ML20069C316
| ML20069C316 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/10/1983 |
| From: | Miller L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20069C299 | List: |
| References | |
| NUDOCS 8303170499 | |
| Download: ML20069C316 (31) | |
Text
'
OPERATING DATA REPORT
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Docket No. 50-272 Date March 10, 1983 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period February 1983 3.
Licensed Thermal Power (MWt) 3338 4.
Nameplate Rating (Gross MWe)
TT33 5.
Design Electrical Rating (Net MWe)
T335 6.
Maximum Dependable Capacity (Gross MWe)Tl77 7.
Maximum Dependable Capacity (Net MWe) TU75 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 672 1416 50425
- 12. No. of Hrs. Reactor was Critical 224.8 224.8 27950
- 13. Reactor Reserve Shutdown Hrs.
95.6 95.6 1068.7
- 14. Hours Generator On-Line 15.8 15.8 26663.5
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 557.9 557.9 79170749
- 17. Gross Elec. Energy Generated (MWH) 2760 2760 25967610
- 18. Net Elec. Energy Generated (MWH)
(12757)
(20322) 24574531
- 19. Unit Service Factor 2.4 1.1 52.9
- 20. Unit Availability Factor 2.4 1.1 52.9
- 21. Unit Capacity Factor (using MDC Net) 0 0
45.2
- 22. Unit Capacity Factor (using DER Net) 0 0
44.7
- 23. Unit Forced Outage Rate 96.8 96.8 28.8
- 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:
UNKNOWN
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page 2 of 3 2 8303170499 830310 i
PDR ADOCK 05000272 R
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date March 10, 1983 Completed by L. K.
Miller Telephone 609-935-6000 Extension 4455 Month February 1983 D2y Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MMe-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 71 10 0
25 0
11 0
26 0
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
l i
31 0
l
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8,1-7 R1 Page 3 of 3 2
,.y
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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 j
REPORT MONTH February 1983 Unit Nam 3 Salem No.1 4
Date March 10, 1983 Completed by L.K.
Miller Telephone 609-935-6000 Extension 4455 4
Method of Duration Shutting License Cause and Corrective l
No.
Date Type Hours Reason Down Event System Component Action to i
1 2
Reactor Report Code 4 Code 5 Prevent Recurrence Nuclear Reactor Coolant 83-012 1/31 F
186.0 A
4 CB PUMPXX Recirc Pump Motors CB PUMPXX 83-014 2/08 F
240.0 A
5 83-016 2/17 F
70.0 B
5 HA GENERA Rotor Windings Generator Generator Voltgage 83-018 2/20 F
27.1 B
5 HA GENERA Suaply i
Otler Auxiliary
)83-020 2/22 F
1.7 A
5 AD Z Z System Problems Nuclear Control Rod RB CRDRVE Drive Power Supplies i
83-022 2/22 F
17.6 B
5 Other Auxiliary AD ZZ System Proble).1s83-024 2/22 F
25.4 A
5 83-026 2/24 F
10.8 B
3 HA TURBIN Turbine Over Speed Test Nuclear Other Steam CB HTEXCH Generator Problems83-028 2/25 F
1.0 A
1 Nuclear Control Rod IA CKTBRK Scram Mechanisms83-030 2/25 F
94.6 A
1 1
1 2 Reason 3 Method 4 Exhibit G 5 Exhibit {
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)~
i i
Page 4 of 32
- 3 MAJOR PLANT MODIFICATIONS UNIT NAME:
S:lem 1 REPORT MONTH FEBRUARY 1983 DATE:
March 10, 1983 COMPLETED BY:
L.K. Miller
~
TELEPHONE:
609/935-6000 X4455' i
SUBhECT
- DCR NO.
PRINCIPLE SYSTEM Deletetemperatureconk*rollerandlow LED-Olli Chilled Water seltet relay from chiller condenser water ficw controls.
lEC-0393A Circulating Water System Alter all "TT" test connections on cordenser discharge pipe.
lEC-0490 Waste Disposal Gas Move panel 110 from El. 64' to 122' in Auxiliary Building.
lEC-0574 Emergency Diesel Generators M3dify air system to include connection to the fuel rack air booster.
lEC-0758 Radiation Monitoring System Installation of a high range plant vent radiation monitor.
1EC-0768 Waste Disposal Liquid Add electric operators to allow remote operation of 3-way valves on vaste hold-up and waste monitor hold-up tanks and operator for cross-tie (lWL115).
(
1EC-0774 Chilled Water System Modify chilled water system to comply with requirements of control's DM-S-12, Par.
5.4.
lEC-0872 "A" Building Heating Increase size of heating panel transformer from 30 KVA to 45 KVA.
1EC-0882 Service Water System Add 3/4" pressure sensing lines off of the existing service water header at the #12 Component Cooling Heat Exchanger.
1ET-0911 Nuclear Instrumentation Provide an installed spare source range detector for use in refueling outage.
lEC-1012 Component Cooling Water Provide motor operators for component cooling water pumps discharge header valve Nos. 11CC3 and 12CC3.
1EC-1013 Component Cooling Water Provide motor operators for component cooling water pumps suction header valve Nos. ICC17 and ICC18.
Provide structural reinforcement for lEC-1048 Structural concrete block walls in order to meet l
seismic qualifications.
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 5 of 32
.y.
MCKET NO:
50-272 MAJOR PLANT MODIFICATIONS UNIT NAME:
Sclan 1 REPORT MONTH FEBRUARY 1983 DATE:
March 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455'
(
SUBJbCT
- DCR NO.
PRINCIPLE SYSTEM lEC-1070 Fuel Transfer System Change wiring on system to correct problem of both pit side and reactor side winch position indicators energizing simultaneously when transfering fuel.
Provide narrow range indication for the main steam and feedwater flow on the console.
lEC-1210 Service Water Replacement of the two 16" return headers which are located below the cavitrol valves SW223.
lEC-1302 Condensate & Feedwater Replace the strainer on the suction pipe of the condensate pump with a strainer of bigger hole opening and greater effective area.
lEC-1337 Liquid Waste Disposal Install a TI recorder on RPl to monitor the levels of the reactor coolant drain
(
and the Aux. Building sump tanks.
lEC-1339 Boric Acid Recovery (N120)
Install TI recorder on RPl.
1EC-1355 Diesel System Provide a permanent source of DC power for alternate shutdown procedures for starting the diesel generators.
lEC-1367 Telephone Conduit runs between New Jersey Bell microwave trailer and telephone manhole #7.
j lEC-1377 SEC Install modified chassis into the SEC l
cabinets.
lET-1392 Overhead Annunciator The annunciator windows presently installed in Section "B" will be replaced.
lEC-1399 4kV Buses Modify short circuit bracing on the 4kV vertical lift metal clad switchgear equipment. Buses lA, IB, IC, IE, IF, 1G and 3H.
lEC-1524 Compressed Air Valve 1SA119 Add a soft rubber like facing, use EPT material, to the metal disc of check valve (s) not otherwise able to pass the Type "C" isolation valve leak rate testing.
