ML20206Q264
| ML20206Q264 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1987 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8704210373 | |
| Download: ML20206Q264 (9) | |
Text
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w g-AVERAGE DAILY UNIT POWER LEVEL Docket No.'
50-272 Unit Name
-Salem # 1 Date April 10,1987 Completed by Pell White Telephone:
'309-935-6000 Extension.
4451 Month March 1987 Day Average Daily Power Level Day Average. Daily Power Level (MWe-NET)
(MWe-NET)
-1
-1010 17 443 2.
807 18 643 3
805 19 655 4
806 20 655 5
774 21 682 6
692 22' 712' 7
711 23 793 8
634 24 751 9
0 25 743 10 0
26 750 11 0
'27 716 12 0
28 1011 13 0
29 1061 14 0
30 1108 15 0
31 982 16 0
P.
8.1-7 R1 l2 3 870331 R
K 05000272
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-.~e-OPERATING DATA REPORT Docket No.50-272-Date April-10,1987 -
Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status 1.
Unit Name Salem-No. 1 Notes 2.
Reporting Period March 1987 3.
Licensed Thermal Power (MWt) 3411 4.
Nameplate Rating (Gross MWe)
TITU 5.
Design Electrical Rating (Net MWe)
ITTE 6.
Maximum Dependable Capacity (Gross MWe)1149 7.
Maximum Dependable Capacity (Net MWe) ITOT 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 This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 2160 85417
- 12. No of Hrs. Reactor was Critical 593.5 2009.5 53292.1
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 548.7 1964.7 51393.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1396461.6 5951931.6 158597977.6 l
- 17. Gross Elec. Energy Generated i
(MWH) 453720-1986630 52684630
- 18. Net Elec. Energy Generated (MWH) 426626-1902626-50087394 1
- 19. Unit Service Factor 73.8-91.0 60.2
- 20. Unit Availability Factor 73.8-91.0 60.2
- 21. Unit Capacity Factor (using MDC Net) 51.8 79.6-53.0
- 22. Unit Capacity Factor (using DER Net) 51.4 79.0 52.6
- 23. Unit Forced Outage Rate 26.3 9.0 25.9
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NA
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/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 l
8-1-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH MARCH 1987 Unit Name Salem No.1 Late April 10,1987 Completed by Pell White Telephone 609-935-6000 Extension 44 51 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 Station Service Transformer Station 0095 03-08-87 F
195.35 A
1 EG TRANSF Power Aux 0097 03-17-87 F
10.00 A
5 HH PIPEXX Feedwater Piping 0098 03-17-87 F
12.17 A
5 HH PIPEXX Feedwater Piping 0100 03-18-87 F
84.75 A
5 HH PIPEXX Feedwater Piping
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A y,~,
s z..:,
__, j.~ i" t7;:- ; 7, m,,-
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2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 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)
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MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MARCH 1987 UNIT NAME:
Salem 1 DATE:
April 13, 1987 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR NO.
PRINCIPAL SYSTEM SUBJECT 1EC-1788 Various Environmentally upgrade numerous safety related Limitorque valve motor operators.
This upgrading is to be accomplished by the replacement of the existing motor operator with a new motor operator which is fully environmentally qualified for use in established or potentially harsh environmental zones.
1EC-1845 Fire Protection Provide increased sprinkler protection in all bays of the charging pump area el.
84'.
1EC-1895 A-C Power System Upgrade the fast transfer of 4KV the 4KV vital buses on an undervoltage condition, by replacing the existing, obsolete undervoltage transfer relays with reliable state-of-the-art type relays.
1SC-0630A Main Steam Replace 11MS46 and 13MS46 auxiliary feedwater pump turbine swing check valves with new check valves of different design.
- DCR - Design Change Request
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~ MAJOR PLANT MODIFICATIONS-DOCKET NO.:--
50-272 REPORT MONTH MARCH 1987-UNIT-NAME:-
Salem 1-DATE:'
April 13, 1987 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497 "DCR-SAFETY EVALUATIONL10'CFR 50.59 lEC-1788
~This DCR provides for the environmental upgrade of numerous safety related-limitorque. valve motor:
operators.
This upgrade was accomplished by the i
replacement of the existing motor-operators-with a new
. motor operator.- This.DCR replaced existing motor operators which were not environmentally. qualified with new motor _ operators wich are environmentallyqualified,-
for harsh' environment service that actually increases the functional reliability =of the affected valves. The-modifications which were performed ~by way of this DCR will not alter any plant process or discharge and will not effect the existing environmental-impact of the i
plant.
Therefore, no unreviewed safety or environmental questions are' involved.
^
4-lEC-1845 This DCR provides.for. increased sprinkler proteciton in-all bays of the charging pump area ~(El. 84'), this system is being added-to comply with the NRC Appendix.R requirements.
Piping for the sprinkler system is seismically supported to' prevent collapsing cn1 the charging pumps.
The. charging pump' motors will'be
~
shielded from water spray to prevent possible damage'or malfunction.. The charging' pump areas have.two drains to remove water from the areas should the sprinkler:-
systems operate.
