ML20073F323
| ML20073F323 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/10/1983 |
| From: | Miller L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20073F297 | List: |
| References | |
| NUDOCS 8304150470 | |
| Download: ML20073F323 (16) | |
Text
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q AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 4
Unit Name Salem # 1 Date April 10, 1983 Completed by L.
K. Miller Telephone 609-935-6000
]
Extension 4455 j
Month March 1983 i
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
l 9
0 24 0
10 0
25 0
11 '
0 26 0
12 0
27 0
13 0
28 0
14 0
29 0
i 15 0
30 0
31 0
i f
P.
8,1-7 R1 8304150470 B30410 PDR ADOCK 05000272 R
PDR.
Page 2 of 17
OPERATING DATA REPORT Docket No. 50-272 Date April 10, 1983 Telephone 935-6000 Completed by L.
K. Miller Extension 4455 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period March 1983 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) 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.
Power Level to'Which Restricted, if any (Net MWe) None
- 10. Reasons for Restrictions, if any REACTOR TRIP BREAKER PROBLEMS This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 2160 51169
- 12. No. of Hrs. Reactor was Critical 0
224.8 27950
- 13. Reactor Reserve Shutdown Hrs.
744 839.6 1812.7
- 14. Hours Generator On-Line 0
15.8 26663.5
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 557.9 79170749
- 17. Gross Elec. Energy Generated
(;MWH) 0 2760 25967610
- 18. Not Elec. Energy Generated (MWH)
(5339)
(25661) 24569192
- 19. Unit Service Factor 0
.7 52.1
- 20. Unit Availability Factor 0
.7 52.1
- 21. Unit Capacity Factor (using MDC Net) 0 0
44.5
- 22. Unit Capacity Factor (using DER Net) 0 0
44.1
- 23. Unit Forced Outage Rate 100 98.7 30.2
- 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:
UNKNOWN
- 26. Units in Test Status (Prior to Commercial Operation) :
Forecast Achieved s 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
Page 4 of 17 UNIT SHUTDOh'N AND POWER REDUCTIONS Docket No. 50-272 REPORT MONTH March 1983 Unit Name Salem No.1 Date April 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 Control Rod 83-030 2/25 F
838.6 A
1 IA CKTBRK Scram Mechanisms 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)
DOCKET NO3 g_ p,,
MAJOR PLANT MODIFICATIONS UNIT NAMEt Salem 1 j
REPORT MONTH MARCH 1983 DATE:
April 10. 1993 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT i
lEC-0723 Component Cooling Replace shell and tube
- heat exchanger with titanium plate type heat exchanger to eliminate 90-10 material degradation problems.
,lEC-0768 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 (1WL115) lEC-0776 Main Turbine Lube Install Denison flow control valves in place of hand valves in lift cil supply lines.
1EC-0838 Chemical and Volume Change pipe nipple to valve 1CV378 from Control Schedule 40S to Schedule 80S.
1EC-0930 Condensate Polishing Condensate Polishing System modifications.
lEC-0975 Safety Injection Add 100 CPM miniflow line to No. 11 and 12 Safety Injection Pumps.
lEC-1038 Auxiliary Annunciators Add RA848A input modules to the auxiliary annunciators.
lEC-1087 Waste Disposal-Liquid Add break flanges to the discharge lines of the #11 and 12 Containment Sump Pumps.
lEC-1211 Service Water Provide interconnection for service water headers for the area of the chiller condensers and emergency air compressor.
1EC-1236 Service Water Reinforce, reverse and refurbish the service water intake stop and fish gates.
lEC-1310 Control Area Air Install arc suppression diodes across Conditioning relay and solenoid coils in control area air conditioning system.
1EC-1341 Waste Disposal (Cas)
Install two T.I. recorders on RPl.
lEC-1423 Safety Injection System Replace narrow range transmitters.
1EC-1434 Main Steam Replace steam traps (M-131) located down-stream of 1MS902, IMS903, and IMS904.