- DESIGN CHANGE REQUEST
.8-1-7.R1 Page 6 of 32
MCKET NOs 50-2h2 MAJOR PLANT MODIFICATIONS
)
MTNW:
Salem 1 REPORT MONTH FEBRUARY 1983 DATE:
March 10. 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455'
- DCR NO.
PRINCIPLE SYSTEM SUBJECT
+.
ISC-0152 Nuclear Instrumentation Provide permanent impl'ementation of spare source range channel for refueling operation.
ISC-0247 Fire Protection Provide test circuit for lights on 1RP5 for fire protection panel.
ISC-0273 Incore Thermocouples Change the method of connecting field cable to the incore thermocouples.
ISC-0577
- 3 Unit -13kV Protection Provide a means to disconnect the two "A" System finger aux. switches when the 52G A.C.B.
is placed in the " test" position.'
i 1SC-0607 Miscellaneous AC Supply Supply feeds to ine thermocouple reference boxes from a power supply.
1SC-0743 Service Water Install 316 S.S. piping, fittings and tubing in lube oil coding system on both
- 11 and #12 Charging Pumps.
1SC-0830 Containment Steel Provide rack for spare fan coil coils.
1SC-0838 Emergency Diesels Provide suction isolation valves in line to diesel pre-lube oil pumps.
1SC-0977 Nuclear Instrumentation Disconnect high flux at shutdown alarm wire connected to TB821-7 in Rack #59 for duration of welding in containment during refueling outage. Wire to be reconnected after fuel shuffle and containment work.
1SC-1062 Structural Design or fabricate reinforcement to radiation shield beams in El. 151' #1 Unit containment access hatch.
1SC-1091 Reactor Pressurizer Relief Install a junction box (s) outside the pressurizer enclosure for the electrical cables going to 1PR6 & 1PR7 and use high temperature cable from the junction box (s) to the motor operated valves. Use present cable from containment penetration to-the junction box (s) cables lA3YAC2P-AT, lA3YACP-A, 1B3YAJ2P-B7.
k
- DESIGN iMANGE REQUEST 8 - 1 !. P.1 Page 7 of 32
N
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. MAJOR PLANT MODIFICATIONS UNIT NAMES Salem 1 REPORT MONTH FEBPUARY 1983 DATE:
March 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455'
{
SUBJNCT
- DCR NO.
PRINCIPLE SYSTEM 13C-1135 Containment Provide brackets for mounting and securing the following ladders inside Containment.
One set to be located on El. 100' and another on El. 130'.
Each set to consist of one each of the following; 10 ft.
extension ladder and step ladder of 4 ft.,
6 ft., 8 ft., and 10 ft.
IPD-0064 Eu. Control System Change wiring alarm point 0154 for NC/NO compatibility.
IPD-0138 DM Water Install check coil.
l l
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 8 of 32
gg ym X.UCR PLANT MODIFICATIONS UNIT NAMia Salem 1 REPORT MONTH February DATE:
March 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE: 609/935-6000 X4455
- CCR NO.
10CF'R50.59 SAFETY EVALUATION LED 0lll The equipment performs the same functions and meets all appli-cable requirements.
No unreviewed safety questions are involved.
lEC0393A No change to the characteristics of the condenser water box thermo-wells.
No unreviewed safety or environmental questions are involved.
lEC0490 The addition of a nipple and cap on the downstream side of the valve is an added safety feature.
No unreviewed safety or environmental questions are involved.
lEC0574 This improves the reliability of plant operation but does not alter or change either the functional requirements or the Technical Specifications.
No unreviewed safety question is involved.
1EC0758 This change will not result in an increase in the quantity of radioactive materials discharged from the plant.
Unreviewed safety or environmental questions are not involved.
1EC0768 This does not affect the structural integrity of the building or its sub-parts.
No unreviewed safety or environmental questions are involved.
lEC0774 Replacing the valve actuator does not result in any unreviewed safety or environmental questions.
lEC0872 This modification involves no systems which release liquids or gasses to the environment.
No unreviewed safety or environ-mental questions are involved.
lEC0882 The addition of these lines will not increase.the potential for any failures or malfunctions of the system.
No unreviewed safety or environmental questions are involved.
lET0911 This test duplicates a previously analyzed and approved function for use as an installed spare.
No unreviewed safety question is involved.
lEC1012 The addition of motor operators will allow more rapid and remote operation.
Handwheels will remain to allow manual-operation.
No unreviewed safety or environmental questions are involved. -
lEC1013 Changing the valve operators from manual to motor driven will not, involve any change to the FSAR, Technical Specification.
No un-l reviewed safety or environmental questions are involved.
I i
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Page 9 of 32 4 h % 57 R UEST
wa-:s. sv..
50-2)2 MAJOR PLANT MODIFICATIONS S&m1 gg77 gggg, REPORT MONTH Fcbru;ry DATE:
Mr.rch 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE: 609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION lEC1048 This change adds structural reinforcing to the block walls of a safety related structure.
No unreviewed safety or environmental questions are involved.
lEC1070 This wiring change corrects a previous DCR (lSC0025) to give accurate position indication.
No unreviewed safety or environ-mental questions are involved.
lECl207 This, is to provide the operator with increased information and flexibility for controlling steam generator level.
No unreviewed safety or environmental questions are involved.
lEC1210 This is to improve service and durability of the system by up-grading the header's material.
No unreviewed safety or environ-mental questions are involved.
lEC1302 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.
lECl337 This change provides additional information to the operator.
No unreviewed safety or environmental questions are involved.
lEC1339 This change provides additional information to the operator.
No l
unreviewed safety or environmental questions are involved.
l l
lEcl355 Provides a permanent source of D.C. power for starting the diesel l
generators.
No unreviewed safety or environmental questions are l
involved.
1 lECl367 No unreviewed safety or environmental questions are involved.
lEC1377 This change will improve the noise immunity of the electronics.
No unreviewed safety or environmental questions are involved.
lET1392 This is to improve the presentation of alarm information.
No unreviewed safety or environmental questions are involved.
lECl399 This change increases the short circuit bracing of the 4kv Group and Vital Buses to 80,000 amps.
No unreviewed safety questions are involved.
I lEC1524 The addition of a soft facing will not alter the original design function of the valves, and has been reviewed with the valve manufacturer.
No unreviewed safety or environmental questions f
are involved.
l l
\\
l Page 10 of 32 1
EI 3N CHANGE RICUEST
uuLw. hv.t 50-272
.v>JOR ?!.J.NT MODIFICATIONS UN:T NAMit Salcm 1 EEPORT MONTH February DATE:
M,rch 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:609/935-6000 X4455
- CCR NO.
10CFR50.59 SAFETY EVALUATION ISC0152 This adds spare equipment as a backup to the existing design.
No unreviewed safety or environmental questions are involved.
ISC0247 This to enhance the reliability of the fire protection panel by detecting if either of the two bulbs used to illuminate the warning windows may have burned out.
No unreviewed safety or environmental questions are involved.
1SC0273 This change is to the method of connecting the thermocouples, not the function of the thermocouples.
No unreviewed safety or environmental questions are involved.
