ML20076H952
| ML20076H952 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/10/1983 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8306200226 | |
| Download: ML20076H952 (14) | |
Text
.
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-311 Unit Name Salem # 1 Date June 10, 1983 s
Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 l
Month May 1983
. Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
16 0
2 0
17 0
3 0
18 0
4 0
19 0
5 0
20 0
6 0
21 0
7 0
22 343 8
0 23 413 9
0 24 518 10 '..
0 25 894
.x y
t 11; 4
5 0
26 974 (tt o
12 0
27-1060 w
-13 0
28 1099 14 0
29 1060 15 0
30 1058
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OPERATING DATA REPORT Docket No. 50-272 Date June 10, 1983 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period May 1983 3.
Lice:. sed Thermal Power (MWt) 3338 4.
Nameplate Rating (Gross MWe) 1135 5.
Design Electrical Rating (Net MWe) 1090 6.
Maximum Dependable: Capacity (Gross MWe)ll24 7.
Maximum Dependable Capacity (Net MWe) 1079 8.
If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Giva Reason
~
N/A 9.
Power Level to Which Restricted, if any (Net MWe) 0
- 10. Reasons for Rectrictions, if any REACTOR TRIP BREAKER PROBLEMS 2/25/83 - 0125 to 5/5/83 - 1830 This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 3623 52632
- 12. No. of Hrs. Reactor was Critical 269.2 494 28219.2
~~~
- 13. Reactor-Reserve Shutdown Hrs.
474.8 2033'74
_3006.5
- 14. Hours Generator On-Line 244.5 260.3 26908
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Grocs Thermal Energy Generated (MWH) 665750 666308 79836499
- 17. Gross Elec. Energy Generated (MWH) 222110 224870 26189720
- 18. Net Elec. Energy Generated (M9HI) 205586 173231 24768084
- 19. Unit Service Factor 32.9 7.2 51.1
- 20. Unit Availability Factor 32.9 7.2 51.1
- 21. Unit Capacity Factor" (using MDC Net) 25.6 4.4 43.6
- 22. Unit Capacity Factor i
(using DER Net) 25.4 4.4 43.2
- 23. Unit Forced Outage Rate 67.1 98.9 32.2
- 24. Shutdowns scheduled cver'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 i
Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page 3 of 14
' UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 REPORT MONTH MAY 1983 Unit Name Snlcm No.1 Date June 10, 1983 Completed by L.K. Miller Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No.
Date Type Hours Reason Down Event System Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence Nuclear Control Rod IA CKTBRK Scram Mechanisms83-030 2/25 F
1673.1 A
1 Nuclear Service WA PIPEXX Water Piping 83-032 5/05 F
385.0 B
1 Feedwater Heater 83-034 5/26 F
14.2 A
5 HB HTEXCH Level Control Traveling Screen / Trash 83-036 5/26 F
4.6 B
HF FILTER Racks / Canal Screens83-038 5/26 F
1.9 HF FILTER 83-040 5/26 F
6.2 HF FILTER 83-042 5/28 F
5.9 HF FILTER 83-044 5/28 F
4.4 HF FILTER 83-046 5/29 F
6.1 HF FILTER i
83-048 5/29 F
4.2 HF FILTER i
Condenser Tube & Water 83-050 5/30 F
4.0 HF HTEXCH Box Cleaning incl Circ Traveling Screens / Trash 83-052 5/30 S
5.7 HP FILTER Rack / Canal Screens l
83-054 5/30 S
4.5 HF FILTER j
83-056 5/31 F
4.0 HF FILTER l
1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 I
F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled D-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-oxplain (NUREG 0161)
Page 4 of 14
MAJOR PLANT MODIFICATIONS DOCKET NO:
50-272 UNIT NAME:
SALEM 1 REPORT MONTH ny 19g3 DATE:
June 10, 1983 COMPLETED BY:
L. K. Miller TELEPHONE: 609/935-6000 Ext. 4455 '
- DCR NO.
PRINCIPLE SYSTEM SUBJECT lEC-0490 Chemical f Volume Control Add a nipple and a cap to existing 3/4" SW valve ICV 240.
lET-1493
'Jaste Disposal-Liquid Install a caustic pump and tank assembly at the suction of the waste evaporator /
feed pump to add sodium hydroxide to the evaporator feed on a temporary basis to allow waste evaporator operation.
lEC-1569A Safety Injection Cut out and replace existing valve ISJ4 with valve 22SJ40.
lEC-1617 Reactor Trip Switchgear Modify mounting of dust covers on DB-50 breakers. Breakers included are A&B Main, A&B Bypass, 11 M/G Output Breaker and 12 M/G Output Breaker.
