ML20133E166
| ML20133E166 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1985 |
| From: | Ronafalvy J, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8507220413 | |
| Download: ML20133E166 (6) | |
Text
r-AVERAG2 DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date July 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month June 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 1091 17 1066 2
1080 18 1092 3
1088 19 1086 4
1096 20 1092 5
1094 21 1091 6
1081 22 1079 7
1085 23 1087 8
1079 24 1093 9
1075 25 1089 10 1090 26 1087 11 1080 27 1089 12 1094 28 1077 13 1101 29 1071 14 1095 30 1070 15 1097 31 16 1103 P. 8.1-7 R1 l
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OPERATING DATA REPORT Docket No.50-272 l
1 Date July 10, 1985 Telephone 935-6000 Completed by J.
P.
Ronafalvy Extension 4455 l
Operating Status 1.
Unit Name Salem No. 1 Notes l
2.
Reporting Period June 1985 3.
Licensed Thermal Power (MWt) 3338 4.
Nameplate Rating (Gross MWe)
TT75 5.
Design Electrical Rating (Net MWe) 1090 6.
Maximum Dependable Capacity (Gross MWe)1124 7.
Maximum Dependable Capacity (Net MWe) llCBf 8.
If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A 9.
Power Level to Which Restricted, if any (Net MWe)
N/A
- 10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 4343 70152
- 12. No. of Hrs. Reactor was Critical 720 4325.6 40149.1
- 13. Reactor Reserve Shutdown Hrs.
0 0
3088.4
- 14. Hours Generator On-Line 720 4322.7 38481.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2405532 14366391 117134388
- 17. Gross Elec. Energy Generated (MWH) 814080 4907320 38823370
- 18. Net Elec. Energy Generated (MWH) 782311 4717899 36815881
- 19. Unit Service Factor 100 99.5 54.9_
- 20. Unit Availability Factor 100 99.5 54.9
- 21. Unit Capacity Factor (using MDC Net) 100.7 100.7 48.6
- 22. Unit Capacity Factor (using DER Net) 99.7 99.7 48.1
- 23. Unit Forced Outage Rate 0
.5 30.6
- 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:
N/A
- 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 of
,1 -
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UNIT. SHUTDOWN AND POWER REDUCTIONS Dockot No.50-272 i REPORT MONTH June 1985 Unit Numa Sn19e Ko.1
- Dnte, July 30,1985 Telephone-609-9J3-6000 Completea by J.P. Ronafalvy Extension 4455
+
.c Mechod of Cause and Corrective Duration-Shutting.
License No.
.Date Type Hours Reason Down Event
' System.
Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence _
-
- There were no outages forj tiia month of June resulting in a load reduction of greater than 20%.
L e 3 Method 4' Exhibit G 5 Exhibit.l_ ~
1
.2 Reason F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as-S: Scheduled B-Maintenance or Test-2-Manual Scram.
for Prepara-Source 3-Automatic Scram.Jtion of Data
. C-Re, fueling-4-Continuation of Entry Sheets D-Regulatory Restriction E-Operator Training & Licensing Exam Previous. Outage for Licensee
'F-Administrative.
5-Load Reduction Event Report
~
G-Operational Error-explain 9-Other (LER) File (NUREG 0161)
H-Other-explain I
l
l MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH June 1985 UNIT NAME:
Salem 1 DATE:
July 10, 1985 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455 1
- DCR NO.
PRINCIPLE SYSTEM SUBJECT 1FC-0643 Annunciator System Revise all call broadcast acknowledge answer back system to be compatible with,GE/ TAC cabinet.
1EC-1324 Circulating Water Install permanent discharge water sample system for continuous sampling.
lEC-1447 Fresh Water Connect one end of the former concrete plant 4" water supply line into the station potable water-system and connect the other end at #1 Well House to lines feeding 901, 902 and other buildings.
lEC-1483 Meteorological Addition of a primary and Tower Control House back-up transmitter, antenna and controller in the Meterological Tower Control House.
1EC-1531 Waste Gas Install redundant waste gas oxygen analysis capability.
lEC-1731 Drains / Sump Pumps Replace No. 13 Turbine Area Sump Pump with' a submersible type slurry pump of different design'and materials.
I 1EC-1852 Moisture Separator Modify.the MSR shell side Reheater Steam and internals.
Design change Drains includes the separation, distribution and drain systems.
lEC-1892 Circulating Water Replace. circulating water pump vacuum breakers valves 11CW15, 12CW15, 13CW15, 11CW115, 12CW115, 13CW115.
l
- DC R NO.