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 5 of 17
MAJOR PLANT MODIFICATIONS DOCKET NO3 50-272 REPORT MONTH MARCH 1983 TNMt Salem 1 DATE_
April 10. 1983 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/935-6000 v449;
- DCR NO.
PRINCIPLE SYSTEM SUBJECT 1EC-1481 Turbine Bypass Steam Increase the time suppfession setting of (C240) the steam generator feed pump suction controls to 5.0 seconds.
1EC-1485 Electrical Penetrations Remove following spare feed thru's from electrical penetration No.1-57 feed thru Nos. I and 2-3/C #2 AWG, 17 and 18 9/C #6 AWG - use plugs and ferrules to close openings in the header plate created in place of the above feed thru's.
1EC-1504 Circulating Water Removal of waterbox ladders on both the inlet and outlet side for the Unit 1 main surface condenser.
Installation of carbon steel scaffolding supports'inside inlet and outlet waterboxes.
ISC-0011 Main Turbine Lube Oil Relocate valves for testing bearing lube oil pumps and backup seal pump.
1SC-0076 Service Water Replace all pump room coolers with coolers of different materials.
1SC-0086 Emergency Diesel Provide a replacement heater with a better, Generators more corrosion resistant sheath.
1SC-0104A Main Steam Transmitters Relocate transmitters 1PT505 and IPT506 to a solid part of the floor.
ISC-0149 Compressed Air Install unions to station air piping at containment penetration cooling coils.
1SC-0347 Component Cooling Provide motor operated valves for auxiliary header isolation valves.
1SC-0464 Fire Protection Add additional sprinkler heads in Maintenance Office storage closet.
1SC-0504 Lube Oil System Replace 11 and 12 main turbine lube oil cooler tubing bundles with alternate materials.
ISC-0650 Steam Generator Feedwater Pump journal bearings - Take new bearing Pumps #11 & 12 retainers and modify them per Franklin Institute Research Lab Report F-A5477, page 3-4.
- DESIGN CHANGE REQUEST 8-1-7.R1 i
Page 6 of 17
MAJOR PLANT MODIFICATIONS DOCKET NO3 50-272 REPORT MONTH MARCH 1983 UNIT NAME:
Salem 1 DATE:
April 10, 1983 COMPLETED BY:
n.x. yi11or l
TELEPHONE:
609/935-6000 X4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT ISC-0749 Steam Generator Alarm High steam generator bIowdown cation Setpoint Changes conductivity alarm, change from 2.0 micromhos to 0.8 micrombos; Low steam generator blowdown pH, change from 8.4 to 8.5; Steam generator inlet dissolved oxygen alarm change from 20% of range to 5 ppb.
ISC-0760 Neutron Hi Flux at Temporarily disconnect the hi flux at shut-Shutdown down alarm wire connected to Rack #59 in TB821-7 for duration of welding in contain-ment during #1 Unit refueling outage.
ISC-0894 Containment Ventilation Move test connections IVC 900 (lVC3&4),
IVC 901 (lVCl&2), and IVC 902 (lVC5&6) from inside containment to north penetration area and extend same to approximately 100' in order to perform presrure drop tests as required by Tech. Spec. paragraph 4.6.3.16.
ISC-0906 Turbine Generator Change overspeed trip setting on the Unit
- 1 turbine generator to 1854 rpm or 3%.
ISC-0932 Main Turbines Install grounding braids on the shaft of
- 1 Main Turbine L.P.
IMD-0117 Safety Injection Install manual isolation and drain valves for containment leak rate testing for ISJ123, ISJ53, ISJ60.
IMD-0120 Demineralized Water Install manual isolation valve.
10D-0004 Page Installation Install page in area of boric acid evaporator and waste evaporator control panels.
IPD-Oll2 Liquid Waste Replace transmitter with a flow element and a pneumatic flow transmitter.
IPD-0140 Radiation Monitoring Physically remove channels R6B and R20A from the Sampling Room and Chemistry Laboratory respectively.
4
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 7 of 17
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MARCH UNIT NAME:
Salem 1 DATE:
April 10, 1983 I
COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION i
lEC0723 The design function and operation of the component cooling i
system within which these heat exchangers are being replaced, has not changed from that covered in the FSAR and Technical Specifications.
