ML18093B298
| ML18093B298 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1988 |
| From: | Miller L, Orticelle A Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8811220333 | |
| Download: ML18093B298 (14) | |
Text
,.,
ttVERAGE DAILY UNIT POWER LE'L 1
Completed by Art Orticelle Month OCTOBER 1988 Day Average Daily Power Level (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
14 0
15 0
16 0
Pg. 8.1-7 Rl Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
50* 311 Salem # 2 11-3-88 609-*~9-3-5---6~0-o-o~~-
4451 Power Level
I
'PERATING DATA REPORT 50-311 11-3-88 935-6000 Completed by Pell White Docket No.
Date Telephone Extension 4451 Operating Status
- 1.
2 *
- 3.
4.
5 *
- 6.
7.
8
- Unit Name Salem No. 2 Notes Reporting Period October 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) 1170 Design Electrical Rating (Net MWe) 1115 Maximum Dependable Capacity(Gross MWe)ll49 Maximum Dependable Capacity (Net MWe) 1106 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. Reasoris for Restrictions, if any N/A
~-------~~~--~~~~-~~~~~~~~~
- 11.
- 12.
- 13.
- 14.
1 5 *
- 16.
1 7.
1 8.
19.
- 20.
- 21.
- 22.
- 23.
- 24.
Hours in Reporting Period No. of Hrs. Reactor was Critical Reactor Reserve Shutdewn Hrs.
Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)
Gross Elec. Energy Generated (MWH)
- Net Elec. Energy Generated (MWH)
Unit Service Factor Unit Availability Factor Unit Capacity Factor (using MDC Net)
Unit Capacity Factor (using DER Net)
Unit Forced Outage Rate This Month 745 0
0 0
0 0
40
-4764 0
0 0
0 0
Year to Date 7320 5688.6 0
56 33. 7 0
18464736 6085020 5817850 76.9 7 6. 9 7 1. 9 '
Cumulative 61825 38051.5 0
36915.5 0
64115257 37714490 35837228 59.7 59.7 52.4 71.3 51.9 4.6 27.9 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:
Estimated date of startup is November 15, 1988.
8-1-7.R2
Completed by No.
Date 0 223 10-01-88 0 223 10-01-88 0 223 10-01-88 0 223 10-01-88 0223 10-01-88 1
F: Forced S: Scheduled Art Orticelle UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1988 Method of Docket No. 50-311 Unit Name Date Telephone Extension
~~~~~~~----'~
Salem No.2 11-3-88 609-935-6000 4451 Duration Shutting License Cause and Corrective Type Hours Reason Down Event 1
2 Reactor Report s
745 c
4 s
7 45 c
4 s
745 c
4 s
7 45 c
4 s
745 c
4 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Component Code 4 Code 5 RC VESSEL RC VESSEL HA GENERA HA TURBIN HC HTEXCH 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther Action to Prevent Recurrence Normal Nuclear Refuelin~
Nuclear Reactor Overhaul Generator Major Overhaul Maj or Turbine Overhaul Misc. Major Condenser 4
Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Overhaul 5
Exhibit Salem as Sou re e e
WO NO 870225128 870226077 870501061 871021055 871201597 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
21 MS 10 (D - 6 3 } I 2 1 FAILURE DESCRIPTION:
VALVE IS LEAKING.
PLEASE TROUBLESHOOT AND REPAIR.
2 2SW144 FAILURE DESCRIPTION:
IS LEAKING AROUND FLANGE.
2 21SW127/22 FAILURE DESCRIPTION:
COMPONENT COOLING HEAT EXCHANGER OUTLET TEMP CONTROL.
2 2B DIESEL GENERATOR GROUND FAILURE DESCRIPTION:
HAS AN INTERMITTENT FIELD GROUND/TROUBLESHOOT.
2 FC-3-21B/SW FAILURE DESCRIPTION:
EXPANSION JOINT/REPLACE EXPANSION JOINT.
WO NO 871218041 880217076 880222104 880401263 880401264 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
21SW23 9 FAILURE DESCRIPTION:
PIN HOLE LEAK BETWEEN HEADER AND VALVE IN 3/4" PIPE.
REPAIR.
2 2CC28 6 FAILURE DESCRIPTION:
BROKEN STEM/REPLACE VALVE/FA-109 TO F-8 IAW DR 86-0601.
2 2SJ29 6 FAILURE DESCRIPTION:
VALVE LEAKS THRU/REPAIR FA-127.
2 2PS3-PZR. SPRAY FAILURE DESCRIPTION:
INLET STOP/REPLACE AIR REGULATOR.
2 2PS1-PZR. SPRAY FAILURE DESCRIPTION:
INLET STOP/PM/REPLACE AIR REGULATOR'S.
WO NO 880414100 880425188 880429061 880502081 880506072 880506093 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2VC14 FAILURE DESCRIPTION:
FAILED LEAK RATE TEST/RESTROKE/MARK NO. FA-128.
2
- 22 CC HT EXCH FAILURE DESCRIPTION:
DEMOLITION AND REPLACEMENT OF PIPING TO THE #22 COMPONENT COOLING HEAT EXCHANGER.
2 2EC22 03 FAILURE DESCRIPTION:
INSTALL NEW SW VALVES/22 S.W. HEADER.
