ML20097B038
| ML20097B038 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1984 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8409130474 | |
| Download: ML20097B038 (10) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date August 10,1984 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month July 1984 Day Average-Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 0
3 0
19 0-4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
S 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
P.
8,1-7 R1 l.
l i
k N '/;
/
Page 2 of 10 B409130474 84033i PDR ADOCK 05000272 R
~-
~ OPERATING DATA REPORT Docket No.50-272 Date August 10, 1984 Telephone'935-6000 Completed Inr L. K. Miller Extension 4455 i
Operating Status 1.
' Unit Name Salem No. 1 Notes
~-
2.
Reporting Period July 1984 1.
3.
Licensed Thermal Power (MWt) 3338 4.
Nameplate Rating (Gross MWe) 1135 5.
Design Electrical Rating (Net MWe)
T5T6 6.
Maximum Dependable Capacity (Gross MWe)TIIT 7.
Maximum Dependable Capacity (Net MWe) TOT 4 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 4
This Month Year to Date Cumulative l
- 11. Hours in Reporting Period 744 5111 62136
- 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 (BUGI) 0 3800023' 99619394
- 17. Gross Elec. Energy Generated 1
(BDni) 0 1281380 32896480 i
- 18. Net Elec. Energy Generated (MWH)
(3067) 1206065 31177377
- 19. Unit Service Factor 0
23.4 53.0
- 20. Unit Availability Factor 0
23.4 53.0 l
- 21. Unit Capacity Factor-(using MDC Net) 0 21.9 46.4
- 22. Unit Capacity Factor (using DER Net) 0 21.6 46.0 i
- 23. Unit Forced Outage Rate 100 56.6 30.7
- 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:
8-22-84
- 26. Units in Test Status (Prior to Commercial Operation) :
~ Achieved Forecast 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 l-Page 3 of 10
- =.
UNIT SHUTDOWN AND POWER REDUCTIONS Dockat No.50-272 REPORT MONTH July 1984 Unit N me Snln': No.1 Date August 10,1984 Completed by L.K. Miller Telephone 609-935-6000 Extension 44bb Method of Duration Shutting License Cause and. Corrective No.
Date Type Hours Reason Down Event System Component Action to 1
2 Rea ctor Report Code 4 Code 5 Prevent Recurrence Nuclear 84-174 4-2 S
192 C
4
-~
RC FU ELXX Normal Refueling Generator Liquid HA GENERA Cooling System 84-176 7-9 F
552 A
4 1
2 Reason 3 Method 4 Exhibit G 5 Exhibit l' 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)
Page 4<of 10
i MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 i
REPORT. MONTH July-1984 UNIT NAME:
Salem 1 DATE:
August 10,-1984 COMPLETED BY:
L.K. Miller TELEPHONE:
609/339-4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT lEC-1413 Reactor Coolant Replace reactor coolant wide range RTD's with environmentally qualified elements.
lEC-1572 Hoists & Cranes -
Derate " Overhead Load Handling System" capacity to 2,200 lbs.
.(1.1. tons) or less by changing the "name/ capacity plate"
. marking and adding appropriate' notes to design, maintenance,
-operating and other documents.
As appropriate adjust load limit devices.
ISC-1357 Containment Replace containment fan coil Ventilation unit suction expansion joint
(#14 FCU) with ones of improved deisgn.
1 5
a 1
Page 5 of 10 c-
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272
-REPORT MONTH JULY 1984 UNIT NAME:
Salem 1 DATE:
August 10, 1984 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/339-4455
- DC R NO.
SAFETY EVALUATION 10 CFR 50.59 1EC-1413 Replacement of the reactor coolant wide range RTD's with more durable equipment will not be changing the function (s) of the RTD's.
No unreviewed safety or environmental questions are involved.
1EC-1572 This change derates the decontamination room crane from 4 000 pounds tx) 2200 pounds.
No change in design or component ls) will be done.
No unreviewed safety or environmental questions are involved.
ISC-1357 The replacement of the Containment Fan Coil Unit suction expansion joints with ones of improved design will not effect any presently performed safety analysis nor does it create any new safety hazards.
No unreviewed safety or environmental questions are involved.
- CCR - Design Chango Request Page 6 of 10
231&G SALEM GENERATING STATION SAFETY PELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPP WIT EQUIPME2R IEENTIFICATIW 9900136-5 m 1
- 11 CCMPCNENT COOLING PWP FAIwRE DESCRIPTICN: HIGi OL7HKAf<D PUMP BET @ING VIBRATIN CCRRECTIVE ACTIN:
REPIJCED OUTBOMO BEAPlNGS 931310 30 1
- 1 AUX BUIIDING VENTIIATICN EXHAUST FILTER UNITS FAIIURE DESCRIPfION: RE?CJCE BUFIE WIRING ASSOCIATED WPIH AUX. AIABM POINTS 436 AND 437.