No unreviewed safety or environmental questions are involved.
IEC0768 Provision of remote operations does not create any new safety hazards.
The basis for the Technical 4
Specifications are not affected.
No unreviewed safety or environmental questions are involved.
1 lEC0776 The installation of the expanded lift oil system and turning gear spray does not alter the original design i
concept of the system.
No unreviewed safety or environmental questions are involved.
IEC0838 No change to the basic design and function of the system is involved.
No unreviewed safety or environmental l
questions are involved.
lEC0930 These modifications are for the purpose of providing improved sampling capability.
No unreviewed safety or environmental questions are involved.
lEC0975 This change does not affect any safety related system or the safe shutdown of the reactor.
No unreviewed safety or environmental questions are involved.
IEC1038 This change does not affect safety related equipment.
No unreviewed safety or environmental questions are involved.
lEC1087 The addition of break flanges in the discharge piping does not change the Technical Specifications or the FSAR.
No unreviewed safety or environmental questions are involved.
lEC1211 This change provides the availability of more than one
. unit for use during an outage.
No unreviewed safety or environmental questions are involved.
lECl236 This DCR reinforces the structural integrity of the service water stop gates.
No unreviewed safety or environmental questions are involved.
Design Change Request Page 8 of 17-
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MARCH UNIT NAME:
Salem 1 DATE:
April 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION 1EC1310 This change will reduce electrical noise induced into other circuits.
No unreviewed safety or environmental questions are involved.
1EC1341 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.
1EC1423 The reliability of the transmitters is being enhanced.
No unreviewed safety or environmental questions are involved.
1EC1434 Orifices have superior operational and maintainability characteristics and are a good alternative solution for the replacement of the steam traps.
No unreviewed safety or environmental questions are involved.
1ECl481 The basic function of the equipment is unchanged.
No unreviewed safety or environmental questions are involved.
s 1EC1485 There is no compromise in safety as a result of this change.
No unreviewed safety or environmental questions are involved.
1EC1504 Due to corrosion within the Unit No. I water boxes the existing ladders must be removed.
It has been determined that these ladders are preventing the cathodic protection system from working properly.
No unreviewed safety or environmental questions are involved.
ISC0011 The relocation of the valves does not change the Technical Specificatica or the FSAR.
No unreviewed safety or environmental questions are involved.
ISC0076 Relocation to provide access for coil removal does not affect any current safety analysis nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
ISC0086 Replacement heaters will be less susceptible to corrosion.
No unreviewed safety questions are involved.
l Design Change Request l
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Page 9 of 17
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l MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 l
REPORT MONTH MARCH UNIT NAME:
Salem 1 l
DATE:
April 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION l
1SC0104A This is a safety related change because it involves moving I
a safety related transmitter and its associated tubing and wiring.
However, no unreviewed safety or environmental questions are involved.
l 1SC0149 Installation of this system does not affect any current safety analysis nor does it create any new safety hazards.
No unreviewed safety questions are involved.
ISC0347 The addition of motor operators will enable more rapid and remote operation.
Handwheels will be maintained to allow manual operation.
No unreviewed safety or environmental questions are involved.
1SC0464 This change does not alter the function or operation of the fire protection system.
No unreviewed safety or environmental questions are involved.
1SC0504 The replacement tube bundles will upgrade these heat exchangers.
No unreviewed safety or environmental questions are involved.
r l
1SC0650 This design change does not affect any presently performed i
safety analysis nor does it create any new safety hazards.
l No unreviewed questions are involved.
I ISC0749 The setpoints do not enter into the logic for the basis of l
any Technical Specifications.
No unreviewed safety or environmental questions are involved.
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1SC-760 No unreviewed safety or environmental questions are involved.
\\
ISC0894 This change does not affect any presently performed safety j
analysis nor does it create any new safety hazards.
No l
unreviewed safety or environmental questions are involved.
t ISC0906 This change does not affect the safe operation of the turbine generator or any safety related equipment.
