ML20086N401
| ML20086N401 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1984 |
| From: | Miller L, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8402210056 | |
| Download: ML20086N401 (10) | |
Text
___ _
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name' Salem # 1
'Date Feb. 10, 1984
~
. Completed by'
'L. K. Miller Telephone 609-935-6000' Extension 4455
' January 1984 Month-Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET)'
1-15
17 1101 2
454 18
-1102 3~
602 -
19 1100 s.
4
~1088 20 1095 l5;>
1053-21 818 6
506 22 345 7
-557 23 1104
'8 0
24 1097=
4 2 0 25 1101 9s s h.0 ~
'O 26 1080 o
~
'11 232 27 1097 12-1066 28
'1057 L
13'
-1084 29.
1091 p
14:
1091 30 1075
~151 1100 31 1100
.1
.16.
1104' ___
PE8,1-7.R11 840221005$840131 P
I PDR ADOCK 05000272
.R PDR n
L g
4 Page 2 of 10
OPERATING DATA REPORT Docket No.
50-272 Date Jan. 10, 1984 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period January 1984 3.
Licensed Thermal Power (MWt) 3338 4.
Nameplate Rating (Gross MWe) 1135 5.
Design Electrical Rating (Net MWe)
T090 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, if any N/A This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 744 58513
- 12. No. of Hrs. Reactor was Critical 668.2 668.2 33819.4
- 13. Reactor Reserve Shutdown Hrs.
0 0
3033.9
- 14. Hours Generator On-Line 628.4 628.4 32406.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1898054 1898054 97717425
- 17. Gross Elec. Energy Generated (Fnm) 635990 635990 32251090
- 18. Net Elec. Energy Generated (;MWH) 604880 604880 30576192
- 19. Unit Service Factor 84.5 84.5 55.4
- 20. Unit Availability Factor 84.5 84.5 55.4
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor 75.3 75.3 48.4 (using DER Net)~
74.6 74.6 47.9
- 23. Unit Forced Outage Rate 15.5 15.5 28.9 24 Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling 5-31-84
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
M/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 3 of 23 Page 3 of 10
UNIT SHUTDOWN.AND POWER REDUCTIONS Dock t No. 50-272 REPORT MONTH January 1984 Unit N2me Salem No.1 Date Feb. 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 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence-Nuclear other Steam 84-010 1-01 F
19.4 A
3 HA GENERA Generator problems Nuclear Reactor CA VESSEL Vessel Flanges & Seals84-016 1-02 5.0 B
5 16.0 I
84-018 1-02
(84-020 1-03 2.3 Traveling Screens /
Trash Racks /
l 84-022 1-05 8.5 HF FILTER Canal Screens l
84-024 1-06 S
5.5 CH PUMPxx Feed Water Pump l
l 84-026 1-06 S
35.6 Nuclear Steam i
I 84-028 1-07 F
80.7 A
3 CC INSTRU G6nerator Controls Condenser Tube and Waterbox Cleaning 84-030 1-13 S
3.2 B
5 HC HTEXCH (incl Circ Water) l 84-032 1-14 2.8 3 Method 4 Exhibit G 5 Exhibit 1 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. tion of Data C-Refueling 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 (NUREG 0161)
H-Other-explain Page 4 of 10
-7 UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 REPORT MONTH JANUARY 1984 Unit Name Salem No.1 Date Feb. 10, 1984 Telephone 609-935-6000 Completed by L.K. Miller Extension 4455 Method of Cause and Corrective Duration Shutting License No.
Date Type Hours Eeason Down Event System Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence Traveling Screens /
Trash Racks /
l HF FILTER Canal Screens84-034 1-14 S
3.0 B
5 Condensate Tube and Water Box Cleaning l
HC HTEXCH (inci Circ Water)84-036 1-15 3.3 Other Circulating Water System Problems 2.6 84-038 1-16 Condenser Tube and Water Box Cleaning (inci Circ Water)84-040 1-20 2.9 Other Feedwater 84-042 1-21 F
15.5 A
3 CH VALVEX Valves Condenser Tube and Water Box Cleaning 84-046 1-26 S
3.8 B
5 HC HTEXCH (inci Circ Water)84-048 1-26 5.1 3 Method 4 Exhibit G 5 Exhibit '.
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. tion 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 9-Other (LER) File G-Operational Error-explain (NUREG 0161)
H-Other-explain Page 5 of 10
UNIT SHUTDOWN AND POWER REDUCTIONS Docknt No. 50-272 REPORT MONTH JANUARY 1984 Unit Name Salem No.1 Dato Feb. 10, 1984 Telephone 609-935-6000 Completed by L.K. Miller Extension 4455 Method 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 Removed thermometer on Inlet & Outlet IF INSTRU piping 84-050 1-29 S
1.2 B
5 84-052 1-29 F
0.3 A
84-054 1-29 0.3 l
84-056 1-29 0.2 84-058 1-29 0.3 84-060 1-29 0.3 Performed test on HH HTEXCH
- 11 MSR 84-062 1-29 S
7.1 B
Condenser Tube and Water Box Cleaning 84-064 1-30 3.0 HC (inci Circ Water)
Traveling Screens /
Trash Racks /
HF FILTER Canal Screens84-066 1-31 F
1.0 Condenser Tube and Water Box Cleaning 84-068 1-31 S
0.5 HC HTEXCH (inci Circ Water) 3 Method 4 Exhibit G 5 Exhibit 1 1
2 Reason 1-Manual Instructions Salem as F: Forced A-Equipment Failure-explain S: Scheduled B-Maintenance or Test 2-Manual Scram, for Prepara-Source 3-Automatic Scram, tion of Data C-Refueling 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 Page 6 of 10
DOCKET NOi" 50 -272
- ~
~
^~1 PLANT MODIFICATIONS
~
UNIT NAME:
SALEM 1 iPORT MONTH JANUARY 1984 DATE:
FEBRUARY 10, 1984 COMPLETED BY:
L.