'This DCR will not change any plant process or discharge and will not effect the existing environmental impact of the plant.
.Therefore, no unreviewed safety or environmental questions are involved.-
1
- DCR - Design Change Request i
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1
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH MARCH 1987 UNIT NAME:
Salem 1 DATE:
April 13, 1987 COMPLETED BY:
L.
Miller TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1895 This DCR provides for the replacement of the existing, seismically qualified, Standard Rochester Instrument Systems (RIS) Undervoltage Relays wich seismically qualified, Standard ITE Undervoltage Relays in the safety related, 4KV Vital Bus Switchgear cubicles LAID, 1BlD and ICID.
The replacement ITE Relays will upgrade the 4KV Vital Bus Undervoltage Transfer response without degrading any safety related functions or systems.
The reason for this change was the reoccurring problems with the existing, obsolete RIS type XET-230 Undervoltage Transfer Relays that have resulted in undesirable outages of the 4KV Vital Bus System in order to effect repairs.
This DCR will not change the plant process nor discharge and will not impact the existing environmental impact of the plant.
Therefore, no unreviewed safety or environmental questions are involved.
1SC-0630A This DCR provides the Auxiliary Feedwater Pump Turbine Swing Check Valves (11MS46 and 13MS46) with new check valves of different design.
The existing valves' design did not perform as originally intended causing violent oscille.cion of the valves disc limited by the valves seat and top of the valves body rendering them inoperable.
The replacement of MS46 valves by new valves of better design will improve the system performance and in no way will create a new safety hazard.
There is no new pipe routing, functional 1
modification of setpoints or introduction of a new failure mode.
This DCR will not change any plant process or discharge and will not effect the existing environmental impact of the plant.
Therefore, no unreviewed safety or environmental questions are involved.
- Design Change Request
A SALEM GENERATING ~ STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 MARCH 1987 On Sunday,_ March 1, the high voltage lines _from Hope Creek to Keeney 3 (5015) parted when a tanker struck and destroyed one of the. towers in the Delaware River.
Two other towers suffered damage-from the sudden change in tower forces.
The Salem and Hope Creek Units were reduced-to approximately 75% and were held at that level for electrical system stability.. Initial indications are that repairs-could-take between 12 and -18 months to return the line to -service. 'In~the interim, steps are being taken to change the relaying. protection'(trip-a-unit scheme) so that the units can be returned to near 100% power.
The unit operated at 100%, 1,155 MW gross until-Sunday when' power,was reduced to 75% as described above. _The unit operated at 75%, 850 MW gross until Friday, March 6, when the: unit was reduced to approximately 65%, 700 MW gross, Ibnited_by electrical system stability.
At 2347 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.930335e-4 months <br /> on Sunday, March 8, No. 1 unit 1was removed from service following a controlled shutdown to perform planned maintenance and to reconnect the No. 1 Auxiliary Power Transformer.
This shutdown concluded the unit's second longest period of continuous operations, 165 days'.
The unit entered Mode 2 on Sunday, March 15, and held at approximately 3% power because of problems. with a main steam stop valve- (11MS167).
The valve was repaired and the unit was synchronized early Monday morning.
Power was increased to approximately 64%, 707 MW gross where it was held while repairs were made to #12 Steam Generator Feed Pump recirculation line.
The repair was completed on Saturday, March 21,.
and power escalated to 71%, 790 MW gross-late in the evening.
The unit remained at 71%, 790 MW until Friday, March 27, when the trip-a-unit scheme was energized following a presentation meeting with l
the NRC.
A power escalation was initiated and 100%, 1,150 MW was 1
achieved early Sunday afternoon.
On Tuesday, March 31, power was reduced to 790 MW at the Load Dispatcher's request because the trip-a-unit scheme was de-energized due to an approaching thunderstorm.
Power was increased to 100%, 1,130 MW gross late the same day.
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REFUELING INFORMATION' 1
DOCKET. NO'. :
50-272 ?
COMPLETED BY:
-L.K.
Miller-UNIT NAME:'
Salem 1 DATE:. April-13,-1987-TELEPHONE :- 609/935-6000 EXTENSION:
4497 Month March 1987-1.
Refueling information has changed from last month:.
'YES NO X:
2.
Scheduled date for next refueling:
September-12, 1987, 3.
Scheduled date for restart ~following refueling: November 126, 1987 4.
A).
Will Technical Specification changes or other.l'icense amendments be required?
YES NO NOT DETERMINED TO M X B)~
Has the reload fuel design been reviewed by.the Station Operating Review Committee?:
i YES NO X
If no, when is it scheduled?
August-1987-5.
Scheduled date (s) for submitting proposed licensing action:
August 1987 if required-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-a i
9.
Date of-last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
September-2001-8-1-7.R4 H
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O PSEG Public 9ervice Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 13, 1987 Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of March 1987 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Powdr Reductions Major Plant Modification Operating Summary Refueling Information Sincerely yours, v4$)
9 J.
M.
Zupko, Jr.
General Manager - Salem Operations JR:sl cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-1-7.R4 J,
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