1SC0577 This modification will eliminate the unnecessary tripping of the 13 kv bus section breaker 3-4 and 4-5, when the 52 G circuit breaker is operated in the test position.
No unreviewed safety or environmental questions are involved.
ISC0607 Provision of a vital power supply will make the thermocouples available for verifying reactor stability during a loss of off-site power.
No unreviewed safety or environmental questions are involved.
ISC0743 This is to upgrade the material.
No unreviewed safety or environmental questions are involved.
I ISC0830 This is to support the spare fan coils and prevent them from I
becoming missile hazards in the event of a seismic condition.
No unreviewed safety or environmental questions are involved.
1SC0838 The installation of these valves will not compromise the ability of the emergency diesel generators to provide power.
No unreviewed safety or environmental questions are involved.
ISC0977 Temporary alarm disconnect.
No unreviewed safety or environ-mental questions are involved.
ISC1062 This provides a rigid setting surface for the concrete shield blocks in front of the equipment hatch on the heavy equipment platform in the yard.
No unreviewed safety or environmental questions are involved.
1SC1091 No unreviewed safety or environmental questions are involved.
1SC1135 This provides a means for securing movable ladders in the containment.
No unreviewed safety or environmental questions are involved.
I Page 11 of 32
-re--.: eravar crerrem
uv..
sw..
sb.2)y FJ.JOP. PLANT MODIFICATIONS UNIT NA..E Salcm 1 V
RIPORT MONTH Februarv DATE:
M'rch 10, 1983 COPJLETED BY:
L.K. Miller TELEPHONE:609/935-6000 X4455
- DCR SO.
10CFR50.59 SAFETY EVALUATION 1PD0064 This provides for routing of an annunciator cable.
No unreviewed safety questions are involved.
1PD0138 No unreviewed safety questions are involved.
l l
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' Cr5:2N CHANGI ?.EOUIST
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PSE80 SALEM GEAdATING STATION i
SAFETT RELATE 3 NORK ORDE3 LOG 3/97/83 SORT ET DEPARTMC!T WIT, WORK ORDER I i - ~ ~ ~ ~ - " ' HO MD DEPT WIT EQUIMNT IDENTIFICATION __... _ _ _....
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903042 M 1
VALVEelSJ78 FAILURE DESCRIPTION 8 VALVE LEAKS THROUGM. VALVE VERIFIED CLOSED Ate ACTUATOR NUT BOTTOMED.
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t NO MD_ DEPT WIT, EQUIPMENT IDENTIFICATION
]
=========================
904768 M 1
VALVE. ICV 75 l
i
. - __.. CORRECTIVE ACTION 2_ VALVE WAS FLSPMINITED ON 8/1/82 N08094862 STEM Ale GASKETS REPLACED 11/28/82 NOS_
904768.
NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
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904833 M 1
VALVE.13CV315 i
I FAILURE DESCRIPTION _t VALVE LEAKS THROUGH,_.._.
i CORRECTIVE ACTION t REPLACED VALVE NITH MARK FA-129 IAN 1ED-0351.
NO NO DEPT UNIT EQUIPMENT IDENTIFICATION l
=========================
c
.907249 M. _.. _.. _.. CONT AIR LOCK EL 100... _.
1 FAILURE DESCRIPTION I ItNER DOOR HAS PIECE MISSING IN UPPER RIGHT HADe CORNER.
CORRECTIVE ACTION I CHECKED DOOR APG REINSTALLED SEAL.
NO HD DEPT UNIT EQUIPMENT IDENTIFICATION
=========================
908682 M 1
VALVE.1PR7 FAILURE DESCRIPTION t VALVE bites AND DOES NOT MAKE CLOSED LIMIT CORRECTIVE ACTION
- REPLACED PLUG ASSET 2LT. SEAT SAT.
l-i Page 13 of 32
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...__.... _P3E8G SALEM ta:EJATING STATION SAFETT RELATED NP"K OROE3 LOG 3/97/43 SORT BT DEPARTtENT, WIT, NORK ORDER 1
b NO NO DEPT WIT EQUIPMENT IDENTIFICATION
=========================
.. _ _ _. 908649.. Pt i
VALVE.13MS44 _...... _.
FAILURE DESCRIPTION
- DISASSEtSLE 13MS46. INSPECT FOR BROKEN PARTS.
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- ~ ~ 'CCRRE'CTIVE ACTION
- REPLACED MANGER [BUSHI [ A W CASKET.
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- NO ND.. DEPT.. UNIT _ EQUIPMENT IDENTIFICATION t
=========================
909354 M 1
VALVE.IIMSI78
.... FAILURE DESCRIPTION t VALVE NAS IN5PECTED DURING PREVENTATIVE MAINT REPACK PROGRAM. STEAM CUTS FOLAS ON VALVE BOUT BEYOW REPAIR.
_ __. _._... CORRECTIVE. ACTION.I_ VALVE MAS REPLACED.IN KIW..
NO NO DEPT WIT EQUIPMENT IDENTIFICATION
=====.
======s=====
99965E M 1
RX STW CLOSURE SCRENS
.. __._FAILWE DESCRIPTION
- SCPE STUDS HAVE CLOSLAFE. SCRENS THAT HAVE TO BE REERKED TO BE REMOVED... --_.
CORRECTIVE ACTION
- NO NO DEPT UNIT EQUIPMENT IDENTIFICATION
=========================
..__....._..909068 M
1 AUX PIPE TUDNEL PIPING t
FAILURE DESCRIPTION 3 REPAIR ARC STRIKES AS REPORTED ON CATALTTIC SWVEILLANCE REPORT 1191.
l CURRECTIVE ACTION
- NORK COMPLETED BT CATALYTIC.
....___ EQUIPMENT IDENTIFICATION NO ND DEPT WIT
=========================
_.. 909921 M 1
12 RCP MOTOR FAILURE DESCRIPTION
- INSPECT MOTOR FOR SIGNS OF WATER A64 CCHTAMINATION CAUSED ST CONTAIte1ENT SPRAT LINE RUPTURE.
CORRECTIVE ACTION
- DISASSEMBLED MOTOR A>m CLEANED. NO TRACE OF BORIC ACID FOUN3 INTERNALLT. HI POTTED WINDItES SAT. REASSEMBLED AND TEST RAN SAT Page 14 of 32
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_.... _ ___.-..... - -. PSEA0 SALEM Intr 4ERATING STATION i
SAFETT RELATED WORK ORO D LOG 3/97/83 i
SORT BT DEPARTMENT, WIT, WORK ORDC HD ND DEPT WIT EGUIPMENT IDENTIFICATION Ae i
======== = = = = * = = = = = = = = = = = = = = = = = = = = = = =
917000 tt 1
VALVE.11CS59. _..
FAILURE DESCRIPTION t VALVE APPEARS TD BE LEAKING THRU CAUSING 80RIC ACID BUILDUP ON PIPITS APW FLOOR.
i MARK FA-1E9 VALVE AS PER DCR 1ED-0351.
CORRECTIVE ACTION
- 11CS59 MARK FA-E7 NAS REPLACED WITH A I
l.. _
. WD ND DEPT _ WIT. EQUIPMENT IDENTIFICATION.... _.. _ _. _..
