ML20207S438
| ML20207S438 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1987 |
| From: | Miller L, White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8703190455 | |
| Download: ML20207S438 (10) | |
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AVERAGE DAILY UNIT-POWER LEVEL Docket No.
50-272 Unit Name-
-Salem # 1-Date
-March 10,1987
~ Completed by Pell White Telephone 609-935-6000 Extension 4451 Month ~
February 1987
~
Day Average Daily, Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET).
1 1084 17 1123 2
1078 18 1138 3
1108 19 1112 4
'1116 20 1117 5
1113 21 1111 6
1121 22 1105 7
1123 23 1112 8
1097 24 1109 9
1110 25 1123 10 1114 26 1108 11' 1114-27 1117-12
-1169 28 1111 13 1062 29 14 1114 30 15 1102 31 16 1095 P.
8.1-7 R1 gasqua E88jha 96\\s R
si OPERATING DATA. REPORT Docket No.50-272 Date ' March 10,1987 Telephone 935-6000 4
Pell White Extension-4451 1 Completed by Operating' Status 1.
Unit-Name Salem No.tl Notes 2.
-Reporting Period February 1987 Licensed Thermal Power.(MWt) 3411 3.
4..
Nameplate, Rating (Gross MWe)
IT73
~5.
. Design Electrical. Rating (Net MWe)
'tiTT
- 6.. Maximum Dependable Capacity (Gross MWe)ITU 7.
Maximum' Dependable' Capacity (Net MWe) ITUT 8..
If Changes Occur in Capacity Ratings (items 3 through 7) since Last
. Report, Give Reason N/A 9.
PowerJLevel to Which Restricted, if any (Net-MWe)
NA'
- 10. Reasons for. Restrictions, if any This Month Year to Date
~ Cumulative
- 11. Hours in Reporting Period 672 1416 84745
.12. No. of Hrs. Reactor was Critical 672 1416 52698.6
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 672 1416 50844.6
- 15. Unit Reserve Shutdown Hours 0
0 0
, 16. Gross: Thermal. Energy Generated (MWH) 2288311-4545470-157201516
- 17. Gross Elec. Energy Generated (MWH) 773370 1532910 52230910
- 18. Net Elec. Energy Generated (MWH) 746008-1476000 49660768
- 19. Unit' Service Factor 100 100 60.0
- 20. Unit Availability Factor 100 100 60.0
- 21. Unit Capacity Factor i
i-(using MDC Net) 100.4 94.2 53.0
- 22. Unit Capacity Factor-99.6 93.5 52.6 (using DER Net) 4
- 23. Unit Forced Outage Rate 0-0 26.0 l
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each) i NA i
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A i
- 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 i.
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UNIT SHUTDOWN AND POWER REDUCTIONS ~
. Unit N;meLdarem no.1 Docket'Na,50-272 REPORT MONTH FEBRUARY 1987 Date March-10,1987.
Completed by Pell White Telephone 609-935-6000 Extension 4451 g
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 LOAD Condenser Tube 0074 02-02-87 F-4.0 B
REDUCTION' HC HTEXCH
& Water Box Claning 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 Reductier.
Event Report G-Operational Error-explain
'9-Other
-(LER) File H-Other-explain
'(NUREG.0161) l l
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.bmJOR PLANT MODIFICATIONS DOCKET:NO.:
50-272 REPORT MONTH. FEBRUARY 1987 UNIT.NAME:
-Salem 1
.DATE:
March 12, 1987 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR NO..
PRINCIPAL. SYSTEM.
SUBJECT 1EC-1475l Crane &' Hoist Implement a color' coding L(marking)1and capacity marking _
of overhead lifting / handling-systems / components.
Hoists &. Cranes.