2 24 G/G TUBE 2
FAILURE DESCRIPTION:
LEAK IDENTIFICATION/PLUGGING.
PERFORM WORK NECESSARY TO LOCATE PRIMARY TO SECONDARY TUBE.
21SJ40-DCR FAILURE DESCRIPTION:
DRILL HOLE IN VALVE DISC./FA-46.
2 22SJ40-DCR FAILURE DESCRIPTION:
DRILL HOLE IN VALVE DISC./FA-46.
WO NO 880510134 880624067 880624090 880624092 880624093 880702005 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
ELIMINATE RTD BYPASS PIPING PER 2EC-2230 FAILURE DESCRIPTION:
DEMOLITION OF EXISTING BYPASS PIPING TO SUPPORT RTD MODIFICATION.
2 21 STM. GEN. TUBE LANE FAILURE DESCRIPTION:
LANE BLKG. DEVICE REMOVAL 2SM0629.
2 22 STM. GEN. TUBE LANE FAILURE DESCRIPTION:
LANE BLKG. DEVICE REMOVAL 2SM0629.
2 23 STM. GEN. TUBE LANE FAILURE DESCRIPTION:
LANE BLKG. DEVICE REMOVAL 2SM0629.
2 24 STM. GEN. TUBE LANE FAILURE DESCRIPTION:
LANE BLKG. DEVICE REMOVAL 2SM0629.
2 TYPE C LEAK RATE TESTING FAILURE DESCRIPTION:
PERFORM TYPE C LEAK RATE TESTING ON CONTAINMENT ISOLATION VALVES.
WO NO 880801160 880818057 880818131 880902097 880902170 880908111 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2PS 1-PZR 2
2 2
2 2
FAILURE DESCRIPTION:
SPRAY VALVE-TRIPPED TO MANUAL SEVERAL TIMES.
2EC22 45 FAILURE DESCRIPTION:
REVISE SSPS LOGIC 1/4 RCP BKR OPEN TO 2/4 RCP BKR.
2EC2193/P9 FAILURE DESCRIPTION:
DELETE REACTOR TRIP FOLLOWING A TURBINE TRIP.
2CV79 FAILURE DESCRIPTION:
REGULATOR AIR LINE IS LEAKING. REPAIR.
23 s. w. PUMP FAILURE DESCRIPTION:
PULL 23 SERVICE WATER PUMP AND INSTALL #21 PUMP IAW M6L-2.
2S27C FAILURE DESCRIPTION:
PIN HOLE LEAK NEAR 21SW127/REPAIR.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880921113 2
SPARE SW PUMP FAILURE DESCRIPTION:
INSTALL INTO #25 POSITION.
881003148 2
2G 4KV/460V FAILURE DESCRIPTION:
TRANSFORMER/HEAT DAJ.111.AGE/INVESTIGATE AND CORRECT.
881013080 2
2C-23SWG-008C FAILURE DESCRIPTION:
HANGER LINEAR INDICATION/REPAIR.
881017065 2
2Rl3C/ 23, 25 CFCU RAD MON FAILURE DESCRIPTION:
FAILING/INVESTIGATE AND REPAIR.
881018126 2
2PR1-PZR FAILURE DESCRIPTION:
PRESSURE RELIEF VALVE-NO OPEN INDICATION-INVESTIGATE.
881020105 2
2S27C FAILURE DESCRIPTION:
HOLE IN SPOOL PIECE AT 21SW122/REPAIR.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 881024150 2
21SW22 3 FAILURE DESCRIPTION:
LINKAGES MISSING/REPLACE AND STROKE VALVE.
881028110 2
2PT455 FAILURE DESCRIPTION:
PZR B/U HTR/NOT SHUTING OFF/CORRECT.
891028005 2
FC-3-31 FAILURE DESCRIPTION:
SW EXPANSION JOINT/REPLACE EXPANSION JOINT.
. --. MAJOR PLANT MOD,IF-TIONS
.REPORT MONTH OCTOBER 1988
- DCR NO.
PRINCIPAL SYSTEM None for the period.
Design Change Request DOCKET N
- UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
DESCRIPTION 50-311 Salem 2 November 10,1988 J. Jackson 60 9/339-4455
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 2 OCTOBER 1988 The Unit was shutdown during the period for a refueling/maintenance outage.
As a result of eddy current examination of Nos. 22 and 24 Steam Generators (S/G) the decision was made to plug the Row 1 tubes in all the S/Gs.
\\'....
REFUEL ING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY:
J. Jackson DATE: November 10, 1988 609/935-6000 TELEPHONE:
EXTENSION 4455 Month OCTOBER 1988
- 1.
Refueling information has changed from last month:
- 2.
- 3.
- 4.
YES X
NO ---
Scheduled date for next refueling:
January 6, 1990 Scheduled date for restart following refueling:
February 20,1990 A)
B)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMIN=E=D-....T~O-DATE X
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
November 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
- 8.
- 9.
8-l-7.R4 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:
193 308 1170 1170 March 2003
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 November 11, 1988 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of October 1988 are being sent to you.
RH:sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information L. K. Miller General Manager -
Salem Operations cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-1-7.R4 The Energy People 95-2168 (1 OOM) 12-84