ISC-0521 waste Disposal-Liquid Install two valves on the common discharge line of laundry pump and chemical drain tank pump.
1SC-0613 Electrical Provide 120V AC power receptacles for Radiation Protection Office areas Service Building 100' El.
ISC-0874 Telephone System Install additional conduits between Control Room and Telephone Poom.
Install additional cable in conduits.
ISC-1015 Turbine Low Vacuum Alarm Change setpoint of PD-188 from 25" HG to 22" HG decreasing.
i i
- DESIGN CHANGE REQUEST 8-1-7.R1 Page 5 of 14 y
_.,,,.. _ ~, _., - _ _
_-4
4 MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MAY 1983 UNIT NAME:
Salem 1 DATE:
June 10, 1983 COMPLETED BY:
L.K. Miller TELEPHONE:
609/935-6000 X4455
- DCit NO.
10CFR50.59 SAFETY EVALUATION 1EC-0490 Installation of the core bores will not affect the integrity of the structure or the safe shutdown of the j
Nuclear Steam Supply System.
No unreviewed safety or environmental questions'are involved.
H 1ET-1493 The temporary hose to be installed is not connected to any safety related equipment and no safety related j
equipment is in the area.
No unreviewed safety or environmental questions are involved.
1EC-1569A These replacement valves are designed to the prsent system and code requirements.
This replacement in no way reduces the integrity and reliability of the Safety Injection System nor does it increase the probability of an accident.
No unreviewed safety or environmental questions are involved.
1EC-1617 This modification will prevent the dust cover from coming loose and falling into the breaker mechanism.
Reliability of the breaker will be improved.
No unreviewed safety or i
environmental questions are involved.
-The addition of these valves does not create any new safety hazards and the Technical Specifications are not I
a f fected.
Additionally, the potential for a malfunction or failure has not been increased.
No unreviewed safety or environmental questions are involved.
i L
1SC-0613 Installation of convenienca receptacles in the Service Building will not affect the operation of any plant safety system.
The proposed change will have no effect on plant function or effluents, however it does improve the efficiency and safety of a function already carried on.
No unreviewed safety or environmental questions are l
involved.
ISC-0874 This installation requires that the cable be installed in accordance with our standard cable control manual l
procedures.
Installation of additional conduit is not i
expected to create or alter any environmental discharges.
No unreviewed safety or environmental questions are involved.
- Design Change Request l
Page 6 of 14 p
[
V MAJOR PLANT. MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MAY 1983 UNIT NAME:
Salem 1 DATE:
June 10, 1983 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/935-6000 X4455
- DCR NO.
10CFR50.59 SAFETY EVALUATION ISC-1015 Changing the setpoint of alarm to reflect the actual turbine trip setpoint will not create any unreviewed safety or environmental questions.
(
4 d
f 4
j d
f i
- Design Change Request
^
Page 7 of 14
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PSE&G SALEM GENERATING SDLTION SAFE 1Y REIATED WORK WDER IOG SAI2M UNIT 1 i
WO NO DEPT WIT EUJIPMENT Trskra-ICATIN 985868 M
1 VALVE, 1FP148 FAIIURE DESCRIPTIN: PEREGM 'iYPE C LEAK RATE TEST APIER VALVE RENORK. 821122.
Cuc<tx;nVE ACTION:
IEAKAGE 249 OVER ALIGABLE m 1554 SCON. IEAKAGE ACCEPTABLE AS IS.
821127.
910237 F0 1
VALVE, 1WL97 FAIIERE DESCRIPTION: REPIACE DIAPHRE.
830104 CORRECTIVE ACTIN:
INSTAT.Tm NEW STEM, DIAPHRAM AND DIAPHRAM E00T. 830106 1
910556 MD 1
VALVE, ISJ4 FAILURE DESCRIPTIW: REPIACE VALVE ISJ4 WITH 22SJ40. BurH ARE MARK FA-46 VALVES. 830204.
CORRBCTIVE ACTION:
1SJ4 REPIAOD Wr1H 22SJ40.
830208 912165 m
1 SERV WPR EXPAN SPOOL a
FAILURE DESCRIPTIW: INSPECT AbD REPLACE AS NWFRSARY DURING OUTAGE. 800418.
l
,i CNRECTIVE ACTION:
CmPIEEE PER WORK OIOER. 821107 W
917897 m
1 12 RHR PWP i
FAIIERE DESCRIPTIW: PWP HAS A SEAL IEAK. 821127.
