ML20197H713
| ML20197H713 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1984 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8406190154 | |
| Download: ML20197H713 (14) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 i
Date June 10,1984 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month ~
May 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) i
-1 0
17 0
2 0
18 0 0 19 0
.4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8
-0 24 0
9 0
25 0
i 10 0
26 0
11 0
27 0
12 0
28 0
~13 0
29 0
l 14 0
-30 0
l
.15 0
31 0
16
-0 P.
8,1 -7 R1 i
Page 2 of 14 g
S406190154 040531 T.
PDR ADOCK 05000272 h27 R
m y
' OPERATING DATA REPORT Docket No.50-272 Date June 10, 1984 Telephone 935-6000 Completed by L.!K. Miller Extension 4455 bperating Status 1.
Unit Name-Salem No. 1 Notes 12. -
Reporting. Period May 1984 3.
Licensed Thermal Power (MWt) 3338 4.
' Nameplate Rating (Gross ' MWe) ~
1135 5.'. Design Electrical Rating (Net MWe)
T555 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)
N/A
~10. Reasons for Restrictions, iI any N/A This Month Year to Date Cumulative 11, Hours in' Reporting Period 744 3647 60672
- 12. No. of Hrs. Reactor was Critical 0
1237.6 34388.8
~
13.-Reactor Reserve Shutdown Hrs.
0 54.5 3088.4
- 14. Hours Generator On-Line 0
1197.8 32975.7
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal' Energy Generated QGGI) 0 3800023 99619394
- 17. Gross Elec. Energy Generated
. QUGI)~
0 1281380 32896480
- 18. Net Elec.. Energy Generated (.MWH)
-(2324)
_1212703 31181015 l
19.' Unit Service Factor 0
32.8 54.4
- 20. Unit Availability Factor 0
-32.8 54.4 i
- 21. Unit. Capacity Factor (using MDC Net) 0 30.8 47.6
- 22. Unit Capacity Factor (using DER Net) 0 30.5 47.2 i
L
- 23. Unit Forced Outage Rate.
0 45.8 29.9 i
l
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each) i.
l' Re fueling 4-2-84 i
U 25>..If. shutdown at end of Report Period, Estimated Date of Startup:
}
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8-11-84 L
- 26. Units in Test Status (Prior to Commercial Operation) :
l Forecast Achieved i
i Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 i
8-1-7.R2 j
Page. of j
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Page 3 of 14 i
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UNIT SHUTDOWN ~AND' POWER REDUCTIONS-Dockst No.50-272 zREPORT MONTH May 1984 Unit-Name S'ilca No.1' Date' June 10, 1984 Telephone 609-935-6000 Completed by.
L.K. Miller Extension 4455
~
Method of Duration.
Shutting License Cause and Corrective
{
No.
Date Type Hours Reason Down
' Event System Component Action to l
1
'2 Reactor Report Code'4 Code 5 Prevent Recurrence Nuclear 84-174 04-02 S
744 C
'4 RC FUELXX Normal Refueling i
i e
4 i
t 3 Method 4 Exhibit G 5 Exhibit 1 1
2 Reason F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as i
S Scheduled B-Maintenance or Test 2-Manual Scram, for Prepara-Source l
C-Refueling 3-Automatic Scram.. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage forjLicensee F-Administrative 5-Load Reduction Event Report i
G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) i i
Page 4 of 14 I., - - -...
J
DOCKET NO:
50-272 MAJOR PLANT MODIFICATIONS UNIT NAME:
SALEM 1
,N 4
REPORT MONTH MAY 1984 DATE:
JUNE 10, 1984 COMPLETED SY:
L. K. MTTIER TELEPHONE:
(609) 339-4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT P
Install electricity.
LED-0196 Service Building "B" lEC-1092 Control Ibom Provide various engraved nameplates.
1ET-1395 Ch mical Volume & Control Perform vibration analysis on main steam check valves (MS46).
