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{{#Wiki_filter:e AVERAGE DA, LY UN, T PafER IVEL Comp I eted by **::"*:.,Pe I I White Month *APRIL 1988 Day Average Daily . (MWe-NET) 1 1089 2 1072 3 1065 4 1088 5 1093 6 1094 7 1092 8 1096 9 1083 10 1091 ' ' 11 1090 l:l 1119 13 1104 " " 14 .. 1095 15 1074 16 1094-Pg. 8.1-7 Rl '8805200103 880430 PDR ADOCK 05000311 R DCD Power Level *. Docket Unit Name* Date Telephone Extension Day Average Daily (MWe-NET) | {{#Wiki_filter:e AVERAGE DA, LY UN, T PafER IVEL Comp I eted by **::"*:.,Pe I I White Month *APRIL 1988 Day Average Daily . (MWe-NET) 1 1089 2 1072 3 1065 4 1088 5 1093 6 1094 7 1092 8 1096 9 1083 10 1091 ' ' 11 1090 l:l 1119 13 1104 " " 14 .. 1095 15 1074 16 1094-Pg. 8.1-7 Rl '8805200103 880430 PDR ADOCK 05000311 R DCD Power Level *. Docket Unit Name* Date Telephone Extension Day Average Daily (MWe-NET) | ||
' . 17 1100 18 1095 19 1095 20 1110 21 684 22 0 23 0 24 924 25 1079 26 1100 27 1114 28 1097 29 1099 30 1091 31 . * .. 50-311 Salem i 2 Apri I 10, 1988 609-935-6000 4451 Power Level s *. ! *:. *=-c .. -.. | ' . 17 1100 18 1095 19 1095 20 1110 21 684 22 0 23 0 24 924 25 1079 26 1100 27 1114 28 1097 29 1099 30 1091 31 . * .. 50-311 Salem i 2 Apri I 10, 1988 609-935-6000 4451 Power Level s *. ! *:. *=-c .. -.. | ||
.. e 0PERATING DATA REPORT Docket No.' 50-311 Date Completed by -**Pell White Operating Status Telephone 935-6000 Extension 4451 -------1. 2. 3. 4. 5. 6. 7. 8. Unit Name Salem No. 2 Reporting Period April 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) II'1rr Design Electrical Rating (Net MWe) 11T3" Maxim'ilm Dependable Capacity(Gross Maximum Dependable Capacity (Net MWe) ITifO Notes If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________ | .. e 0PERATING DATA REPORT Docket No.' 50-311 Date Completed by -**Pell White Operating Status Telephone 935-6000 Extension 4451 -------1. 2. 3. 4. 5. 6. 7. 8. Unit Name Salem No. 2 Reporting Period April 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) II'1rr Design Electrical Rating (Net MWe) 11T3" Maxim'ilm Dependable Capacity(Gross Maximum Dependable Capacity (Net MWe) ITifO Notes If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________ | ||
: 9. Power Level to Which Restricted, if any (Net MWe) N/A | : 9. Power Level to Which Restricted, if any (Net MWe) N/A | ||
: 10. Reasons for Restrictions, if any N/A 11 .. 12. 13. 14. 15. 16. ' ' 17. 18. 19. 20. 21. 22. 23. 24. This Month Year to Date Hours in Reporting Period 719 No. of Hrs. Reactor was Critical 689.3 Reactor Reserve Shutdown Hrs. -.....,0 __ _ Hours Generator On-Line 664.04 Unit Reserve Shutdown Hours O Gross Thermal Energy Generated (MWH) 2249256 Gross Elec. Energy Generated (MWH) 750550 Net Elec. Energy Generated (MWH) 719576 Unit Service Factor 92.4 Unit Availability Factor 92.4 Factor ** (usingMDCNet) 90.5 Unit Capacity Factor 2903 28 73. 3 0 2844.34 0 9570418 3190410 3062440 98.o 98.o 95.4 57408 35236. 2 0 4126.14 0 55220939 34819940 33081818 59.4 59.4 52.1 (using DER Net) 89.8 94.6 51.7 Unit Forced Outage Rate Shutdowns scheduled over next Refuelin . Outa e Scheduled to 7. 6 2 29. 3 6 months (type, date and duration of each) be in 9-1-88 and lastin for 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-1-7.RZ Completed by No. Date 0078 4-21-BtS 0079 4-22-88 1 F: Forced S: Scheduled 1;. '. I'*' 1* : i!) *,; ***:*; 1 .. ,:. lltlIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1988 Uock.et No | : 10. Reasons for Restrictions, if any N/A 11 .. 12. 13. 14. 15. 16. ' ' 17. 18. 19. 20. 21. 22. 23. 