1 CORRECTIVE PCTION:
REELi 7. BUIWP WIRING 84-07-20-660-1 MD 1
REPIACE BOI'IT SHOES AbD SHEAR KEY 939488-5 50 1
1CV75 FAILURE DESCRIPTICN: ICPAIR 'IHE FUFMMITE REPAIR CWRECTIVE ACTICN:
,REFAIR E VALVE 938423-5 CD 1
13MS7; #13 SPEAM GENERA'IOR MIV DRON VALVE FAIIURE DESCRIPTION:
- 13 E7 IS SIIMING STEAM COBRECTIVE PCfICN:
WEIDED IIEE FwG, REPIACED SPEAM A20 FIDG ASSENBLY, INSTATJm A NEW SEAT RING, AND PEPICKED VALVE i
i Page 7 of 10
WIT 1 9900079-2 FD 1
IB Dmu, FAILURE DESCRIPTICN:
10 CPEED CC:ffROL, PREIJBE PWP DID N(7f SIART, AND HI VIB. AIAIM CN S'IART T DIESEL.
CORRECEIVE JCTIW:
EADE UP SPEED CCN11EL CIRCUlT, REPLACED HCR RELAY IN DG. CAB. EDR PRELIBE PtEP, AND REPIN'FD VIBRATIN SWIICH 948019 m
1 RMS STRIP GARP RECORDER FAILURE DESCRIPTICN:
RECORDER WILL IKTT PRINT W SCAN POINES CORRECTIVE 1CTICN:
CIANED INPtTP SELECIOR SWTICH, INSTATT.Fn NEW PRINr INDEX CCNfROL CIRCUIT BOARD, INSTAILED NEW EOINF SOLENOID MO SDCHRWIZED RECWDER 84-07-18-500-1 CD 1
til CFCU FAILURE DESCRIPTICN:
'IRIPPID CN SIIX4 START CuceL'nVE JCTICN:
REPIICED OVFRIDADS 84-07-05-520-4 l
IC DIESEL PRETI1RE PWP FAILURE DESCRIPTICN:
EREAKER TRIP 2FD, PUMP 901ED CateF1m1VE ACTICN:
REPLACED PUMP AND MCEOR i
Page 8 of 10
-. ? ~
SALEM UNIT No.cl OPERATIONS
SUMMARY
-REPORT JULY 1984 Unit No. 1 remained shutdown as the fifth refueling outage-continues.
After installation and. testing of.one Pressurizer Safety Valve the Unit entered Mode.5 on July 19, 1984.
Generator reassembly work
- continues.. Series' connections.and header caps insulation is complete and
- in the cure cycle.
Installation of the rotor has been. completed.
The series connections (exciter end) has been insulated.
Steam Generator secondary side inspections have been completed for all Steam n
i Generators.
Installation of tube lane blocking devices for all_ Steam Generators-has been completed. ~ Type A test _for all Steam Generators has been completed.
Final reactor cavity decon has.been completed.
Reactor vessel stud hole cleaning completed.
The; Reactor Head has been. set in place and the studs installed and tensioned.. Missile Shield installation has been completed.. Pressurizer hanger work has been completed.
Nos. 11, 13 and 14 RCP motors have been installed.
Reactor. Coolant Pumps No. 11 and No.-13_have been aligned.
No. 14 is in the-process of being aligned.
In-core Thermocouple cable upgrade commenced on July 21, 1984.
All Flux Thimbles have-been cleaned and eddy current tested.
Type "C" leak rate testing has been completed.
One hundred and seventeen (117) valves have been tested and accepted.
No. 12 CFCU motor has been installed.
Limitorque valve modifications j
are in progress.
Preparations are in progress for the Type A Containment Integrated Leakage Rate Test.
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Page 9aof 10
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-REFUELING INFORMATION DOCKET NO.:
50-272
- COMPLETED BY
L.K.-Miller UNIT.MAME:
Salem 1
-DATE:
August 10, 1984-
-TELEPHONE:
609/935-6000 EXTENSION:
4455 i-
[ Month July 1984 1.
Refueling information has changed from last month:
YES NO X
~2.
Scheduled date for next refueling:
February 24, 1984 3.
Scheduled date for restart following refueling: September 1,1984 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO JC NOT DETERMINED TO DATE B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES X
NO If no, when is it scheduled?
5.
Scheduled date (s) for submitting proposed licensing action:
j Not required l'
G.
Iniportant licensing considerations associated with refueling:
NONE P
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 i
l
-Page 10 of 10
)
VQh y.
O PSEG Public Service Electric and Gas Company P.O. Box E hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1984 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commiss' ion Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT S ALEM 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 July 1984 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, b
o
/,
. M.
Zupko, Jr.
General 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 10 CEgj>tj 8-1-7.R4
\\i i
The Energy People OS 2169 (20M) 1181