IEC-1812 Reactor Coolant Install an inline valve on the 3/8" tubirs on the disclurge of the valve 1BC3 and the head valve.
I lEC-1880 Incore Instrumentation Restore damaged thmuucouple colunn #A5.
.i 7
ISC-0313 Service Water (Pumps 12, 13 edify SW pump notors to allow filling and 16) of oil reservoirs. Extend spare thermo-couple connections f/ exciter bearing metal tmperature which are located in exciter terminal in Generator End Terminal Box.
ISC-0650 Steam Generator Feedwater Pump Journal Bearings - Ta%. new bearing Pump #11 retainers and nodify the per Franklin Institute Besearch Lab Report F-A5477.
ISC-0713 Fuel Handling Building Mount bracket to hold fuel handling slings on wall El. 130'.
ISC-0995 Annunciators m dify Auxiliary Annunciator inputs 013, 138, 531, 553 and 613 to indicate NORMAL (no alarm) when breakers are de-energized.
Field relay contacts can be rewired, at l
the equipnent associated with above inputs, to initiate an alarm only when the 'equignent is energized.
ISC-1007 Isolated Phase Bus Provide an alternate switch for the isolated phase bus tmperature alarm.
l LSC-1193 Contaiment Ventilation Control circuit for' containment fan coil units should provide for a trip o,f the high speed breaker should the ty breaker fail to stay in the closed position.
Also, red start light should not cme on without both breakers closed.
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- DESIGN CHANGE REOUEST 9-1-7.R1 Page 5 of 14
DOCKET NO:
50-272 Q
' MA'JOR PLANT _ MODIFICATIONS
' REPORT MONTH MAY 1984 UNIT NAME:
SALEM 1 DATE:
JUNE 10, 1984 COMPLETED BY:
L. K. MILLER TELEPHONE:
(609) 339-4455 v]
t\\,j
- DCR NO.
PRINCIPLE SYSTEM SUBJECT IST-1243 Circulating Water Bearing Change ptmps to some other type pump, Inbe Pumps such as subnersible trash pump as recamended by the Plant Engineering Division. A test will be performed on one pump only.
ISC-1318-Cafeteria Install double door by Cafeteria hallway.
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- DESIGN CHANGE REOCEST
'S-1-7.R1 Page 6 of 14
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5 j-HMAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272
^ _
REPORT MONTH MAY 1984 UNIT NAME:
Salem 1 DATE:
June 10, 1984 COMPLETED BY:
L.K. Miller TELEPHONE:
609/339-4455
- DCR NO.
SAFETY EVALUATION. 10 CFR 50.59
? LED-0196
'These: changes are not safety related and do not effect safety related systems.
No.unreviewed safety or environmental questions are involved.
1EC-1092 l Implementation of this Design Change only involves cosmetic type work.
No unreviewed safety or environmental questions are involved.
- 1ET-1395 Operational modes will be simulated during performance of this vibration analysis.
Therefore, everything will be within the design basis..No unreviewed safety or environmental questions are involved.
1EC-1812 Implementation of this Design Change does not involve any unreviewed. safety or environmental questions.
-1EC-18 80.
This. Design Change is being implemented to repair the damaged thermocouple column, No. A5.
No unreviewed safety or environmental questions are involved.
ISC-0313 The change in the upper bearing oil fill piping will not affect the operation of the motor.
Therefore, this change i
will not involve any change to the FSAR'or the Technical Specifications.- No unreviewed safety or environmental
. questions are involved.
ISC-0650 This Design. Change'does not affect any presently performed safety analysic nor does it create any new' safety hazards.
TheLTechnical Specifications are not affected.
No unreviewed safety or environmental questions are involved.
ISC-0713 The: installation of a bracket to supp rt the fuel handling
~
- slings does affect'any previously perrormed safety analysis.
No unreviewed safety or environmental questions'are-E involved.
't 1SC-0995 All potential realistic failure modes have been considered but are not applicable.