No l
unreviewed safety or environmental questions are involved.
I 1SC0932 This DCR provides grounding braids for turbine shaft grounding.
No unreviewed safety or environmental questions are involved.
Design Change Request Page 10 of_17
-~
i MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 j
REPORT MONTil MARCII UNIT NAME:
Salem 1 DATE:
April 10, 1983 COMPLETED BY:
L.K. Miller i
TELEPHONE:
609/935-6000 X4455 i
- DCR NO.
10CFR50.59 SAFETY EVALUATION 1MD0ll7 Installation of the test isolation valve does not change the system operating characteristics.
No unreviewed
]
safety or environmental questions are involved.
IMD0120 The addition of these valves enhance maintenance but do j
not alter the basic function or design.
No unreviewed j
safety or environmental questions are involved.
LOD 0004 No safety function, analysis, or margin will be adversely j
affected.
No unreviewed safety questions are involved.
l 1PD0112 This change does not affect any safety related systems or 3
the safe shutdown of the plant.
No unreviewed safety questions are involved.
i IPD0140 These monitors do not perform a safety function and are l
not intended for use during accident conditions.
No unreviewed safety or environmental questions are involved.
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e Design Change Request Page 11 of 17
PSE&G SALDi GENERATING STATION Page 12 of 17 SRFBIY REIATED NORK ORDER IOG SALD4 UNIT 10.1 NO ?O DEPP UNIT EQUIlEENT IDDTTIFICATICU 905623 M
1 CON 2. AIR IOCK, EL.100 FAIIURE DESCRIPTION: INSPECT PER CBl RECOtt H OATIONS. ALSO REPACK SHAPES AND REPLACE MISSDE ACCESS COVER BOLTS.
CDRRECTIVE ICTION:
COUID ?X7f REPACK SHAPTS BUT TIGHTENED PACKDE NETTS. REPIACED DOOR SEALS ON INNER AND OUTER DOORS.
905644 M
1 RX FLUX 'HID1BIES FAILURE DESCRIPTION: EDDY CURRDTT TEST ALL UNIT 1 FLUX TIIDmTPS 830111.
CDxRtLnVE AcrION:
TEST COMPIITE. 56 THIMBLES DONE. 2 WERE CIOGGED A?O WERE NOT DONE.
830111.
908725 M
1 VALVE, llSW223 FAILURE DEDCRIPTION: DISASSEMBLE, INSPECT AND PEPAIR AS NECESSARY.
CORRECTIVE ACTION:
FOUND 'IUBE SHEETT BADLY CDRRODED DUE 'IO GRAPHITIZATION, 'IUBES ANT SHROUD DAMAGED DUE 'IO CAVITATION. RB0VED TUBE ASSEMBLY AfD INSTAT.TFD TUBE SHEE.T SPACER.
908979 M
1 VALVE, IPR 1 FAIIURE DESCRIPTION: 1PR1 IIAKS THROUGI. 821018.
COxxtLnVE ACTION:
RD10VED BURRS FIDI CAGE SEAT AND CLEANED VALVE IITTERNAIS. REPIACED CAGE AND BONNETT GASKETTS. 821104.
914790 M
1 VALVE, 11VC19 FAILURE DESCRIPTION: REMOVE VALVE 11VC19 AND REIOCATE WITH VALVE 21VC19 FRRK 10. FA138. 821222.
CORutLnVE ACTION:
COMPIEfED AS REQUIRED BY DR FO-82-1317. 830114.
917279 M
1 11 OC ROOM COOLER FAILURE DESCRIPTION: ROOM CDOLER HAS SERVICE VRTER LEAK. 821004.
CORutLnVE ACTION:
OPENED COOLER AND CUT AWAY SOME PORPION OF FINNED FRTERIAL 'IO IDENTIFY LEAK IOCATION. REPAIRED LEAK WITH BELZONA. 821120.