PRINCIPLE SYSTEM SUBJECT 1EC-1965 Structural-#1 North Replace shield blocks in Penetration shielding wall 15' west of GG line.
lEC-1972
' 500KV Lines Rearrangement of 500KV lines in Salem switchyard to provide relay modification necessary to reroute Salem-New Freedom line to Salem-Deans line.
1SC-1237 Generator Exciter Modify exciter enclosure roof to provide direct access to Monitor No. 11 bearing vibration.
- Service Building El.
Removal of 7' section of 127'-Structural non-load bearing wall between Operations _ Staff Office and room previously used as Station Bunk Room.
Removal and blocking up existing door to Operations Staff Office.
1SC-1428 Existing Walls Install hangers for herculite rolls and poly bags at locations determined by the Solid Radwaste Supervisor.
ISC-1586 Switchyard Replace transformer that Miscellaneous Power failed with new style.
Original transformer had.PCB's
(# changeout will require installation of a temporary transformer).
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MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH JUNE 1985 UNIT NAME:
Salem 1
~~
DATE:
July 10, 1985 COMPLETED BY:
J.
Ronatalvy TELEPHONE:
609/339-4455
- DC R NO.
SAFETY EVALUATION 10 CFR 50.59 lEC-0643 This DCR is' not Safety Related and does not affect any safety related equipment.
No unreviewed safety or
-environmental questions are involved.
lEC-1324 The installation of a concrete foundation pad and a meter shed will neither affect any previously performed safety analyses nor affect the safe operation of the plant.
No unreviewed safety or environmental questions are involved.
1EC-1447 The installation of piping to bypass production well No. 1 does not affect any previously performed safety analyses nor affect the safe operation of the plant.
No unreviewed safety or environmental questions are involved.
1EC-1483 No safety function or safety margin will be affected by this DCR.
No unreviewed safety or environmental questions are involved.
1EC-15 31 No function of any system or component required to safely shutdown the Unit is affected.
Also, the ability to keep the Unit in a shutdown condition is not affected.
No unreviewed safety or environmental questions are involved.
1EC-17 31 This DCR replaces the #13 Turbine Generator Area Sump Pump from a 5 horse power pump to a 10 horse power pump.
New cable will be routed for the change.
The associated motor control center is revised to accept the new motor.
The system function will not change.
No unreveiwed safety or environmental questions are involved.
1EC-1852 This DCR provides for the modification of the internals of the MSR's to improve their performance and reliability.
No unreviewed safety or environmental questions are
- involved, lEC-1892 The replacement of the vacuum breaker valves (CW115S) does not affect any previously performed safety analyses nor does it create any new hazards.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request 1
I
1 d
4
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59 lEC-1965' This DCR involves minor' modifications for repair of the 4
masonry block wall radiation shield in the North Penetration Area at elevation 100' in line with the 4
I
^ Containment Personnel Lock.
This wall was-notched to allow passage of a replacement. coil for one of the Containment Fan Coil Units.
The design modification was analyzed by the Civil Design Div. to insure that the wall as revised will maintain integrity in the event of a i
seismic occurrence.
No unreviewed safety or environmental questions are involved.
4 l
1EC-1972 Thia DCR replaces 500KV relaying.
No safety related i
l!
componente are affected.
The same number of offsite power sources as are currently present will'he available after the change.
Seismic considerations for the new relay racks and the new. relays are. considered. acceptable since the mounting configurations, rack structural members, and f
)
all, mounting hardware are identical to the equipment which is being removed.and has been evaluated.
No work is being t
done'which affects interfaces,-either directly or through j
isolation devices, with any safety.related function or I
component.
Therefore, no failure mode exists which could
.I affect the safe shutdown of the Reactor Plant.
The Tech.
Specs are not affected by this DCR.
Sections 8.1 and 8.2 i
of the FSAR are affected by this DCR.
The FSAR-currently i
states that two lines from Salem switchyard go to the New i
Freedom switchyard.
The sections will be changed to
?
indicate that one line-runs between Salem and New Freedom switchyards and one line runs between Salem and Deans i
No unreviewed safety or environmental questions.are involved.
t 1SC-1237
- This modification will not alter any plant discharge or process and will not affect the existing plant impact.
1 This change has no effect on any. safety related system.
No unreviewed ' safety or environmental questions are
-involved.
1SC-1317 The work to this DCR will all be done.in the Service Building (a non-safety related structure).
No unreviewed safety or environmental questions are-involved.