=========================
917E78 M 1
VALVE.1CVI85 FAILURE DESCRIPTION
- BOOT TO BOD 44ET LEAK.
CORRECTIVE. ACTION t. REPLACED DIAPHRAM._..
NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
j 917807 M 1
PERS AIR LOCK EL 130
._...FAILUR5 DESCRIPTION.
- ROLLER MJTS ON.D44ER DOOR. LOCK ARE -
CRACKED..
CORRECTIVE ACTION t CLOSING 000R WITH EXCESSIVE FORCE CAUSES GREATER STRAIN CH ROLLERS AS THEY ENSAGE DOOR LATCH. REPLACED ROLLERS.
NO NO DEPT WIT EQUIPMENT IDENTIFICATION
=========================
917897 M 1
1E RHR PUMP FAILURE DESCRIPTION
- EXCESSIVE LEAKAGE FROM MECHANICAL SEAL.
CORRECTIVE ACTION
- SEAL FAILURE CAUSED BT PUMPING RING SPDetING ON SHAFT APW DAMAGINS SEAL.
REPLACED MECHANICAL SEAL APG REAFFIXED PLM PUMPING RING.
NO NO DEPT WIT EQUIPMENT IDENTIFICATION
=========================
917978 M 1
EMERG OIESEL IC.
FAILURE DESCRIPTION t PRE-LUBE OIL PUMP HAS DIL LEAK.
CORRECTIVE ACTION 1 INSTALLED NEW SEAL IN PRE-LUBE OIL PUMP.
Page 16 of 32
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SAFETT CELATED NORK ORDE3 LOG 3/07/83 SORT BY DEPARTMENT, WIT, NORK ORDER ND NO DEPT UNIT EWIPMENT IDENTIFICATION
. n
=========================
- _.. 919606 M._
_1__ lt_ CONF. FAN COIL. UNIT... ___ _...
FAILURE DESCRIPTION
- WILL NOT REACH DESIRED FLON t2500 GPM,IN SLON SPEED.
CORRECTIVE ACTION
- FOLRe PLASTIC PLUGGED IN ItSN57. CLEANED OUT VALVE AM Tlet BLROLE.
e MD.MD _ DEPT. WIT EQUIPMENT IDENTIFICATION.._..._..-
=========================
922046 M 1
CONT FAN CDIL LMIT 15 FAILURE DESCRIPTION
- LON SPEED CIRCUIT BREAKER TRIPPED A FEN TIMES DURING A SINGLE SHIFT.
1 CORRECTIVE ACTION 2 DURING TEST,. PHASE.THREE.0VERLDAD FAILED ___ AFTER 17 MIWTES. REPLACED OVERLOADS DE TESTED SAT.
ND HD DEPT WIT EQUIPMENT IDENTIFICATION
.,===========================
924272 M 1
INCORE DETECTOR SYS FAILURE DESCRIPTION _t DRIVE A 5 PATH NORMAL POSITION LIMIT _ _.. SMITCH NEEDS ADJUSTMENT DRIVE.F88 NEED.TO HAVE DETECTOR APG CABLE ASSDeLIES REPAIRED.
CORRECTIVE ACTION
- REPLACED A 5 PATH. REPLACED 88F DRIVE UNIT CABLES.
ND HD DEPT UNIT EQUIPMENT IDENTIFICATION
=========================
924273 M 1
INCORE DETECTOR SYS B FAILURE DESCRIPTION
- EXCESSIVE RELAT CHATTER IN RELAYS FOR 8 DRIVE.
CORRECTIVE ACTION 3 REPLACED DRIVE COMPARATOR CARD.
-. EQUIPMENT IDENTIFICATION-.. - - -_. - _. _ = -. _. -
_ -.. ~. -
~.. - -. ~
NO NO DEPT WIT
=========================
9253%.M 1
13 COMPONENT COOLING PUMP...
FAILURE DESCRIPTION
- OUTBOARD PLMP SEAL IS LEAKING EXCESSIVELT,
. -. CORRECTIVE ACTION
- REPLACED SEAL.
S Page 17 of 32
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PSE&S SALEM wtHE"ATING STATION SAFETY RELATED WORK ORDE3 LOG 3/97/83 S3RT BT DEPARTMENT,LMIT. WORK ORDER NO HD DEPT LMIT EQUIPNENT IDENTIFICATION
.8e
=========================
_. _..._. 925415. ft.___ _.1_
. VALVE e ICV 75_.
FAILURE DESCRIPTION
- VALVE IS LEAKING AT BOTTOM PART. COULD HOT TELL EXACTLY letERE LEAK IS COMING FROM.
CURRECTIVE ACTION
- DISASSEt2 LED. CLEANED. BLUE CHECKED CAGE TO SEAT. REMOVED GALLED SPOT ON CAGE.
INSTALLED HEW BOOT TO B0te4ET GASKET.
_ _ _ _. NO HD. DEPT _LMIT EQUIPMENT IDENTIFICATION _ _.
=========================
925434 M 1
VALVE.11MS167
~~
~
FAELUREDESCRIPTION't CAte40T GET CLOSED IteICddON IN CthTROL ROOM ON STEA51 GENER TUR BEZEL OR OVERHEAD LIGHTS.
_ _ __ _.. CORRECTIVE ACTIDH t RESET THE RELATS THAT_NERE 0PEHED.ON.__ _ EMERGENCY SIGNA'.. _..._.
% e4 D e r'T UNIT EQUIPMENT IDENTIFICATION
===a=.
s===
================
925767 M 1
1A Et1 ERG DIESEL
._ FAILURE DESCRIPTION.3 LOWER RIGHT AIR. START. MOTOR DOES NOT DEVELOP PROPER SPEED..
CORRECTIVE ACTION t REPLACED STARTER MOTOR.
ND HD DEPT UNIT EQUIPMENT IDENTIFICATION
=========================
.. _ _.... COMPONENT COOLING HEATEXCHANGER.11 925769 M 1
l i
FAILURE DESCRIPTION
- SERVICE NATER LEAK IN HEAT EXCHANGER.
l CORRECTIVE ACTION 2 PLUGGED THREE TUBES. ROM 31 Ti2ES 3 Ate 11 ROM 44 TtBE 2.
EQUIPMENT IDENTIFICATION WO HD DEPT UNIT
=========================
926289 M 1
SUPPORT Al-SH-A-332 FAILURE DESCRIPTION
- ONLY SINGLE HUTS ON ANCHOR BOLTS.
CORRECTIVE ACTIDH t INSTALLED DOUBLE HUTS Ate JAM LOCKED.
Page 18 of 32
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~ P S E 5 6 SAL'EM t,...c2difMG STATION "
~ ~ ~
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SAFETY CELATED WORK ORDE2 LOG 3/07/83 SORT BT DEPARTMENT. LMIT, WORK ORDE2
' ~~~~
~-~WO HD DEPT LMIT EQUIPMENT IDENTIFICATION se
=========================
. 926302.M _ _._ 1..
SUPPORT Al-SW-S-338 FAILURE DESCRIPTION t ONLY SINGLE NUTS ON ANCHOR BOLTS.
