ML18093A834
| ML18093A834 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1988 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8805200111 | |
| Download: ML18093A834 (11) | |
Text
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e AVERAGE DA \\LY UNIT Pc.MER-LEVEL Completed by-;:*'::Pe.11 White Month APRIL 1988 Day Average Daily Power (MWe-NET) 1 0
2 0
3 0
4 0
5 0
6 0
7 0
.8 0
9 0
10 0
11 0
12 0
13 0
ti ti 14 0
15 177 16 1089 P. 8. 1-7 Rl 8805200111 880430
- .PDF~
- ADCIC:K 05000272
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. ~ric:ri Level Day Docket No.
Unit Name Date Telephone Extension 50-272 Salem t 1
- Apri I 10, 1988 609-935-6000 4451 Average Daily Power Level (MWe-NET) 17 1104 18 1104 19 1088 20 1108 21 1104 22 1101 23 1112 24 1096 25 1106 26 1110 27 1101*
28 1107 29 1119 30 1102 31
npERATING DATA REPORT Docket No.50-272 Date: -.':'A_p_r-ri-=-1--=-1"="0-,-=-1"="9':'9':'9-Completed by Pell White Telephone: 935-6000 Extension: ~4~4=5~1----------~
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period April 1988
- 3.
Licensed Thermal Power (MWt) 3411
- 4.
Nameplate Rating (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe)
III5
- 6.
Maximum Dependable Capacity(Gross MWe)ll49
- 7.
Maximum Dependable Capacity (Net MWe) 1106
- 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 1-0. Reasons for Restrictions, if any.
N/A This Month
- 11. Hours in Reporting Period 719
- 12. No. of Hrs. Reactor was Critical 375.25
- 13. Reactor Reserve Shutdown Hrs.
o-----
- 14. Hours Generator On-Line
- 369.65
- 15. Unit Reserve Shutdown Hours 0
- 16. Gross Thermal Energy Generated (MWH)
' ' 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Uni~ Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor
- (using DER Net)
- 23. Unit Forced Outage Rate 1244849 418050 397875 51.4
- 51. 4 50.0
- 49. 6 0
Year to Date 2903 1224. 25 0
1141.15 0
3766834 1263"'400 1186440 39.3 39.3 37.0 36.7 3.0 Cumulative 94992 58919.35 0
56932.95 0
176035843 59335650 56379401 59.9 59.9 53.7
'53.2 23.9
- 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:
N/A 8"'."1-7. R2
UNIT SHUTD:OWN AND POWER REDUCTIONS REPORT MONTH APRIL 1988 Docket No.50-272 Unit Name "s~a~r=em=-""N~o~.~1.---~-
Completed by Pell White.
No.
0032 0040 Date Type 1
3-31-88 s 4-30-88 F
Me~ti~a of Duration Shutting Hours Reason Down 2
Reactor 365.4 B
4
.17 A
5 1
2 Reason F: Forced S: Scheduled A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing F-Administrative G-Operational Error-explain H-Other-explain License Dat e April l0,1988 Telephone 609-935-6000 Extension 4451
-~-----
Cause and Corrective.
Event System Report Code 4 Component Code 5 Action to Prevent Recurrence Exam CB HT EX CH cc VESSEL 3 Method 1-Manual 2~Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther NUCLEAR STEAM GENERATOR TUBE LEAK LOST OF PRESSURIZER PRESSURE
. 4 Exhibit G Instructions*
for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
,'.\\
5 Exhibit 1 Salem as Source II L
WO NO 870406024 870513047 880108061 880113113 880115085 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
14MS175 FAILURE DESCRIPTION:
VALVE LEAKS THRU REPLACE VALVE BONNET.
1 11MS131 FAILURE DESCRIPTION:
HAS A FURMANITED BONNET AND IS BLOWING STEAM.
1 lRCEl-CRDM FAILURE DESCRIPTION:
WELD LEAK-INSPEC. AND REPAIR.
1 POLAR CRANE/AUX HST PAWL DAMAGED FAILURE DESCRIPTION:
THE AUX HOIST LOAD BRAKE RATCHET PAWL IS DAMAGED.
1 13CC 19 7 FAILURE DESCRIPTION:
WELD REPAIR BROKEN LINE WHERE INSTRUMENT LINE TIES INTO THE ROOT VALVE.
l i
SALEM.UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880120048 1
13 CFCU FLOW FAILURE DESCRIPTION:
INDICATION WITH CFCU OUT OF SERVICE. INVESTIGATE 880129101 1
1SJ12 FAILURE DESCRIPTION:
LEAKS BY ITS SEATS.
PERFORM VALVE DISK MODIFICATION 880217106 1
lRCEl FAILURE DESCRIPTION:
INCORE SYSTEM H.P. SEALS LEAKING/REPAIR. "THREE H.P.
SEALS.
MAJOR PLANT MODIFICATIONS REPORT MONTH April 1988
- DCR NO.
lEC-2062 lEC-2202 lSC-1530 PRINCIPAL SYSTEM Service Water Bldg.
Service Water System Containment Vent.
