMS 2R41B i
FAILURE DESCRIFf1W:
OIANIEL FAILED 830216 CORRECTIVE ACTIN:
CH CPR PROPERLY EKGPr 2RPl DISPLY NN-EUfCTIWAL. REPL BAD ACIA OIIP IN CNTRL R M000L. TST SAT. 830305 927603 PD 2
24 BCP SEAL LEAKOFF i
FAIIURE DESCRIPTIW:
IEAKOFF FIOW OIANNEL QTf W CALIBRATIN 830127 l
CORRECTIVE ACTION:
INSTALLED NEW PC BOARD, LVDT AND An3USTED LINKAGE. CWPIEfED CALIBRATIN.
830203 1
927740 PD 2
BMS 012R16 FAILURE DESCRIPTIW:
INVESTIGMPE 1K PIUS COUNES. 830318 CORRECTIVE ACTION:
OIECK SOURCE MECHNICLY S'IUCK IN 7EE IN POSITION. READJUSTED SWRCE CABLE &
CYCLED. SAT. 830318 994703 PD 2
OP DELTA T IOOP 21 ~
i FAIIURE DESCRIPTIW:
OIANNEL FAILED HIGI CORRECTIVE ACTIN:
NO OUTPUT FBCM 21M-412E.100tO CAPS C2&C3 BIOWN. REP ICD C2,C3,C4,C6, & C7.
1 FNCINL TST SAT. 820128 Page 19.of 21 i
1 SALEM UNIT 2 OPERATIONS
SUMMARY
REPORT JUNE 1983 The First Refueling Outage of Salem Unit No. 2 commenced on January 21, 1983, and has continued through the month of June.
Both service water headers were inspected and cleaned of biofouling in preparation for startup of the unit.
Containment integrity was established on July 25, 1983.
During surviellance testing, problems were encountered with No. 22 RHR pump motor.
These problems necessitated replacement of the motor, delaying the heatup of the unit.
i s
1 l
l Page 20 of 21 i
l
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REFUELING INFORMATION DOCKET NO.:
50-311 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 2 DATE:
July 10, 1983 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month June 1983 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
March 31, 1984 3.
Scheduled date for restart following refueling:
June 10, 1984 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO X
NOT DETERMINED TO DATE 7/1/83 B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled? February 1984 5.
Scheduled date (s) for submitting proposed licensing action:
March 1984 (if required) 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 72 I
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:
March 2000 8-1-7.R4 i
Page 21 of 21 h
~ ~. ' '
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 10, 1983 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 Specifications, 10 copies of the following monthly operating reports for the month of June 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, f=
(V-/ t . M. Zupko, Jr. General Manager - Salem Operations LKM:sbh cc: Dr. Thomas E. Murley Acting 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 21. 8-1-7.R4 The Energy People 95 2189 (20MI 11-81 E}}