. CORRECTIVE ACTION I INSTALLED DOUBLE NUTS Am JAM LOCKED.
WO NO DEPT LMIT. EQUIPMENT IDENTIFICATION _ _ _
=========================
928677 M 1
VALVE.11SW22
~ ~ ~
~
~
~- Fh'ILURE' DESCRIPTION 't VdLVE F5ILfD TO CLOSE FROM' ~O'NTRO'l ROOM.~
~
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C CORRECTIVE ACTION.I. INSTALLED HEW TORQUE SWITCH, TEST. SAT.
NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
.=====================================
928761 M 1
VALVE.11G84
._. _ FAILURE DESCRIPTION I VALVEWILL NOT SHUT. FULLY._letEN CALLED TO OPEN. VALVE FIRST. CLOSES.TMEN OPEH5.._.. _
CURRECTIVE ACTIDH t REPLACED OPERATOR DIAPHRAM AM SET UP FOR PROPER OPERATION.
WO HD DEPT UNIT EQUIPMENT 1DENTIFICATION
=
=======e====
928833... M
_ _.12 COMPONENT COOLING PUMP RM COOLER.. _ _ _ _
1 FAILtRE DESCRIPTION
- COOLER HAS SERVICE WATER COIL LEAK.
MED TO SUPPORT MODE 3 OPERATIONS.
CORRECTIVE ACTION
- REPAIRED TtBE LEAKS.
0
_ _ _ _. _ _... _ _ _ _...... EQUIPMENT IDENTIFICATION...
DEPT LMIT
. WD HD
=========================
930351 M 1
VALVE.11MS168 FAILURE DESCRIPTION
- VALVE CONTROL BREAKER KEEPS TRIPPING.
CORRECTIVE ACTION REPLACED VALV0P MOTOR.
Page 19 of 32
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- - _ _. _. _ -... - - - - _..PGE88. ~. -
._ - ~__-- -
i SALEM 6tNERATING STATION SAFETT CELATED WORK ORDE2 LOG 3/07/83 I.
SORT BT DEPARTMENT, WIT. NORK ORDER i'.....
._ ND HD DEPT WIT EGUIPMENT IDENTIFICATION
..8e
=========================
I'__.._..__.;
.93040E M i _ RX.. TRIP BKR A.- _... _ _.
FAILURE DESCRIPTION
- RENDYE RX TRIP BKR A FROM UNIT 1 Am INSTALL IN WIT 2.
CORRECTIVE ACTION t SMAPPED BREAKERS TEST SAT.
_..._.. __.. _ ND ND DEPT _ UNIT.. EQUIPMENT IDENTIFICATION._.__...._. _ _ _ _.. _..
=========================
930424 M 1
12 SAFETT INJECTION PUMP FAILtRE DESCRIPTION
- DWING TESTING. It SI PWP CUTBOARD BEARING TEMP WENT OVER 350 DEG WITH ALL COOLING SUPPLIES OPEN. OIL ON FLOOR.
_ CORRECTIVE _ ACTION t REPLACED THRUST BEARING.. CLEANED.E E...
. FLUSNED ALL OIL LINES ABS CLEANED OIL PLN MD ND DEPT UNIT EGUIPMENT IDENTIFICATION i
=
r===
================
, _ _ __J 965689 M 1
12 COMPONENT COOLING MX PIPING I. _. _......... _ _. _ _ _
._. FAILURE DESCRIPTION 2. SERVICE NATER PIPING MELDS DEVELOPED.__....PIDGIOLE LEAKS AFTER 1 TEAR OPERATION.
RADIOGRAPH OF WELD AREA SHOWED MAJOR DEGRADATION IN MAJORITY OF MELDS.
CORRECTIVE ACTICH I WELD REPAIRS WERE MADE ON ALL LARGE BORE PIPING. SOME SMALL BONE LINES NERE l._
_. REPLACED DUE.TO DIFFICULTT OF WELD REPAIR..
MD NO DEPT WIT EQUIPMENT IDENTIFICATION
=========================
=
1 It REACTOR COOLANT PUMP 993130 M FAILURE DESCRIPTION
- OVERNAUL APG RENORK PUMP SEALS.
CURRECTIVE ACTION
- REPLACED HD.1.2 Ate 3 SEALS.830128 WO ND DEPT WIT EQUIPMENT IDENTIFICATION
=========================
906661 M 2
22 SN PUMP STRAINER FAILURE DESCRIPTION
- OPEN Ate INSPECT.
COwWECTIVE ACTION 3 REPLACED SHOES ADS BEARING. INSTALLED NEW STRAINERS.
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PSE8O SALEM tn.nERATING STATION SAFETT EELATED WORK ORDE2 LOG 3/07/83 SORT BT DEPARTHENTe LMITe NORK ORDER
.. _ _ _. NO HD DEPT LMIT EQUIPMENT IDENTIFICATI0H O
E=EEE 3==E 3:35 R:22====33E=============
928922__M f
VALVEe 24SJ54 _....______ _.
FAILtRE DESCRIPTIDH t HOOPEN IteICATION OH VALVE WEN CTCLED FOR TEST. VALVE YERIFIED OPEN LOCALLY.
_ _. _ _. CORRECTIVE ACTION
- DlWING MAINT REPAIR VALVE FAILED TO CTCLE AT NOTOR CONTROL CENTYR. FOUDW CLOSING l
COHTACTOR TRYIHG TO PULL CLOSED. REPLACE 0 CLOSING COIL. CTCLED VALVE SAT.
WD HD DEPT tMIT..EQUIPNENT IDENTIFICATION __......
=========================
928938 M 2
21 CHILLED NTR RECIRC PLMP
.. _ _. _ _... _... _ _.. _. _ _ _... _.... _. _. _.. FAILURE DESCRIPTIDH t PUMPSM0KED W EH STARTED.
_... _ _ ____. CORRECTIVE. ACTION.t_ ADJUSTED. IMPELLER...
NO HD DEPT LMIT EQUIPMENT IDENTIFICATI0H
.===r=_.. ::._::: __::::====================..
917481 P 1
CONT PRESS RELIEF OUTLET DAMPER
/
.. __ _.. _. __.._ _...._ _. _ FAILURE DESCRIPTIDH 8. I LEX. HOSLTO DAMPER OPERATOR LEAKING CORRECTIVE ACTION REPLACED FLEX HOSE.
WO HD DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
l
. _ _ _..IPT-135 LETDOWN LINE PRESS
... ~
I 917763 P 1
l FAILURE DESCRIPTION
CORRECTIVE ACTION
\\
WO HD DEPT (MIT EQUIPMENT IDENTIFICATION
=========================
917946 P 1
RC LOOP 14 W TH FAILURE DESCRIPTION 14 LOOP WIDE RANGE TEMPtH) INITIALLT READ 25 DEGF LESS THAN OTHER LOOPS. CHA>NEL FAILED BEFORE REPAIRS INITIATED.
CORRECTIVE ACTION
- REPLACED AMP BOARD Ate RECALIBRATED.
COMPUTER CHECK SAT.