No unreviewed safety or environmental questions are involved.
4 4
-*DCR'- Design Change Request Page 7 of 14 s
N
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59 ISC-1007 Implementation of the Design Change does not involve any unreviewed safety or environmental questions.
-1SC-1193
.All potential realistic failure modes have been considered but are not applicable.
No regulatory requirements are involved.
No unreviewed safety or environmental questions are involved.
1ST-1243 Implementation of this Design Change does not affect safety related equipment or alter any plant process or discharge.
No unreviewed safety or environmental questions are involved.
ISC-1318 Iaplementation of this Design Change does not alter any plant process or discharge, nor does it affect any safety related equipment.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request i
f Page 8 of 14
' P C E & G - SAIDI GENERATING STM'IW -'
~
' SMTIY R12ATED WORK OEDER LOG '
SAIDI INIT 1 :
' WO NO DEPT UNIT EQUIPMENT IDENTIFICATIN 923751 CD
'l SERVICO WATER PIPING 'IO CHTT.TRRS FAIIURE DESCRIPTIW: PIPING HAS PINHOLE LEAM IN 'IHE VICINITY CF VALVE 11SW96 (053084).
CCRRECTIVE ACTICN:
REPLACED FIANGE, REDUCER, PIPE, ifJTS Am STRAPS (060183) 1.
935330 OD l'
VALVE 1CV258 FAILURE DESCRIPTICN: 'IHERE IS A CRACK IN 'IHE WEID BEINEIN 'IHE VALVE AND THE PRESSURE GAUGE CN j.
NO.12 CHARGING PWP SUCTICH (021884)
CORRECTIVE ACTIW:
INSTAT.Tm NEW BCteET CN VALVE ICV 258 IND WEIDED IN NEW 'IUBING LINE (030584) i 935704 CD 1
NO.15 SERVICE WATER PUMP MCIOR BREAKER FAIIURE DESCRIPTICE: 125VDC COffROL POWER DEIN HANDLE BROKIN OFF (101483)~
I CORRECTIVE ACTIW:
REPIJCED CNTROL DEICN (050884) 936511 CD 1
OVERHEAD ALARM D-35 FAILURE DETRIPTICN: WHILE FILLING 'INE REFUELING CAVITY FRCM THE RWST HI/IO LEVEL ALARMS WERE RECEIVED AT 11' AND 12.5' RESPBCTIVELY. THE DESIGN SEfPOINf IS 15.25' I
(032684) i CWRECTIVE ACTIW:
RECALIBRATED ' HIE IEVEL ALARMS (032684) l 941542 IC 1
MONI'IOR 1R15 i
FAIIERE DESCRIPTIW: DEFECTIVE DETECITE DISCOVERED DURING CHMMEL CALIBRATICN (020884) l CORRECPIVE ACTIW:
REPIACED AND CALIBRATED DETECICR (020884) i I
Page 9 of 14 1
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-PSE&G SALEM GENERMPING STATIM,
SAFE 1Y REIATED NOFK ORDER IOG
-941548
-IC' 1R " MNI'IOR 1R46B
'FAI wRE DESCRIPTIN : WANNEL FATim ION (022384) -
CORRECTIVE ACTIW:.
REPIACED RESIS'IGtS R1 MO R6 AIO CALIBRATED DETBC'IOR :(041284) 941928 OD 1
VALVE IWL108
-FAIwRE DESCRIPTIN : VALVE LEAKS 'IEROUm (121283)
CCRRECTIVE ACTIN:
REPIJCED VALVE DIAPHRAGM (042484) 4 945065 MD 1
VALVE 14MS7' l
FAIIURE DESCRIPTIW : DISASSENBLE AND INSPECT VALVE (020584)
Cuo<tA:nVE ACTIW:
WEEDED -IN NEN. VALVE AND REPLACED PIPING (042684) i 948009
-CD 1
1B1 125VDC BATTEIN CHARGER i
FAIw RE DESCRIPTION: CHARGER HAS BAD CUFPUP BRFJJTR, PLEASE INVESTIGATE (042984)
I CORRECTIVE ACTIW:
REPIJCED WI'IH NEW BREAKER AND RETURNED 'IO SERVICE (051184) 1 1
948016 CD 1
1R41 GANNEL APD FAIwRE DESCRIPTIN: HI/ID FIOW AIA% LCKED IN AND WILL NOT CLEAR (043084).