24. This Month Year to Date Hours in Reporting Period 719 No. of Hrs. Reactor was Critical 689.3 Reactor Reserve Shutdown Hrs. -.....,0 __ _ Hours Generator On-Line 664.04 Unit Reserve Shutdown Hours O Gross Thermal Energy Generated (MWH) 2249256 Gross Elec. Energy Generated (MWH) 750550 Net Elec. Energy Generated (MWH) 719576 Unit Service Factor 92.4 Unit Availability Factor 92.4 Factor ** (usingMDCNet) 90.5 Unit Capacity Factor 2903 28 73. 3 0 2844.34 0 9570418 3190410 3062440 98.o 98.o 95.4 57408 35236. 2 0 4126.14 0 55220939 34819940 33081818 59.4 59.4 52.1 (using DER Net) 89.8 94.6 51.7 Unit Forced Outage Rate Shutdowns scheduled over next Refuelin . Outa e Scheduled to 7. 6 2 29. 3 6 months (type, date and duration of each) be in 9-1-88 and lastin for 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-1-7.RZ Completed by No. Date 0078 4-21-BtS 0079 4-22-88 1 F: Forced S: Scheduled 1;. '. I'*' 1* : i!) *,; ***:*; 1 .. ,:. lltlIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1988 Uock.et No | ||
* Unit Name Date Telephone Extension | * Unit Name Date Telephone Extension | ||
Line 47: | Line 47: | ||
609/339-4455 DESCRIPTION This modification installed drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing. This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve. | 609/339-4455 DESCRIPTION This modification installed drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing. This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve. | ||
MAJOR PLANT MODIFIC,IONS REPORT MONTH -APRIL 1988 *DCR SAFETY EVALUATION 10 CFR 50.59 DOCJT NO: 50-272 UNIT NAME: | MAJOR PLANT MODIFIC,IONS REPORT MONTH -APRIL 1988 *DCR SAFETY EVALUATION 10 CFR 50.59 DOCJT NO: 50-272 UNIT NAME: | ||
DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: | DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: | ||
(609)339-4455 2SC-1323 This design change did not increase the probability or consequences of an accident. | (609)339-4455 2SC-1323 This design change did not increase the probability or consequences of an accident. | ||
By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification. | By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification. | ||
Line 64: | Line 64: | ||
YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee? | YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee? | ||
YES NO X If no, when is it scheduled? | YES NO X If no, when is it scheduled? | ||
August, 1988 5. Scheduled date(s) for submitting proposed licensing action: August 1988 if required 6. Important licensing considerations associated with refueling: | August, 1988 5. Scheduled date(s) for submitting proposed licensing action: August 1988 if required 6. Important licensing considerations associated with refueling: | ||
: 7. 8. 9. NONE Number of Fuel Assemblies: | : 7. 8. 9. NONE Number of Fuel Assemblies: | ||
A) Inc ore B) In Spent Fuel Storage Present licensed spent fuel storage capacity: | A) Inc ore B) In Spent Fuel Storage Present licensed spent fuel storage capacity: |
Revision as of 17:06, 25 April 2019
ML18093A833 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 04/30/1988 |
From: | RONAFALVY J, WHITE P, ZUPKO J M Public Service Enterprise Group |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
NUDOCS 8805200103 | |
Download: ML18093A833 (10) | |
Text
e AVERAGE DA, LY UN, T PafER IVEL Comp I eted by **::"*:.,Pe I I White Month *APRIL 1988 Day Average Daily . (MWe-NET) 1 1089 2 1072 3 1065 4 1088 5 1093 6 1094 7 1092 8 1096 9 1083 10 1091 ' ' 11 1090 l:l 1119 13 1104 " " 14 .. 1095 15 1074 16 1094-Pg. 8.1-7 Rl '8805200103 880430 PDR ADOCK 05000311 R DCD Power Level *. Docket Unit Name* Date Telephone Extension Day Average Daily (MWe-NET)
' . 17 1100 18 1095 19 1095 20 1110 21 684 22 0 23 0 24 924 25 1079 26 1100 27 1114 28 1097 29 1099 30 1091 31 . * .. 50-311 Salem i 2 Apri I 10, 1988 609-935-6000 4451 Power Level s *. ! *:. *=-c .. -..