Page 22 of 32
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p SAFETY CELATED WORK ORDE3 LOG 3/07/83 SORT BT DEPARTMENT,,LMIT, WORK ORDER
. ' Ti " -'
~
WD HD DEPT LMIT EQUIPMENT IDENTIFICATION
+
=========================
_ __919540_.P.
1__ VALVES.1CV75.77,79 FAILURE DESCRIPTION
- STROKE VALVES TO VERIFT SEATING.
~ ~ ~ '
~
~
~ CORRECTIVE ACTION
i Ho HD DEPT UNIT EQUIPMENT IDENTIFICATION
=========================
91 % 15 P 1
VALVE ICV 277
' ~ ' " '--~
~
' FAILURE DESCRIPTIONt RESOLVE' PROBLEM 'WITH SHIFTING LIMIT SWITCH' ACTUATING ARM.
~
~~
~
~
___ CORRECTIVE ACTION
- REPLACED DIAPHRAM, RETIGHTENED DIAPHRAM __ BACKING PLATE HUT SET VALVE FOR. PROPER _.
OPERATIDH APE) CHECKED OPERATION OF LIMIT SWITCHES.
NO HD DEPT LMIT EQUIPMENT IDENTIFICATI0H
=====================================._
919800 P 1
STEAM DtMP TO CONDENCER
. FAILURE DESCRIPTION. *.1PT-507. CHA>NEL OUT.0F. CAL.
CORRECTIVE ACTION t REPLACED CONTROLLER S/H EO-108 WITH CONTROLLER S/H HO-114.
WO HD DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
919873 P 1
PZR LEVEL CH 3 FAILURE DESCRIPTION
- CHA>NEL READS 6% LOWER THAN CH 18 E.
CORRECTIVE ACTIDH
- OPEHED EQUALIZING VALVE TO TRANSHITTER ILT-462. CHA>MELS CHECK READIHB SAME.
REFERENCE LEG WAS HOT FILLED.
.. ~.. - - -
. _ -... _ _.. _ -.. _.. _ _ UNIT EQUIPMENT IDENTIFICATION WO HD DEPT
=========================
919875 P 1
W100 kAG E RC LLCPS FAILURE DESCRIPTION
CORRECTIVE ACTION
RTD'S WILL BE REPLACED AGAIN HEXT REFUELING OUTAGE.
Page 23 of 32
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PSE&S SALEM buCATING STATION SAFETT CELATED WORK ORDER LOG 3/07/83 SORT BY DEPARTIENT, WIT WORK ORDER WO MD DEPT WIT EQUIPMENT IDENTIFICATION
,8.
======================-==
.. _.. 919889..P.
1 _ VCT LEVEL _. __._.._......_....
FAILURE DESCRIPTICH t VCT LEVEL CHANNEL OUT OF CAL.
CORRECTIVE ACTION
- REPLACED CONTROLLER HO-152 NITH SN 277.
i
' M ND _ DEPT.. WIT EQUIPMENT IDENTIFICATI0H
=========================
919939 P 1
RX LOOP 13 DELTA T/TAVG CH3
_...... _ ~
.__.. FAILURE DESCRIPTIDH 3 CHAWEL OUT OF CAL.
__.____ ____. CORRECTIVE. ACTION.t CALIBRATED LON. LEVEL AMP.. REPLACED CAPACITORS C2.3.4.6 AIS C7 IN ITM-4316.
REPLACED ISOLATOR ITM-432G S/N 00-501 NITH S/N 90-387.
HD NO DEPT WIT EQUIPMENT IDENTIFICATION
....=====..====_====.======================== __.
925390 P 1
VALVE.14M518
.._ FAILURE DESCRIPTION 3 VALVE _CAN MOT.BE OPERATED FROM.(HE CONTROL ROOM.
CORRECTIVE ACTION I SUPPLT AIR TO VALVE MAS TURNED DOWN TO 20 PSI. OPENED SUPPLT VALVE FULLT TO GET 55 PSI. ADJUSTED BLOCK ON LIMIT SWITCHES..
WO MO DEPT UNIT EQUIPMENT IDENTIFICATI0H
-============================
925452 P 1
VALVE.11M510 FAILURE DESCRIPTION VALVE CA W OT BE CONTROLLED FROM THE CONTROL CONSOLE CONTROL CAN BE DWE AT LOCAL CONTROL PANEL.
CORRECTIVE ACTION t FOUND BLOWN DIAPHRAM Ale REPLACED.
REPLACED STRIPPED ELBON ON POSITItMER.
REPLACED PART OF INSTRUMENT LINE THAT ALSO HAD A STRIPPED FITTING.
i NO MO DEPT WIT EQUIPMENT IDENTIFICATI0H l
=========================
927536 P 1
VALVE. IPS3 FAILURE DESCRIPTION t DURING FUNCTIONAL TEST AFTER STS N00.
WABLE TO GET FULL DPEN STROKE CH VALVE.
CORRECTIVE ACTION
- REPLACED LEAKING DIAPHRAM, CHECKED SAT FRGrt CONTROL ROOM.
Page 24 of 32
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-PSE88- - - SALEM wdRATING STATION.. -
SAFETY RELATED NORK ORDE3 LOG 3/07/83 SORT BY DEPARTTGtF IMIT, NORK ORDER
~ ~~~~ ~ - ND NO DEPT 15itT~EGUIPMENT IDENTIFICATI0U' '
~
~ ~ 7 3.~
~ ~ ~ ~
======= >==================
927601 P____,1.__ STEAM FLON CH 2 _.
FAILURE DESCRIPTION t CHAT #4EL OUT OF CAL.
.. CORRECTIVE ACTION
- REPLACED IFM-523C S/H D0-240 MITH S/H FO-101. CALIBRATED CHAD 64EL SAT.
.. _.. _. _._._ _. NO NO. DEPT _LMIT._ EQUIPMENT IDENTIFICATION.._.
=========================
928612 P 1
VALV0P.13SN42
_. FAILURE DESCRIPTION.. VALVE DOESN'T CONTROL OIL TEMP IN AUTO OR MADUAL.
CORRECTIVE ACTION t FOUDG SETPOINT FOR. VALVE POSITIONER TURNED D0144 TO ZERO. RETURNED SETPOINT.70.7.6 AFTER CHECKING 11 APO 12SN42 SETPOINTS..
NO HD DEPT LMIT EQUIPMENT IDENTIFICATION
_._ __=====================================.,
928678 P 1
VALVE,13GB10 FAILLRE DESCRIPTION.t FAILED TO OrEN FROM CONTROL ROOM.. _...
CORRECTIVE ACTION
- REPLACED DIAPHRAM ADO POSITIONER PILOT.
i
. NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
. _ _ _.928990._P 1. VALVE 1NL99 FAILURE DESCRIPTION t VALVE MILL NOT OPEH.
CORRECTIVE ACTION t REPLACED FAULTY AIR REGULATOR TO SV389 letICH SUPPLIES AIR TO INL99.
= _.