Derate-Fuel Handling Crane capacity to12,200 pounds (1.1
' tons).by changing'
" nameplate / capacity plate" marking and; adding appropriate' notes to design, maintenance, and other documents.
lEC-1576 Hoists &' Cranes Drate " Overhead Load Handling L
System" capacity to 2,200 pounds (1.1 tons) or less by changing the "name/ capacity plate" marking and adding appropriate notes to design,-
maintenance, operating, and other documents.-
t i
i
- DCR - Design Change Request b
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MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH FEBRUARY 1987 UNIT NAME:
Salem 1 DATE:
March 12, 1987-COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1475 This DCR provides for the implementation of a color coding and capacity marking on all the cranes, hooks, slings, monorails, overhead hoists, mobile and hydraulic cranes and special lifting devices for Unit
- 1.
This painting job will not create a new safety hazard to the plant, neither will affect the safe shutdown of the reactor.
The implementation of this capacity marking is done to comply with the commitment made to the NRC and also with Section 5.1.l(4) of NUREG-0612.
This DCR will not change the plant. effluent releases and will not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
1EC-1575 This DCR provides for the-implementation of a color coding to derate the fuel handling crane from its present 10,000 pounds to 2,200 pounds lifting capacity, for Unit #1.
This painting job will not create a new fire safety hazard to the plant, nor affect the safe shutdown of the reactor.
Implementation of this lower capacity marking is done to comply with a commitment made to the NRC and withSection 5.1. l(4) of NUREG-0612.
This DCR will not change the plant effluent releases and will not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
1EC-1576 This DCR provides for the implementation of a color coding to derate the manipulator crane from its present 3,000 pounds to 2,200 pounds lifting capacity, for Unit
- 1.
This painting job will not create a new fire safety hazard to the plant, nor affect the safe shutdown of the reactor.
Implementation of this lower capacity marking is done to comply with a commitment made to the NRC and with Section 5.1.1(4) of NUREG-0612.
This DCR will not change the plant effluent releases and will not alter the existing i
environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
- Design Change Request
A N
4.
-.h j PSE&G-SALEM GENEPATING' STATION
' SAFETY ~RELATED. WORK ORDER LOG
' SALEM UNIT 1
%O NO UNIT EQUIPMENT IDENTIFICATION 87021181436 1
15 CFCU SW FLOW FAILURE DESCRIPTION:
THERE IS NO SERVICE WATER FLOW INDICATED [ON THE' CONTROL ROOM BEZEL.
PLEASE~ INVESTIGATE AND' REPAIR.
CORRECTIVE ACTION:
FOUND LOW SIDE SENSING LINE PLUG. FIX.SAME.. VERIFY FLOW
'IN LOW.AND HIGH SPEED.
8702180847 1
11 CFCU DISCHARGE FLOW CONTROL VALVE FAILURE DESCRIPTION:
WHEN 11 CFC IS IN.HIGH SPEED, NO SW FLOW-IS OBSERVED.
WHEN IN LOW SPEED, SW FLOW IS SAT.
SUSPECT.11SW65 VALVE-IS CLOSING FULLY WHEN FCU IN HIGH SPEED.
IEC'PLEASE.
INVESTIGATE. WORK REQUEST #001707-CORRECTIVE ACTION:
ADJUSTED BACK-PRESSURE CONTROLLER AND HIGH AND LOW FLOW SET POINTS TO OBTAIN PROPER READINGS IN CONTROL: ROOM..
8702170205 1
VCT RELIEF VALVE FAILURE DESCRIPTION:
VALVE DOES NOT OPEN WHEN CV243 IS': OPENED EVEN THOUGH.
~
PRESSURE IS GREATER THAN 20#.
PLEASE. INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
SET-CONTROLLER SET POINT FOR 20 PSI. (CONTROLLER INTEGRATED PROPERLY.
VALVE ICU244 OPERATED SAT.
CONDUCT TEST AS PER M3M OPERATING SAT.
m
. ~.'
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 0099187949 j.
1 PLANT VENT STACK 4
FLOW RECORDER FAILURE DESCRIPTION:
RECORDER OUTPUT VALVE IS VARYING BETWEEN 0.& 97,000 SCFM,-PLEASE REPAIR.
CORRECTIVE ACTION:
FOUND SAMPLE LINE FROZEN, THAWED LINE, FLOW RETURNED TO NORMAL, INSULATED AND ADJUSTED HEAT TRACE.