- DCR - Design Change Request i
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59
. ISC-1428 Work to this DCR does not impact the safe shutdown or isolation of the reactor, nor is the margin of safety decreased. -No unreviewed safety or_ environmental
-questions are involved.
1SC-1586 This DCR replaces a miscellaneous power transformer in the 500KV switchyard.
This is a non-vital application and no safety related systems are affected.
There is no change in the design basis for the FSAR or the Tech. Specs.
Testing will be used to confirm that.the transformer as non-PCB. _No unreviewed safety or environmental questions are involved.
- DCR '- Design Change Request l
l 1
I E.
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t PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8506260205 SIC 1
IC D/ G FAILURE DESCRIPTION:
WHEN INCREASING LOAD, ACTUAL LOAD SPIKES _ DOWNWARD.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
TROUBLE SHOT IC D/G, FOUND E.G.A. GOV. CONT. BOX WAS NOT OPER. PROP.
REPLACED BOX.
SURVEILLANCE TEST - SAT.
8506200458 SMD 1
1CV75
. FAILURE DESCRIPTION:
ICV 75 STARTING TO LEAK AGAIN.
PLEASE RE-INJECT WITH FURMANITE.
1 CORRECTIVE ACTION:
FURMANITE MADE TEMP. REPAIRS BY INJECTING FURMANITE-i COMPOUND FURM. JOB N/L 9830 4
'8506200032 j
'SMD 1
PZR HEATER DEION FAILURE DESCRIPTION:
THE DEION IS TRIPPED.
PLEASE DETERMINE THE CAUSE FOR THE TRIPPED CONDITION AND CORRECT.
CORRECTIVE ACTION:
REPLACED lEP12X BREAKER WITH A NEW BREAKER i
8506200041 l
SMD 1
PZR HEATER DEION t
i FAILURE DESCRIPTION:
THE DEION IS TRIPPED.
PLEASE DETERMINE THE REASON FOR THE TRIPPED CONDITION AND CORRECT.
{
CORRECTIVE ACTION:
REPLACED lEP7X BREAKER WITH A NEW BREAKER
=
f SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8506181178 SMD-1 1EP PZR. HTR. BUS I
FAILURE DESCRIPTION:
1EP10X, 9X, 4X, AND 13X DEIONS KEEP TRIPPING.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REPLACED THE ABOVE MENTIONED BREAKERS WITH NEW BREAKERS i
~
-8506171814 SIC 1
SEM FLOW / FEED FLOW REC t
FAILURE DESCRIPTION:. THERE IS APPROX. A 10% DISCREPANCY BETWEEN THE FEED FLOW AND STEAM FLOW ON THE RECORDER.
THE BEZEL METERS I
ARE APPROX. THE SAME.
PLEASE CORRECT.
a CORRECTIVE ACTION:
CHECK CAL OF STEAM FLOW AND FEED FLOW AS PER ICD CARD.
i REPLACED SERVO-AMP V155H6 WITH V14DH6.
- j 1
8506140056 SMD 1
12 FHB EXH FAN j
FAILURE DESCRIPTION:
THE FAN TRIPPED OUT.
LOCALLY THE FAN IS SAT.
PLEASE CHECK THE BREAKER.
CORRECTIVE ACTION:
REPLACED WORN AND BROKEN FAN BELTS ON MOTOR 4
4 8506131456 SMD 1
12 SPENT FUEL PUMP FAILURE DESCRIPTION:
REPAIR LEAK ON DISCHARGE FLANGE OF 12 SPENT FUEL COOLING PUMP CORRECTIVE ACTION:
REPLACED FLEX GASKET IN DISCHARGE FLANGE WITH GRAPHIOL GASKET i
i i.
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4 u
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8506131464 SMD 1
11 SPENT FUEL PUMP 4
FAILURE DESCRIPTION:
REPAIR LEAK ON THE DISCHARGE FLANGE OF 11 SPENT FUEL COOLING PUMP.
CORRECTIVE ACTION:
REPLACED FLEX GASKET WITH GRAFOIL GASKET IN DISCHARGE FLANGE 8506131472 SMD 1
SPENT FUEL COOLING FAILURE DESCRIPTION:
REPAIR 2 FLANGE LEAKS IN FRONT OF SPENT FUEL HEAT-EXCHANGER IN THE VICINITY OF ISF900-& ISJ901 VALVES CORRECTIVE ACTION:
REPAIRED LEAK IN 2 FLANGES,BY REPLACING FLEX GASKETS WITH GRAFOIL GASKET 8506071178 i
SOD 1
CX)MPONENT COOLING I
FAILURE DESCRIPTION:
REVISE THE COMPONENT COOLING FLOW RATE TO THE RHR HEAT EXCHANGERS DURING COLD LEG RECIRCULATION FROM 2000 GPM TO 4000 GPM PER HEAT EXCHANGER.