ND HD DEPT LMIT EQUIPNENT IDENTIFICATION
===========':============
930292 P 1
PUMP 13 CHREING FAILURE DESCRIPTION
- SPEEDDEMAle FAILS HIGH SR4EH CONTROLLER IS PLACED IN MANUAL. UNASLE TO DECREASE SPEED AUTO OPERATION APPEARS SAT.
CORRECTIVE ACTION
- REPLACED MANUAL / AUTO STATION 1HC-141B S/H 102 WITH S/N 108.
Page 25 c[h 32
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PSE&O SALEM stHERATING STATION i
SAFETT CELATED NORK ORDE2 LOG 3/07/83 SORT BT DEPARTMENT, IMIT, WORK ORDER l'
NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
..8e
=
n=======================
4 930320...P. _ _1___. VALVE.1CC71._..
FAILURE DESCRIPTION t VALVE CAPR40T BE CONTROLLED FROM CONTROL ROOM.
i i
CORRECTIVE ACTION t REPLACED PILOT ON POSITIONER AND REPLACED MAMJAL/ AUTO STATION.
e i
e 4.._ _ _____._ _ NO NO. DEPT _ LMIT_.IQUIPMENT IDENTIFICATION._..
]
=========================
930330 P 1
13 ACCtMULATOR i.. _. _ _.
FAILURE DESCRIPTION
_.___.__...._ __... _ _ _ CORRECTIVE. ACTION. t_ REPLACED.Ct APG C3 IN ILC-934C/G POWER SUPPLT.
ND le DEPT LMIT EQUIPMENT IDENTIFICATION
.__=============..========================
930332 P 1
VALVE.1PS1
_ _.... _.. _. _.. _... _ _ _. _ _ _ _ _ _.._ FAILURE DESCRIPTION
- VALVE WILL NOT RESPote TD. CONTROLS.
CORRECTIVE ACTION
- REPLACED E/P CONVERTER APG OPERATOR DIAPMRAM.
NO NO DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
930479 P 1
P250 COMPUTER FAILURE DESCRIPTION
COPRECTIVE ACTION
- RESET 125VDC POWER SUPPLT. TEST SAT.
..e WO NO DEPT (MIT EQUIPMENT IDENTIFICATION
=========================
930488 P 1
VALVE.1VC2 FAILURE DESCRIPTION 2 SOLENDID VALVE LEAKING.
CORRECTIVE ACTION I REPLACED SOLENOID VALVE SV-802.
Page 26 of 32
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.p 3. ---.
SAFETT EELATED WORK ORDE2 LOG 3/07/83 SORT BY DEPARTMENT. tMIT, NORK ORDER
- NO HD DEPT ~~LMIT' Et5JIPMENT' IDENTIFICATION
~
~ ' ' '.' s e'
~ ~ ~ ~ ~ ~ ~ ~ ' ~ ~ '
2
- =======
================
930494 P.___ 1_ VALVE.12AF21 FAILURE DESCRIPTION
- NO CLOSED INDICATION ON CONTROL ROOM BEZEL 1
j
. CORRECTIVE ACTION t ADJUSTED LIMIT SWITCHES.
, _ _ _ _ _ __... _ NO HO._ DEPT tMIT_ EtlUIPMENT IDENTIFICATI0H.
=========================
901124 P 2
RMS.2R5
. FAILURE DESCRIPTIDH t CHAtNEL FAILED.
.. CORRECTIVE ACTION
- REPLACED 96 AFC C7 IN DETECTOR AMPLIFIER DOARD. REBUILT CotNECTOR CH DETECTtR CABLE _._
TEST SAT.
ND HD DEPT EMIT EtlUIPMENT IDENTIFICATION
.=====_.====.====
====r=======
910143 P 2
VALVE.23M3171
.. _ _ _ FAILURE DESCRIPTION.t RESTROKE VALVE DUE TO EXCESSIVE LEAKTHRU. _ _ _ _
CORRECTIVE ACTION t REPLACED FAULTT DIAPHRAM DMICH MAS CAUSING VALVE NOT TO CLOSE COMPLETELT.
ND HD DEPT LMIT EQUIPMENT IDENTIFICATION
=========================
917806 P 2
23 AUX FEED PUMP FAILURE DESCRIsrIgon : PLMP STARTS FOR MO APPARENT CAUSE.
CORRECTIVE ACTION
- FDLDO RC5 APO RC7 IN BACK OF SSP PANEL BLO6M IN HALF. REPLACED WITH SPARES.
.e.
WO HD DEPT LMIT EQUIPMENT IDENTIFICATION
r==
====================
._ 917836 P 2
21 $/G LEVEL CH 4 FAILURE DESCRIPTION t CHAFNEL 4 READING 4X HIGHER THAN CHA>HELS 2 Atc 3.
CORRECTIVE ACTICH t REPLACED FAILED TRANSMITTER.
Page 27 of 32
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jE PSE88 SALEM Gle.cCATING STATION SAFETY EELATED NORK ORDE2 LOG 3/07/83
- i SCRT BT DEPARTMENT, LMIT NORK ORDER S
ND NO DEPT UNIT EQUIPMENT IDENTIFICATION 8'
i
=
===s
============
g;
_ _..... _ _. 9179tt P.
_._ 2 VALVE s tHT32 _.... _ _.._._. __... _ _
9 FAILtmE DESCRIPTION
- SOLENDID VALVE ENERGIZED AW OPERATING BUT 2NT32 DOES NOT MOVE.
e
's,
CORRECTIVE ACTION t VERIFIED OPERATOR DIAPHRAM MDT BlonM.
MAINT REPAIRED VALVE. STROKED ADM VERIFIED LIMITS.
I',
j.__ _. _. _... ND NO.. DEPT..tMIT _ EQUIPMENT IDENTIFICATION.___....
I,'S
=========================
919973 P 2
WMS 2R36 FAILURE DESCRIPTION
- BATTERIES FOUND DEFECTIVE DURING FUNCTIONAL PROCEDLRE.
+
t
.._. CORRECTIVE. ACTION t. REPLACED FOLR BURGESS AA BATTERIES IN PONER SUPPLY.
h' y
e ND HD DEPT LMIT EQUIPMENT IDENTIFICATION
[
.... __=====,_====
.===s.========================
F 919991 P 2
Rtf5 2941B l-;
..... FAILURE DESCRIPTION t. REMOTE. DISPLAY.IS ALL F'S..._.__
_j.t
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CORRECTIVE ACTION t CHANSED ACIA'S IN REMOTE CONTROLLER.
!31 l.,.
,.r.
ND NO DEPT UNIT EQUIPMENT IDENTIFICATION
?
=
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..921454...... _
!,r P
2 RMS.2R41C
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FAILURE DESCRIPTION t CHAPG4EL FAILED.
..-.----.T, CORRECTIVE ACTION
- CHAT #4EL NORKING IN FIELD. FOUDB DIODE IN REMOTE CONTROLLER SHORTED OUT. REPLACED F
RENOTEt2RPIIPOWER SUPPLYe REPLACED DIODE. REPLACED RANS. FUNCTIONALLY SAT.
E' '
ND NO DEPT _. _...