0099187990 1
REACTOR TRIP BREAKER A CLOSED INDICATION 4
FAILURE DESCRIPTION:
THERE IS NO CLOSED INDICATION ON_THE. CONSOLE.
PLEASE_
i l
INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
FOUND 28 V.P.C. BREAKER IN OFF POSITION.
TURNED j
BREAKER ON.AND RECEIVED INDICATION.
0099188015 1
PROTECTION CHANNEL II FAILURE DESCRIPTION:
WHILE PERFORMING A FUNCTIONAL'ON THE POWER RANGE CHANNEL, THE BISTABLE WAS TRIPPED AND ALL HIGH STEAM FLOW ALARMS CAME UP-AND LOCKED.IN.. PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
FOUND DEFECTIVE COMPONATOR ITC-42140-REPLACED WITH SN # GO-281.
PERFORMED SECTIONS OF PROCEDURE IIC-2.6.005 AND IIC-2.2.005 TO VERIFY, CALIBRATION OF LOOP.
i-i
A, SALEM UNIT 1 WO NO.
UNIT-EQUIPMENT IDENTIFICATION 8701040294 1
15 SW PUMP.
FAILURE DESCRIPTION:
15 SW PUMP. FAILED 4.0.5-P DUE TO HIGH VIBRATION.
POINT 1 VERTICAL.WAS 12 MILS,. POINT 1: HORIZONTAL WAS 6 MILS.. PLEASE INVESTIGATE AND REPAIR.-
CORRECTlVE ACTION:-
REBUILT PUMP AND INSTALLED NEW EXPANSION JOINT.
8702090872 1
15 SW PUMP MOTOR FAILURE DESCRIPTION:
MOTOR VIBRATING 8.5 MILLS AT UPPER. BEARING AND
'7.5 MILS ON MOTOR FRAME.
MOTOR WAS UNCOUPLED FROM PUMP WHEN READINGS WERE TAKEN.
CORRECTIVE ACTION:
' REPLACED #15 SW MOTOR.
RAN MOTOR'FOR 20 MINUTES BEFORE COUPLING, ALL SAT.
8702100011 1
16 SERVICE WATER PP STRAINER FAILURE DESCRIPTION:
THE STRAINER SHEAR KEYS HAVE SHEARED RESULTING IN AN INOPERABLE STRAINER.
THE T.S.A.S.
IS A RESULTS-OF THIS PROBLEM IN CONJUNCTION WITH 15 BEING C/T.
PLEASE-REPAIR.
CORRECTIVE ACTION:-
REPLACED SHEAR KEY AND LOWER SEAL PLATES R.P.T.'
REPACKED STRAINER.
1 i
SALEM GENERATING STATION MONTHLY. OPERATING
SUMMARY
- UNIT NO. 1 FEBRUARY 1987
.The Unit began the period operating at one hundred percent (100%)
power, 1,156 MW gross until Monday, February 2, when power was reduced to 85% for a few hours to clean condensers.- The unit ran at 100%,
1,155 KW gross for the remainder of the month except for a brief power reduction on Sunday, February 15, to perform a turbine valve surveillance test.-
Number 11A Circulating Water Pump was out of service to install the temporary power feed from Hope Creek and was completed Friday, February 113, which completed the temporary power feed project.
On Thursday, February 19, Salem completed 1,000,000 man hours of work without a lost time accident.
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K.
Miller UNIT NAME:
Salem 1 DATE:
March 12, 1987 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month February 1987 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
September 12, 1987 3.
Scheduled date for restart following refueling: November 26, 1987 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE X
B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
August 1987 5.
Scheduled date (s) for submitting proposed 1pcensing action:
August 1987 if required 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 380 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170 9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4 4
L.
b 2f p.
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 1987 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of February 1987 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincer
- yours, J. M upj
, Jr.
Gene al s nager - Salem Operations JR:sl cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King'of Prussia, PA 19406 Director, Office of Management U.S. Nuclear Regulatory ~ Commission Document Control Desk Washington, DC 20555 Enclosures 8-1-7.R4
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The Energy Peopka
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