K. MILLER TELEPHONE:
(609) 339-4455
- DCR NO.
PRINCIPLE SYSTEM SUBJECT lEC-0717 Various Systems using Replace JX8342A3 so'lenoid valves per f
Asco JX8342 Series'D.C.
TPL 6754 with X8342B3 solenoid I
Solenoid Valves valves per TPL 11891.
Replace JX8342A22 solenoid valves per TPL 6753 with X8342B22 solenoid valves per TPL 11892.
r lEC-16.59 Reactor Vessel Level Remove the bypass valves currently Instrumentation installed in the RVLIS D.P.
instrument rack.
Also, replace ll5VAC neon bulbs in the hydraulic isolator panels (lamps with green screens) with 28VDC incandesant bulbs. including a 2200 dropping resistor).
lEC-1725 Bleed Steam ind Heater Increase water level setpoints by Drain.(G100) two inches on all low pressure feedwater heaters which include
.llA,B,C, 12A,B,C.
lEC-17*45 Main Generator Hydrogen Add additional piping in the main System.
generator and between the generator and hydrogen dryer to provide adequate differential pressure across the hydrogen dryer.
i
~1SC-1255 Common Equipment, Remove the present concrete curbs Buildings and Grounds (dams) at personnel doofs between t
No. 1 & No. 2 Unit Switchgear Ro6ms and replace with an easily l
removable aluminum curb (dam).
The floor between the'two units to be smoothly finished.
Five curbs are involved - 4 at El. 84' r
and 1 at El. 64'.
h h
t.
i
+
[
DESIGN CHANGE REOUFST~
l
- 9-1-7.R1 Page 7 of 10
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH JANUARY 1984 UNIT NAME:
Salem 1 DATE:
February 10, 1984 COMPLETED BY:
L.K.
Miller TELEPHONE:
609/339-4455
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59 1EC-0717 Installation of this DCR will improve system reliability.
No unreviewed safety or environmental questions are involved.
1EC-1659 Installation of this DCR does not result in any new safety concerns.
No unreviewed safety or environmental questions are involved.
1EC-1725 This DCR does not affect any safety related equipment.
No unreviewed safety or environmental questions are involved.
1EC-1745 Installation of this DCR does not involve any change to the FSAR or the Technical Specifications.
No unreviewed safety or environmental questions are involved.
1SC-1225 Implementation of this DCR will not create any new safety hazards, nor will it effect any presently performed safety analysis.
No unreviewed safety or environmental questions are involved.
- DCR - Design Chanae Request Page 8 of 10
SALEM UNIT 1 OPERATIONS
SUMMARY
REPORT JANUARY 1984 Unit No. I was returned to service on January 1, following repairs to a secondary side handhole-cover leak in No. 14 Steam Generator.
On
' January 2, power was reduced to investigate a reactor vessel flange leak.
The leak appears to be minor in nature and well within the Technical Specification limits, and the unit was restored to full power on January 3.
On January 5, unit load was reduced to perform repairs to No. 12 Steam Generator Feedwater Pump governor control linkage.
Power was maintained at approximately 50% until January 7, while mechanical cleaning of No. 11 Steam Generator Feedwater Pump suction strainer was performed.
On January 7, the reactor tripped due to a.high water level condition in No. 14 Steam Generator.
The level was restored to within the operating band, and on January 8, a unit startup was commenced.
Unit No. I was restored to full power operation on January 12, and continued to operate at full power until the reactor tripped on January 21, due to a Lo-Lo level condition in No. 13 Steam Generator.
Unit No. I was returned to full power on January 23, following repairs to a faulty feedwater bypass level controller and feedwater bypass valve.
Full power operation continued until January 29, when load was briefly reduced to 90% for Moisture Separator, Reheater (MSR) vibration testing.
The unit was restored to full power on January 30, and operated at full power for the remainder of the month.
p t
Page 9 of 10
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 1 DATE:
February 10, 1984 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month January 1984 1.
Refueling information has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
May 31, 1984 3.
Scheduled date for restart following refueling: September 4,1984 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE 2/1/84 B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
April 1984 5.
Scheduled date (s) for submitting proposed licensing action:
April 1984 (if required) 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 212 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 1996 8-1-7.R4 Page 10 of 10
l
~
O PSEG-Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 10, 1984 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 January 1984 are being cent to you.
Average, Daily Unit Power Level Operating Data Report
-Unit Shutdowns and Power Reductions Major Plant Modification Operating Summary Refueling Information Sincerely yours,
,1 w-J. M..Zupko, r.
Genera'A Manager - Salem Operations
-LKM:sbh cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I F
631' Park. Avenue y
King of Prussia, PA 19406 Director, Of fice - of Management.
Information and Program Control U.S. Nuclear Regulatory Commission Washington,-DC 20555 Enclosures Page lof 10 8-1-7.R4 4),
-The Energy People 95 2189 (20M) 1181
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