ML20215F194
| ML20215F194 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1987 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706220276 | |
| Download: ML20215F194 (8) | |
Text
V AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date June 10,1987 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month' May 1987 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET).
(MWe-NET)'
1 1123 17 1106 2
1096 18 1114 3'
1114 19 1112 4
1129 20 1116 5
1112 21 1120 6
1117 22 1109 7
1128 23 1115 8
1115 24 826 t.
9 1111' 25 1157 10 1107 26 1062
'll 1140 27 1115 4
12 1001 28 1117 13 1091 29 878 14 1120 30 257 j
15 1115 31 271 16 1111 P.
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OPERATING DATA REPORT Docket No.50-272-Date June 10,1987 Telephone 935-6000 Completed by Pell White Extension ~4451 l
Operating Status
)
1.
Unit Name Salem No. 1 Notes l
2.
Reporting Period May 1987 l
3.
Licensed Thermal Power (MWt) 3411 j
4.
Nameplate Rating (Gross MWe) 1170 5.
Design Electrical Rating (Net MWe)
ITTY 6.
Maximum Dependable Capacity (Gross MWe)ll49 7.
Maximum Dependable Capacity (Net MWe) TTUE 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)
NA
- 10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 3623 86880
- 12. No. of Hrs. Reactor was Critical 744 3472.5 54755.1
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 744 3427.7
- 15. Unit Reserve Shutdown Hours 0
0 52856.3 0
- 16. Gross Thermal Energy Generated (MWH) 2378695 10713530 163369576
- 17. Gross Elec. Energy Generated (MWH) 799020 3588890 54286890
- 18. Net Elec. Energy Generated (MWH) 771781 3447201 51631969
- 19. Unit Service Factor 100 94.6 60.8
- 20. Unit Availability Factor 100 94.6 60.8
- 21. Unit Capacity Factor (using MDC Net) 93.8 86.0 53.7
- 22. Unit Capacity Factor (using DER Net) 93.0 85.3 53.3
- 23. Unit Forced Outage Rate 0
5.4 25.4
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling Outage - October 5, 1987 - @ 55 Days
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A
- 26. Units in Test Status (Prior to Commercial Operation):
1 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
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' MAJOR PLANT MODIFICATIONS DOCKET NO.:.
50-272 REPORT' MONTH MAY 1987 UNIT NAME:
Salem 1 DATE:
June 12, 1987 1
COMPLETED BY:
L. Miller j
' TELEPHONE:
609/339-4497
_j l
i l
- DCR NO.
PRINCIPAL SYSTEM SUBJECT i
L 1EC-2027
. Fire Protection This DCR calls for-the replacement of 38 fire doors in the Auxiliary Building with hollow metal doors.
There 4
will be 1 door frame replaced.
I 1EC-2062 Service Water Modify the existing steel
- pkg. 1 Intake Structure fence (wind breaker _ wall) by providing a gate on the north
& south walls, at the Service Water Intake Structure, Roof elevation 112'-0".
J
.1
- DCR - Design Change Request
i t
}
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i
. MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MAY 1987 UNIT NAME:
Salem 1 DATE:
June 12, 1987 COMPLETED BY:
L.
Miller d
TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1EC-2027 The replacement fire doors are not safety related j
equipment.
Since the new doors replaced existing fire doors in kind, there are no changes to the UFSAR.
The fire doors are essentially passive and inert so that a failure of the doors will not 4
I result in any damage or influence the operation of any safety related equipment. There is no impact on any Technical Specification basis.
This change ensures that all fire doors in the Unit 1 side of i
the Auxiliary Building are fire related and have appropriate hardware attached.
This is essential for maintaining fire separation between safety related equipment. The replacement fire doors have the same or better fire rating than the doors replaced.
The replacement fire doors have no impact on any plant process of discharge.
No unreviewed safety or environmental questions are involved.
IEC-2062 Package 1 - Lifting and removing heavy loads through the new steel gates addes to the safety of operation and precludes the possibility of physical damage to any safety related equipment in the area.
The new steel gates and supports are mounted seismically to meet '.e existing criteria, thus maintaining the integrity of the Seismic Class I Structure.
No new failure modes have been introduced because the existing fence and new gate have been designed to withstand a seismic event as well as winds of one hundred (100) miles per hour.
There is no impact on any previous analysis of the FSAR nor changes to the Technical Specifications.
This modification has not changed any plant process or discharge nor affected the' existing environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request i
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 MAY 1987 The unit began the period operating at one hundred percent (100%)
power,:1,155 MWe gross, and continued at that level until May 12, 1987, when power was reduced to seventy one percent (71%), for system stability requirements during a thunderstorm.
The Unit was returned to full power operation and continued at that level until May 24, 1987, when power was reduced to fifty eight percent (58%) for planned maintenance.
On May 25,.1987, upon completion of the planned maintenance on No. 12 Steam Generator Feed Pump suction strainer, power was increased to one hundred percent (100%).
The Unit continued to operate at that power until May 29, 1987, when a load reduction to seventy percent (70%) power was performed as a result of a transformer trip out at the New Freedom switching station.
Later, the same day, the load reduction was continued to thirty percent (30%) power to I
place the Unit in a condition below the P-8 Interlock (35%) for energizing the auxiliary power transformer.
On May 31, 1987, upon successful completion of energizing the auxiliary power transformer, a power ascension was commenced for the remainder of the period.
l 1
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' REFUELING INFORMATION I
DOCKET NO.:-
50-272-COMPLETED BY:
L. K '. Miller UNIT NAME:
Salem 1 DATE:
June 12, 1987 TELEPHONE:
609/935-6000 EXTENSION:
4497
- MonthL May 1987 1.
Refueling.information'has changed from last month:
YES NO X'
- 2.
Scheduled date'for next refueling:
October 3, 1987 3.
Scheduled date for restart following refueling: December 2, 1987 4.
A)
Will Technical. Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE X
B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it. scheduled?
September 1987-
. 5.
Scheduled 'date (s) for_ submitting proposed licensing. action:
l September 1987 if required-l 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of~ Fuel' Assemblies:
A)
Incore 193 B)'
In Spent Fuel Storage 380 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
m
,, ' ;LJ
- O PSEGt
- Public Service Electt'ic a'nd Gas Company' P.O. Box E Hancocks' Bridge, New Jersey 08038 Salem Generating Station '
June'15, 1987 i
Director, Officefof Management j
U.S. Nuclear Regulatory Commission j
-Document' Control Desk
- Washington, DC 20555
Dear Sir:
~
MONTHLY _ OPERATING REPORT SALEM NO. 1
' DOCKET NO.-50-272
^
In compliancewith Section 6.9.1.6, Reporting Requirements for the l
Salem Technical Specifications', the original copy of the monthly s
operating reports:for'the month'of May 1987 are being'sent to you.
, Average Daily Unit' Power-: Level Operating Data Report i
Unit Shutdowns and Power-Reductions
' Major Plant Modification-Operating Summary Refueling Information-l Sincerely yours s
[
a J. M.
Zupko, Jr.
General Manager - Salem Operations RH:sl.
-cc:
Dr. Thomas E. Murley
)
Regional Administrator USNRC j
Region I-1 631 Park Avenue King of Prussia', PA 19406 Enclosures 8-1-7.R4 p,\\
. The Energy People' osm m.n m