PSE&G SALDi GENERATDU STATION Page 13 of 17 SAFEIY REIATED WORK ORDER IDG SALD4 UNIT ?O.1 NO NO DEPT UNIT EQUIPf22Tf IDHTflFICATION 925409 M
1 VALVE, 13MS167 FAILURE DESCRIPTION: CANtK7f GET CIDSED INDICATION IN C07 TROL ROOi STEAM GENERA'IOR RF"/RL OR OVERHEAD LIGHTS.
CORFW'PIVE ACTION:
FF%T'P THE REIAYS THAT WERE OPENED ON DIERGENCY SIGNAL.
927335 M
1 FIRE BARRIER PDETRATIONS FAIIERE DESCRIPTIOI: SEAL FIRE BARRIER PDETRATIONS 1419A2008S, 9S,12S, AND 13S.
CDxxtLnVE ACTION:
PHEIRATIONS SEATm.
930923 M
1 PRESSURIZER COtTfROL HEATERS FAIIURE DESCRIPTION: CONTROL IEATERS KEEP TRIPPRU OUf.
00xxtLnVE ACTION:
NANED, TmRICATED AND PERFOH4ED M3D ON BREAKER.
939132 M
1 D4 ERG. COtTIROL AIR COMP.
FAILURE DESCRIPTION: DCP 1SC-0842 REIUBE INNER AND APTER COOLER 17ITH MATERIAL AVAIIABLE ON SITE.
821019.
COxPUr.LVE ACTION:
'IUBE SHEET SH7f OUP TO BE REIUBED. REINSTAT.Tm. SEE 988097 AND 984743.
984743 M
1 D1 ERG. OJNTROL' AIR COMP.
FAILURE DESCRIPTION: INSPECT ALL VALVE CAGES DISCS AND ASSDSLY PARTS EDR OXIDATION / DIRT DAMAGE.
INSPECT CYL WALL WHEN CAGES RDOVED. MEASURE PISION RING PER INST. MANUAL.
CORxtLnVE ACTION:
PISION RINGS MEASURE 1.5 WIDE HP, 2 5/16WI DE LP REPIACED GASKETS, OIL FILTER, AIR INTAKE FILTER, 2 CHECK VALVES Ato CHANGED OIL. SEE WO 939132 AND 988097.
1 985916 M
1 VALVE, 1GBil FAILURE DESCRIPTION: CONDUCT LIPT SEAL TEST.
i CDRxtLnVE ACTION:
REPLACED VALVE WITH NEW FARRIS VALVE SET AT 152 PSIG.
PSE&G SALEM GE!NJG STATION Page 14 of 17 SAFEIY REIATED NOPE ORDER IOG SAID1 LWIT NO. 1 WO NO DEPT UNIT D2UIH ETT IDD EIFICATION 988097 M
1 DE. CONTROL AIR COMP.
FAIIURE DESCRIPTION: REIUBE IST D2!ER COOLER DUE 'IO EDDY CURRa'T RESULTS.
1 TUBE LESS THAN 20%, 55
'IUBES 20-50%, 85 'IUBFS 50%, 8 'IUBES GREATER THAN 50%.
CORRWIVE ICTION:
Purim INNER COOLER BUNDLE, REBUILT MO REINSL TJm.
SEE 939132 AND 984743.
991788 M
1 VALVE, 101145 FAIdJRE DESCRIPTION: VALVE LEAKS THPOUGH.
CORRECTIVE ACTION:
LEAK THROUGH ON 1 01149. VALVE SEATS hTRE REIAPPED MD STDi WAS REPIACED ON 101149 993129 M
1 12 BCP FAILURE DESCRIPTION: INSPECT, CLEAN AND NATERPROOF MDIOR BEARING INSUIATION AS PER WESTINGE10USE LETTER PSE-78-559.
CORFFT'PIVE ICTION:
riPANED MO REINSUIATED THE UPPER BRACKET DONELS AS PER IRITER. 821109.
993198 M
1 13 OIILLER RECIRC. PLNP FAILURE DESCRIPTION: MEGGER FDIOR. ARC APPEARED Wh'N FDIOR WAS STARTED.
CDHRarr1VE JCTION:
FDIOR SHIPPED 'IO OUTSIDE FACILITY EOR REPAIR.