- DCR - Design Change Request DOCKET NO.:
50-272 UNIT NAME:
~S,.....a.... l,_e_m-~1------
DATE:
May 10,1988 COMPLETED BY: J. Ronafalvy TELEPHONE:
609/339-4455 DESCRIPTION This design change provided additional steel supports to modify the existing steel fence (windbreaker wall) at the Service Water Intake Structure, roof elevation 112-0.
The modification consisted of the installation of a steel gate necessary to limit the lifting and removal of heavy loads (such as pumps, motors, etc.) through these gates and not over the fence, to comply with NUREG-0612 document ("Control of Heavy Loads at Nuclear Power Plants"}.
This design change involved replacement of Service Water Pratt motor operated butterfly valves in the Service Water Intake Structure (SWIS).
The existing rubber lined carbon steel Pratt butterfly valves were replaced with Al-Br Jamesbury butterfly valves.
This design change involved shortening the No. 15 riser ventilation duct of the Containment Ventilation System.
This duct had a gooseneck at the discharge end to direct the air downwards.
The duct protrusion (gooseneck) interfered with Containment hatch removal and storage.
MAJOR PLANT MODIFICATIONS REPORT MONTH APRIL 1988 DOCKET NO" 50-272 UNIT NAME:
--=s,-a--=1,_e_m--=--1-------
- OCR lEC-2062 lEC-2202 lSC-1530 DATE:
May 10,1988 COMPLETED BY:
J. Ronafalvy TELEPHONE:
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 Lifting and removing heavy loads through the new steel gates adds to the safety of the operation and precludes the possibility of physical damage to any safety related equipment in the area.
The new steel gates and supports are mounted seismi-cally to meet the existing design criteria, thus maintaining the seismic integrity of this seismic class I structure.
No new failure modes have been introduced as a result of this modification and there is no impact on any previous analysis in the FSAR or changes to the Technical Specifications.
This modification did not alter any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
The valves which were replaced were rubber lined carbon steel valves which were subject to high erosion and they required extensive repairs every outage.
The replacement valves of stainless steel are of better design and will require less maintenance.
This modification did not alter any plant process or discharge or affect the environ-mental impact of the plant.
No unreviewed safety or environmetal questions are involved.
This design change involved work on a safety related item but does not alter the function of the Containment Ventilation System in total.
The purpose of the gooseneck in the original design was to direct the airflow downwards.
The removal of the gooseneck changed the airflow direction from downflow (slightly) to horizontal.
This portion of airflow eventually mixes with the remaining airflow and provides cooling without any reduction in the cooling capacity of the system.
This modification did not alter any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
DCR - Design Change Request
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 APRIL 1988 The Unit began the period shutdown for repairs to a tube leak in No.
13 Steam Generator.
The leaking tube was identified and mechanically plugged.
In addition, a previously plugged tube which was suspected to be leaking through was tested and seal welded.
The Unit was subsequently returned to service on April 16, 1988, and operated at full power for the remainder of the period.
REFUELING INFORMATION DOCKET NO.:
COMPLETED BY:
J. Ronatalvy UNIT NAME:
50-272 Salem 1 DATE:
May 10,1988 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month APRIL 1988
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
April 15, 1989
- 3.
Scheduled date for restart following refueling: May 30, 1989
- 4.
A)
B)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE X
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
February 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
February if required
- 6.
Important licensing considerations associated with refueling:
- 7.
- 8.
- 9.
NONE Number of Fuel Assemblies:
A)
Inc ore B)
In Spent Fuel Storage Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-l-7.R4 193 464 1170 1170 September 2001
Pressurizer Spray Valve lPSl Partially Stuck Open On April 20, 1988, an operator identified that the Pressurizer pressure was dropping rapidly with the small group of backup heaters and the control group of heaters in service.
The large group of backup heaters were energized and Pressurizer pressure continued to decrease.
An operator was dispatched to investigate.
He found the lGPX and lEPX infeed breakers clqsed, but many individual deions tripped.
The deions were reset and Pressurizer pressure continued to decrease.
Pressurizer level was increased and load was reduced in an attempt to reduce the rate of decreasing Pressurizer pressure.
Due to maintaining the temperature high for Pressurizer pressure considerations, the Over Temperature Delta Temperature setpoint was reached and a brief turbine runback was experienced.
A Containment entry was made and Valves 1PS24 & 1PS28 were closed to isolate the Pressurizer Spray Valves. After the Pressurizer Spray Valve were isolated, pressure turned and started to increase.
The lowest Pressurizer pressure reached was 1980 psig.
By opening the Pressurizer Spray Block Valves one at a time, it was determined that Valve lPSl was partially stuck open.
Pressurizer pressure is presently being maintained with the small group of backup heaters in service along with the controlling group and Valve lPSl isolated. Additional details of this occurrence can be found in Salem Unit 1 Incident Report 88-162.
e PS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 May 14, 1988 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 April 1988 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours,
~~
J. M. Zupko, Jr.
General Manager -
Salem Operations RH:sl cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 The Energy People 95-2189 (11 M) 12-84