k CORRECTIVE ACIIW:
PLMP HAD APPARENT OIL LEAK, REPLACED WITH NEW PUMP (043084) r j
948679 IC 1
1R41C RMS CHANNEL 2
FAIIURE DESCRIPTIN: PLEASE. IhWESTIGATE CONTINUOUSLY CYCLING REIAYS EUR FAIw RE NARNING AIARMS.(041884)
CucoL:nVE ACTIN:
RECALIBRATED AIARMS (041984) i Page 10 of 14-
s PSE&G SALEM GENERATING STATICN SAFE 71Y REIATED WCRK ORDER IOG 948693 IC-1 ITNITOR 1R12A FAIIURE DESCRIPTICN: POWER CN INDICA'lDR IJGYP HAS BROKEN SOCKEP (042584)
Cuu<EL'nVE ACTION:
REPIACED SOCKEr IN CHANNEL DRAWER (042584) i 948728 IC 1
OCMPCNENT COOLING SURGE TANK IETEL INDICATION
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FAIIURE DESCRIPTICN: PLEASE CALIBRATE IETEL DEVICES (042584) i Cuc<rL'nVE ICfICN:
RECAllBRATED LEVEL DEVICES (042584) 948731 IC 1
NO.13 ' AUXILIARY FEEDWATER POMP SUCTICN PRESSURE INDICATIN FAIIURE DESCRIFIICN: - PRESStiRE TRANSMITTER FOLND Olff CF CALIBRATICH (042684)
CORRBCTIVE PCTICN:
RECALIBRATED TRANSHITIER (042684) 4 948729 IC 1
NO.12 BORIC ACID TANK TEMPERATURE CCNTROL J
FAILURE DESCRIPTICN: TEMPERATURE COTPROL FOUND OLTI OF SPECIFICATICN (042684)
I cuto<rffIVE ACTICN:
RECALIBRATED TEMPERATURE CCNTROLLER (042684) l 948873 CD 1
RADIATICN MCNI'lORING SYSTEM FAILURE DESCRIPPICE: RECEIVING SPURICXJS OVERHEAD AIAPMS (041984)
CUKKtCTIVE 7CfICN:
CLEANED MODULE PINS AND BACK PIANE SOCKEIS PERFORMED FUNCTICNAL TEST (041984) 948879 CD 1
RMS STRIP CHARP RECOEDER XA-9193 FAILURE DESCRIFfICN: PEN IS HUNG UP AND IS NOP PRINTING PROPERLY (041984) i i
Cuu<rL'nVE PCfION:
REPIACED BAIANCING MDPOR AND FORN PINICN BUSHING (042784) i Page 11 of 14
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' P S E & G - SALEM GENERMPING STATIN.
SAFm REIMD WORK WDER IOG i
949808 lE 1 l LNO.12 CHARGING PWP FAIIIDE DESCRIPPIW: INSPECT PWP SEAT FCR SIGS W LEA 1GCE -(022484)'
CORRECTIVE ACTICN:
INSTAT.Tm NEW SEAIS (050184) 991588 CD 1
VALVE 110C200 i
FAII11RE DESCRIPTIW: CANNor GET GOCD SHUITF CN VALVE. (121181)
CORRECTIVE ACTIW:
REPIACED VALVE BCNNEP WHICH HAD BEEN DAMAGED BY IDCKWIRE Am REPACKED VALVE' (052484)
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i OPERATIONS
SUMMARY
REPORT MAY 1984
'As the period began, Unit No. 1 remained shutdown as the fifth refueling outage continues.