CORRBCTIVE ACTION:
REPIJCED MBCHANICAL SEAL.
821216 l
921281 MD 1
11 GARGING RMP FAILURE DESCiuvrJm: OU'IBOARD RNP SEAL LEAKING WATER EXCESSIVELY. 821030.
CNRECTIVE ACTION:
INSTAT.TE NEW CUTBOARD SEAL.
821119 l
t i
i l
Page 8 of 14 l
A
PSE&G SALEM GENERATING STATION SAFE 1T REIATED WORK CRDER IOG SAIIM LEIT 1 WO NO DEPT (Nr2 EQUIIMNr n*NnrICATIN 921405 MD 1
11-12 CCNT SLMP PlNP FAIIURE DESCRIPTIW: 10MPS KEEP 'IRIPPING CUT CN OVERIDAD. 821111 CCRRECTIVE ACTIW:
BODI MOICRS MM3 RED ZERO MBGGMS 'IO GROLDO. REPLAGD POIOR EUR fil.
- 12 POIOR m.
830211 922901 MD 1
11 CHTTJm wrR PtNP FAIIURE DidCiurriCN: ICMP BREAKER 'IRIPS CUT W OVERIDAD AFTER APPROK 1 HR.
830316.
l COELM ACTION:
CHECKED CURRENT READDGS. E0020 60 AMPS RLENING. REPIACED 'DfE OVERIDAD HEMIER.
830421.
922969 1:D 1
Cuteercr1VE ACTION:
REPIACED BEARING HOUSING PIATE, INBOARD OIL SEAL AND (>-RING.
830316.
923071 MD 1
CONr AIR IOCK EL 100 FAIIERE DESCRIPTIN:
INNER AND CU'IER DOOR AIR FICW HIGH. 830301.
t CtmunVE ACTION:
AILTUSrED DOCES. 830301.
t 923073 MD 1
VALVE, IFR7 FAIIURE DESCRIPTIW: NO CIDSED DOICATIN. 830301.
CORRECTIVE ACTION:
REPIACED 'IERQUE SWTIUI WITH SWITCH FRm 2PR7. TESTED SAT. 830303.
923096 PO 1
VALVE, IPR 7 i
FAIIERE DESCRIPTIW: WOUID NOT GET WEN LIMIT IN CmTROL ROOM. 830306.
i CCERECTIVE AcrION:
VERIFIED 'IORQUE SWTICI Nor PREIDADED AND LEFT SLT AT 1.
830306.
Page 9 of 14
PSE&G SALEM GENERATING STATIM SAFEIY REIATED WORK WDER IOG SAIIM UNIT 1 WO PO DEPT WIT EGJIPMENT TiEnrirICATIN 923127 MD 1
CCNT AIR IOCK EL 130 FAILURE DESCRIPTIW: HIGH AIR FION W BOITI IMER AND QTIER DOORS. 830301.
CNRECTIVE ACTION:
INNER DOOR GASKET WAS OUT W GROOVE. RESET.
830302.
923167 MD 1
12 OC PUMP m COOLER FAIUJRE DESCRIPTIN: COOLER HAS A COIL LEAK W APPROX 5 GPM. 830223.
CumtL'nVE ACTION:
REPAIRED 'IUBE LEAK IAW MllE. 830306.
923537 MD 1
VALVE,11CI:16 FAILURE DESCRIPTIm: VALVE WILL NDP FULLY CIOSE ELECIRICALLY. 830321.
i CutstLnVE ACTION:
RESET CICSING 'IORQUE SWIYCH 'IO 2.
N N T) IZOICATIm BEING RECEIVED WT1H EDIE i
ICMPS RUNNING.
923580 MD 1
14 cmT FAN ODIL i
FAILURE DESCRIPTIW:
14 CFCU WILL NOP SIART IN ION SPEED. BKR IOOKS m.
830326.
CORRECTIVE ACTIW:
REPIACED BAD 3X REIAY IN 125VDC BREAKER CCNTROL CIRCUIT. 830328 923636 MD 1
WST PURIF PLNP FAILURE DESCRIPTION: PLMP HAS BAD PACKING IEAK.
830407.
l CustLnVE ACTION:
REPLACED MBCHANICAL SEAL AND REALIGED PtNP.
830411.
l 923663 MD 1
12 CC PtNP M COOLER i
FAILURE DESCRIPTI W : 000EER HAS COIL IEAK. 830408.
CORRECPIVE ACTION:
STOPPED LEAKS WITH BELZm A.
830413.
Page 10 of 14
-=
PSE&G SALEM GENERATING SDTIN SAFE 1Y REIATED WORK WDER ILG.