._._-.__._...__...a*
tMIT EQUIPMENT IDENTIFICATION
=========================
.c 922005 P 2
RMS.294IC FAILURE DESCRIPTION
- CHAT #4EL CONTINUALLY SPIKES INTO WARNING.
CORRECTIVE ACTION
- DISCRIMINATOR VOLTAGE DRIFTING. REPLACED DISCRIMINATOR POT S VERIFIED OPERATION.
V*w Page 28 of 32
_.p SAFETT RELATED NORK ORDE3 LOG 3/07/83 SENPT BT DEPART? ENTE LMIT NORK ORDER ND HD DEPT LMIT EQUIPMENT IDENTIFICATION
~
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~ ~ ^ ' ~ ~ ~ ~ ~ ~
~
=========================
^
_922125. P.__ _,2.., VALVE tVC1.._
FAILURE DESCRIPTION
- VALVE NILL NOT COME OFF CLOSED LIMIT.
~~
- ~ ~ "' CORRECTIVE ACTION l' REPLACED 'OPEN COIL IN SOLEHOID' VALVE ~~
SV-1923. TEST SAT.
'~ '~~"~~
~
~
~
l__ _.__.
__.ND MD. DEPT (MIT _ EGUIPM' INT IDENTIFICATION
=========================
4 927660 P 2
24 S/G STEAM PRESSLRE CN 2 FAILURE DESCRIPTION t CHAMEL DUT OF CAL.
t CORRECTIVE ACTION 2. REPLACED. EPM-545A. SIGNAL ISOLATOR Ale _. ADJUSTED ZERO OF 2PI-5455.
ND 95 DEPT LMIT EQUIPMENT IDENTIFICATI0H
=========================
928626 P 2
. _... FAILURE DESCRIPTION t..IteICATION ERRATIC...
CORRECTIVE ACTION t VERIFIED TRANSMITTER CUTPUYS OSCILLATING 200-300MV. LON PRESSLRE SENSIDS LINE PLUGCED. BLEN DOWN LINES AND CALIBRATED..
ND NO DEPT LMIT EQUIPMENT IDENTIFICATI0H
=========================
928631
.23 CONT FAN COIL UNIT. _ _.... _
P 2
FAILURE DESCRIPTION 8 SERVICC WATER FLON IDWICATION IN CONTROL ROOM READING 1100 GPM NITH FAN COIL LMIT OUT OF SERVICE..
CORRECTIVE ACTION 2 REPLACED FAILED TRANSMITTER 2FA-3541Z.
- .4.
.NO NO DEPT...
.. _... _ _EOUIPMENT IDENTIFICATION..
LMIT
=========================
926650 P 2
SHUTDOWN BU8C RCD INDICATION ISAt FAILURE DESCRIPTION. CHAWEL FAILED TO HEUTRAL POSITION.
CORRECTIVE ACTION
- REPLACED ' SIGNAL C00GITION MODULE Ate CALIBRATED SAT.
Page 29 of 32 1
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PSE&G SALEM 6.ERATIr3 STATION SAFETT RELATE 3 WORK ORDER LOG 3/97/83 SORT BT DEPARTVENT, WIT, WORK ORDER MD ND DEPT WIT EQUIPMENT IDENTIFICATION
. ae
=
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.___. _._.._. 928903_.P P
RMS 2R5 FAILURE DESCRIPTION MONITOR IS JUPfM UP AM3 DONN DCALE.
CORRECTIVE ACTION 3 REPLACED 06 AM) 97 ON DETECTOR AMPLIFIER 90AlfD REBUI.T COPO4ECTtNt ON DETECTOR CABLE j ____..__ __. MD MD. DEPT _ WZT.. EQUIPMENT IDENTIFICATION.____... _.. _ _.
--===================================
.i 928912 P 2
RMS 2R418 FAILURE DESCRIPTION
- CHANNEL IN HD SCAN.
I.___
. _ CORRECTIVE. ACTIDH 8. FOLRW PONER SUPPLT FOR LOCAL CA8INET ___..EXTREMELLT NOT. DIRECTED AIR FLON.TO N 8 CCHPONENTS. RESET CHAPe4EL. TEST SAT.
MD NO DEPT tMIT EQUIPMENT IDENTIFICATION
===,======================
928943 P 2
23 CONT FAN COIL WIT
_ _ _..._. _ FAILURE DESCRIPTION.LLON. SERVICE NATER FLON.IH LON SPEED..
CORRECTIVE ACTION 1 CTCLED 23SN57 SEVERAL TIMES TG FLUSN SILT FRON SERVICE NATER PIPING.
MD HD DEPT WIT EQUIPMENT IDENTIFICATION
=========================
.. _ _ _ ~. -.
930490 P 2
RMS 2RIIA FAILURE DESCRIPTION
- MONITOR FAILED.
CORRECTIVE ACTTON
- RZSET LOGIC. RESEATED MAJOR CIRCUIT BOARDS TESTED SAT.
Page 30 of 32
SALEM UNIT 1 OPERATIONS
SUMMARY
REPORT FEBRUARY 1983 Unit No. 1 was in cold shutdown (Mode 5) at the and of February.
Investigations continued into the two occur-rences where both reactor trip breakers failed to open after receiving an automatic trip signal from the Solid State Protection System.
i Earlier in the month, following an inadvertent Safety In-jection on January 30th the Boron Injection Tank inlet valve ISJ4 was discovered leaking through.' It was replaced with 22SJ40 valve from Unit 2 on February 6th.
No. 12 Reactor Coolant Pump (RCP) motor was damaged by an equipment operator's error on January 29th.
It was replaced by No. 24 RCP motor from Unit 2 on February 7th.
On February 9th plant heatup to Mode 3 was attained.
Cali-bration of the Control Rod Position Indication System spanned February lith thru 13th.
The reactor was taken critical on February 14th.
Zero power physics tests for the Cycle 5 reload were completed the next day.
Repairs to a hydrogen leak in the main generator cooling system delayed turbine generator roll until February 20th.
Two reactor trips occurred on February 20th due to steam generator level control problems.
The unit was briefly synchronized early February 22nd, but again the reactor tripped on low steam generator level.
The unit was again synchronized late February 22nd.
During the routine swap-over to the station auxiliary power trans-former, the IF bus 4kv breaker failed to close, resulting in a loss of significant plant equipment including No. 13 Reactor Coolant Pump and No. 12 Steam Generator Feed Pump.
The l
subsequent drop in steam generator water levels prompted the l
operators to trip the reactor manually.
On February 24th the unit was synchronized for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at 20% load.
The unit was removed from service for a planned turbine over-speed trip test.
~
Following a successful overspeed test and a weight addition to No. 1 jack shaft on February 25th, the unit was again synchronized.
A low-low steam generator level initiated a reactor trip signal.
Both reactor breakers failed to open.
Operators tripped the reactor using the manual console trip switches.
In accordance with the Station Emergency Plan, a Site Alert was declared.
Page 31 of 32
REFUELING INFORMATION Docket No.
50-272 Unit Name Salem #1 Date Mar. 10, 1983 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month March 1983 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date of next refueling:
December 31, 1983 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 3/01/83 B.
Has the reload fuel design been reveiwed 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 recuired 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 32 of 32
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