CORRECTIVE ACTION:
OTSC MADE TO II 7.3.2 TABLE II 7.3.2 TABLE AND III TO REFLECT 4000 GPM SETPOINT CHANGE.
OTSC MADE TO SP (0) 4.0.5.P-CC 11,12,13 STEP 5.7 & 5.8.1 TO VERIFY CC15 FLOW CONTROL VALVE IS SET FOR 4000 GPM l
I t
l I
f I
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8506080037 SIC 1
l FAILURE DESCRIPTION:
THE CHANNEL IS FAILING INTERMITTENTLY.
PLEASE INVESTIGATE.
l CORRECTIVE ACTION:
CLEARED RAMS AND RESEATED MODULE AT LOCAL MONITOR.
^
VERIFIED SETPOINTS AND REPLACED 1PRI METER FACE GLASS.
8506060010 SMD 1
B/U PZR HTRS 27,28,55 FAILURE DESCRIPTION:
THIS BREAKER PERIODICALLY TRIPS.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
TESTED NEW BREAKER AND INSTALLED IN 1EP SX POS.
8506060028 SMD 1
B/U PZR HTRS 12,13,&l4 l
FAILURE DESCRIPTION:
THIS BREAKER TRIPS PERIODICALLY.
PLEASE INVESTIGATE l
AND REPAIR.
CORRECTIVE ACTION:
TESTED NEW BREAKER AND INSTALLED lEP 1X POS.
l l
8505110366 SIC 1
1R41B PLANT VENT IODINE FAILURE DESCRIPTION:
1R41B, PLANT VENT IODINE RADIATION MONITOR IS CONSTANTLY FAILING.
THE MONITOR IS READING Ell, AND THE METER IS SPIKING.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REMOVED LOCAL SCALER S/N 168 AND CLEANED J1 AND J2 PINS WITH D FLUX CLEANING SOLUENT.
REPLACED R2 FUSE XMIT LOOP 1 IN REMOTE 862C1 CONTROLLER.
REPLACED REMOTE POWER SUPPLY S/N 459 WITH S/N 474.
MODULES l
REINSTALLED.
______.m.
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8505141318 SMD 1
12 SW23, S.W. NUC. HDR CROSSTIE FAILURE DESCRIPTION:
12SW23, THE NUCLEAR HEADER CROSS-TIE VALVE WILL NOT CLOSE ALL THE WAY.
VALVE STROKE STOPS APPROX 2" FRCH LIMIT.
THE BREAKER DOES NOT TRIP OPEN HOWEVER.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
RUST ON FACE OF CONTACTS OF TORQUE SWITCH.
REMOVED RUST AND STROKED VALVE SAT.
8504161226 SMD 1
13 CHARGING PUMP FAILURE DESCRIPTION:
THERE IS INDICATION OF PIF' TON SEAL LEAKAGE.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REPACKED 5 CYLINDERS, REPLACED 3 PLUNGERS, REPLACED 5 STUFFING BOXES.
0099164230 SIC 1
1C DIESEL GEN FAILURE DESCRIPTION:
PLEASE REPLACE THIS RELAY DUE TO INOPERI3ILITY OF OLD RELAY.
CORRECTIVE ACTION:
FOUND INPUT SHORTENED ON 2 STG.
INSTALLED SPARE.
CHECKED CALIBRATION.
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 i =
JUNE 1985 i
SNLEM NO. 1 The Unit operated at full power for the entire period.
1 I.
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REFUELING INFORMATION DOCKET NO. :
50-272 COMPLETED BY:
J.
Ronafalvy UNIT NAME:
Salem 1 DATE:
July 10, 1985 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month June 1985 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
February 22, 1986 3.
Scheduled date for restart following refueling:
May 4,1986 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled? _ January 1986 5.
Scheduled date (s) for submitting proposed licensing action:
January 1986 if required 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 296 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170 9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4 4
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' Public Service Eiectric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 10, 1985 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 June 1985 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, J. F Zu o,
r.
GeMral anager - Salem Operations JR:sbh cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control
.U.S.. Nuclear Regulatory Commission Washington, DC 20555
-Enclosures Page of 8-1-7.R4
- I The Energy People W2189 UOM) 1181 m.
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