Repair of the generator is in progress.
To date, all generator coils have been replaced.
Subsequently, a successful DC High Potential Test was performed.
The generator is presently scheduled for return to service August 11, 1984.
Work continues on the reactor thermocouple column.
Eleven of the thirteen thermocouples.have been removed.
Two of the thermocouples will not be replaced.
Reactor Split Pin replacement was-completed on schedule.
In all, sixty-one. guide tubes had been removed.
A total of four (4) defective pins were identified out of a total of 122 pins replaced.
Retubing was completed on No. 11 Component Cooling Water Heat Exchanger with titanium tubes.
No. 11 Service Water Header repairs have been completed.
No. 12 Service Water Header inspections are continuing with the header due to be returned to service on June 13, 1984.
No. 12 Component Cooling Heat Exchanger Service Water piping modifications continue with scheduled completion by June 17, 1984.
Steam Generator. moisture separator modifications are in progress.
The
. Steam Generator hydraulic snubber testing has been completed.
Four of the. snubbers were' removed and shipped to Wyle labs.
Four (4) replacement snubbers are being installed.
Sludge lancing has been completed on all Steam Generators.
Both primary and secondary side inspections continue to demonstrate excellent Steam Generator chemistry.
Flow Slot Photography and annulus search have been completed on all Steam Generators.
Results of the photography revealed five (5) weld rod stubs in #11 and two (2) weld stubs in #13.
The weld wire' stubs were removed on May 10, 1984.
Flow Slot Photography was redone on Nos. 11 and 13 Steam Generators with satisfactory-results.
Final annulus searches will be performed upon completion of all secondary work.
Additional "J" Tube Inspections have been scheduled on Nos. 11 and 13 Steam Generators.
Safisfactory results were'obtained on the initial inspections, however the scope of the inspections have increased.
Pressurizer hanger work is in progress.
Preparation work, including ALARA considerations, have been completed.
Type "C" leak rate testing is in progress.
To date, seventy-nine (79) of one hundred and seventeen (117) valves have been accepted. Work on No. 11 and No. 12 Station. Power Transformers (SPT) has been completed and they were returned to service May 10, 1984 and May 18, 1984 respectively.
IA Vital Bus outage is complete with IB
. Vital Bus outage in progress.
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REFUELING INFORMATION Docket No.
50-272 Unit Name Salem #1 Date
' June 10, 1984
. Completed by L.-~K. Miller Telephone 609-935-6000 Extension 4455 Month ~ May'1984
~
t 11.
-Fofueling information has changed from last' month:
1-YES NO X
2.
Scheduled date of next refueling:
February 24, 1984 3.
Scheduled date for restart following refueling:
September 1, 1984-t
.4..
.A.-
Will_ Technical. Specification changes or other license amendments be required?
YES NO' 3
NOT DETERMINED TO DATE 6/01/84
.Ilas'the reload fuel design-been-reveiwed by the Station Operating f
_' B.
Review Committee?
YES NO X
If no, when is it scheduled?
July 1984 4
f
'5~
Scheduled date(s) for submitting proposed licensing action:
~
July 1984, if required i
6.
.Important.. licensing ~ considerations associated with refueling:
. ht "
e 7.
' Number ot Fuel Assemblies:
A.
.Incore 0
}
-B.-
.In-Spent Fuel Storage 489
- 18..
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 l
Page 14 of 14 A
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O PSIEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June 10, 1984 Director, Office of Inspection and Entorcement 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 May 1984 are being sent to you.
Average Daily Unit Power Level Operating 7ata Report Unit Shutdowns and Pover Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, h
W
^#T J
M.
upko, Jr.
G neral Manager - Salem Operations LKM: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 lof 14 8-1-7.R4-I The Energy People c61189 (20M) 1181
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