SAIDI UNIT 1
+
WO NO DEPT WIT EQUIPMENT IDENTIFICATIN 924724 MD 1
MIB DOOR SEAL FAILURE DESCRIPTIW: INSPECT AND REPAIR AS NFrMARY. 830324.
Cuc<rl;nVE ACTION:
DOOR SEAL HAS SMALL HOLE WHICH H&DS 'IO 12 PSI. INSTALLED NEW SEAL. 830405.
924816 MD 1
13 C W P COOLIIG P W P FAILURE DESCRIPTIW: PUMP SEENS TO HAVE EXCESSIVE HO PIAY.
830328.
Cuc<rcr1VE ACTION:
NO APPARENT PRmini. END PIAY AT.008 ' IDEAL. 830329.
924830 to 1
- 1 RWSr PURIF PWP FAIIURE DESCRIPTIW: OIL LFAKING FRW BEARDG OIL RESERVOIR. 830330.
Cuo<rx;nVE ACTION:
REPIACED ALL INTERNAL PARPS W PWP. REALINED COUPIJNG. 830405.
924847 PO 1
1B D/G EXH FAN DMPER FAILURE DESCRIPTIW: DAMPER CW'IROL ATTEMPPS 'IO CPERATE BUT DAMPER IS MBCHANICALLY BOUto. 830401.
Cuoci;nVE ACTION:
IDBRICATED DAMPER MBCHANISM AND OPERATED. 830404.
928844 MD 1
1 AFPMP ROOM COOLER FAILURE DESCRIPTIW: COOLER HAS SERVICE WATER LEAK. 830124.
Cuoca;nVE ACTION:
REPAIRED 'IUBE IEAK.
830201.
930912 P
1 VALVE, 11SW24 FAILURE DESCRIPTICN: VALVE CIOSED WITH STRAINER DELTA P AT 45 PSI. SOLENOID AIR SUPPLY VALVE ABNORMALLY hor.
830213.
CORRBCPIVE ACTIW:
REPIACED VALVE DIAPHRAM. 830218.
Page 11 of 14
PSE&G SALEM GENERNrING STM'Im SAFEIY RELATED WORK ORDER IOG SALEM UNIT 1 WO NO DEPT LNIT rJQUIINENT IDENTIFICATION 930917 P
1 VALVE, IPR 17 FAILURE DESCRIPTION: CONTROL IOOM GETS NO @EN OR CLOSED INDICATIN. 830210.
tuceL'nVE ICTION:
REPIACED DIAPHRAM AND STROKED VALVE.
830211.
923179 PD 1
VALVE, IPS1 FAILURE DESCRIPTIW: VALVE WILL NOP OWTROL IN NTIO. 830217.
CORR N_ JCfION:
REPIACED AUIO/ MANUAL STATION MCOULE AND CGTRar.T.ER 1FC-455F. 830222.
Page 12 of 14
SALEM UNIT 1 OPERATIONS
SUMMARY
REPORT MAY 1983 Unit No. 1 began the month in shutdown mode 5 as an operability verification program on safety systems was completed.
The discovery of shellfish in the service water system delayed startup of the unit as a program of chlorination, flushing, and component inspection was undertaken.
This program was successfully completed and a reactor startup was commenced at 1846 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.02403e-4 months <br />, May 20, 1983.
Unit No. I was synchronized at 1932 hours0.0224 days <br />0.537 hours <br />0.00319 weeks <br />7.35126e-4 months <br />, May 21, 1983, and achieved full power operation on May 27, 1983.
Unit No. 1 operated at full power for the remainder of the month.
Page 13 of 14
_ _. _ =. -
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K.
Miller UNIT NAME:
Salem 1 4
DATE:
June 10, 1983 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month May 1983 1.
Refueling information has changed from last month:
YES X
NO 2.
Scheduled date for next refueling:
August 4, 1984 3.
Scheduled date for restart following refueling:
October 21, 1984 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE 6/1/83 B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled? July 1983 5.
Scheduled date (s) for submitting proposed licensing action:
July 1984 (if required) i 6.
Important licensing considerations associated with refueling:
l NONE i
7.
Number of Fuel Assemblies:
A)
Incore 193 l
B)
In Spent Fuel Storage 212 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170 j
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 14 of 14 1
0 PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June 10, 1983 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 May 1983 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, J.
pko, Jr.
General Manager - Salem Operations LKM:sbh cc:
Mr. J. Allan Acting Regiona] 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 Pagel of 14 8-1-7.R4 p,
1 l
l i
The Energy Peopk)
% 2189 (20W 1181