919543 P
1 FC IOOPil DELTA T-TAVE CHI FAIIURE DESCRIPTION: IBS-411GI TRIP POINT OUT OF SPEC.
COxaELnVE ACTION:
REPIACED CAPACI'IORS C2, 3, 4, 6, 7, 8, 9, NO 10 SLEEA'IOR I'IO-411E AND I'IM-412T.
919570 P
1 FEED FLON 01 II, 14 S/G FAILURE DESCRIPTION: G ENNEL OUT OF CALIBRATION. 821106.
CDRxtLnVE ACTION:
REPIACED SIGAL ISOIA'IOR 1FM-541C. RECALIBRATED AND ANUSTED QBNNEL.
821106.
PSE&G SAIDI GENERATING SI'ATICN Pagc 15 of 17 SAFETI REIATED WORK ORDER IOG SALD1 UNIT NO.1 WO NO DEPT UNIT EQUIPMD.T IDENTIFICATION 919607 P
1 VALVEOP, 145R15 FAILURE DESCRIFFION: DIAPHRAM LEAKING. 821214.
CONxtL:nVE ACTION:
REPIN'm DIAFURAM AND SET STROKE OF VALVE. 821220.
919888 P
1 PZR LEVEL 00NI'ROL IIC-459D FAIIURE DESCRIPTION: CHANNEL OUT OF CALIBPATION. 821206.
CDuxn;nVE ACTION:
REPI/cm C2 AND C3 IN IIC-459D. 830104.
919946 P
1 1PRI CONTROLLER FAIIURE DESCRIlTION: IPC-456 elf TRIPS OUT OF SPEC. 830103.
00xFEunVE ACTION:
REPIACED COMPARA'IOR SNG 0205 WITH SN1158. 820102.
930331 P
1 ACCLNUIA'IOR, #14 FAIIURE DESCRIPTION: HIGI/IUW LEVEL AIABM OI-D WILL NOT AIItRM ON HIGI LEVEL.
CORieL'nVE ACTION:
REPLACED C2 AND C3 IN IIC-934D/H PCUER SUPPLY BOARD. REPIACED IIC-935D/H SW G0121 WIMI SW 669.
930514 P
1 BMS, 1RllA FAIIURE DESCRIPTION: CUANNEL IN AIABM CORRECTIVE ACTION:
REPIACED D2rECIOR AND CALIBRATED. EDUND THAT 'IIIE Dt;rn;10R HOUSING WAS COUTAMINATED DDOONNED HOUSING AND RE'IURNED CHANNEL 'IO SERVICE. 82/12/06.
930722 P
1 FEED FLON, 14 S/G OI2 FAIIURE DESCRIPTION: INDICA'IOR OUT OF SPEC.
wxFFur1VE ACTION:
REPIACED CAPACI'IOR C2 AND C3 IN QJMPARA'IOR lEC541 A/B POWER SUPPLY S/N 00-128.
985882 P
1 VALVE, 12CA330 FAIIURE DESCRIPTION: STIOKE AND SET LIMIT SWI'ICHES AETER CAT. PERFORMS MAINT ON VALVES.
CDtoeL'nVE ACTION:
STROKED, CHECKED SFATING AND SET LIMIT SWI'ICHES
SALEM UNIT 1 l
OPERATIONS
SUMMARY
REPORT i
1 MARCll 1983 Unit I was placed in cold shutdown in February following two l
occurrences of failure of the Reactor Trip Breakers to operate upon j
receiving an automatic signal from the Solid State Protection System.
4 The unit has remained shutdown throughout March while extensive investigations of the problem have been conducted by PSE&G, the NRC, and Westinghouse.
A series of meetings between PSE&G and the NRC are in progress at this time.
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Page-16.of 17
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 1 DATE:
April 10, 1983 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month April 1983 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
December 31, 1984 3.
Scheduled date for restart following refueling:
March 11, 1984 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE 4/1/83 B) lias the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled? December 1983 5.
Scheduled date(s) for submitting proposed licensing action:
December 1983 (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