.. e 0PERATING DATA REPORT Docket No.' 50-311 Date Completed by -**Pell White Operating Status Telephone 935-6000 Extension 4451 -------1. 2. 3. 4. 5. 6. 7. 8. Unit Name Salem No. 2 Reporting Period April 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) II'1rr Design Electrical Rating (Net MWe) 11T3" Maxim'ilm Dependable Capacity(Gross Maximum Dependable Capacity (Net MWe) ITifO Notes If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________
- 9. Power Level to Which Restricted, if any (Net MWe) N/A
- 10. Reasons for Restrictions, if any N/A 11 .. 12. 13. 14. 15. 16. ' ' 17. 18. 19. 20. 21. 22. 23. 24. This Month Year to Date Hours in Reporting Period 719 No. of Hrs. Reactor was Critical 689.3 Reactor Reserve Shutdown Hrs. -.....,0 __ _ Hours Generator On-Line 664.04 Unit Reserve Shutdown Hours O Gross Thermal Energy Generated (MWH) 2249256 Gross Elec. Energy Generated (MWH) 750550 Net Elec. Energy Generated (MWH) 719576 Unit Service Factor 92.4 Unit Availability Factor 92.4 Factor ** (usingMDCNet) 90.5 Unit Capacity Factor 2903 28 73. 3 0 2844.34 0 9570418 3190410 3062440 98.o 98.o 95.4 57408 35236. 2 0 4126.14 0 55220939 34819940 33081818 59.4 59.4 52.1 (using DER Net) 89.8 94.6 51.7 Unit Forced Outage Rate Shutdowns scheduled over next Refuelin . Outa e Scheduled to 7. 6 2 29. 3 6 months (type, date and duration of each) be in 9-1-88 and lastin for 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-1-7.RZ Completed by No. Date 0078 4-21-BtS 0079 4-22-88 1 F: Forced S: Scheduled 1;. '. I'*' 1* : i!) *,; ***:*; 1 .. ,:. lltlIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1988 Uock.et No
- Unit Name Date Telephone Extension
.)U-.ll 1 Salem No.2 Pell White ... *.
- . . * .* :_ 'i: * :
- 1 ...... ::,:
- Method of Duration Shutting Type Hours Reason Down 1 F F 2 Reactor 22.7 A 3 32.27 A 3 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction License Event Report E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain
- "' System Code 4 CB CB 3 Method I-Manual Component Code 5 INSTRU HT EX CH 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther .. .. , ..
10 6 1988 60 -935-6 00 4451 Cause and Corrective Action to Prevent Recurrence REACTOR COOLANT FLOW INDICATION STEM GENERATOR LEVEL 4 t:xhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit Salem as Source e*
- WO NO 870609036 870713077 870729104 871016130 871202144 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2 23SW228 FAILURE DESCRIPTION:
REPLACE/ RESTORE LINE 1619 UPSTREAM 23SW228 TO ORIGINAL FORM 2 2MS219 FAILURE DESCRIPTION:
VALVE LEAKS THRU, CUT OUT VALVE AND REPLACE 2 22 AUX FEED PUMP FAILURE DESCRIPTION:
EXCESSIVE LEAKAGE 2 21 SERVICE WATER PUMP FAILURE DESCRIPTION:
DECLARED INOPERABLE DUE TO LOW FLOW. 2 23SW2 FAILURE DESCRIPTION:
LEAKING PAST ITS SEAT, REMOVE EXISTING VALVE & REPLACE.
,.o SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880211069 2 21CV16 2 FAILURE DESCRIPTION:
LEAKING DIAPHRAM/REPLACE.
880216092 2 22 BAT PUMP FAILURE DESCRIPTION:
MECHANICAL SEAL LEAKING/REWORK FAILED MECHANICAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.
880307088 2 22SW133 FAILURE DESCRIPTION:
NO/FLOW/DISASSEMABLE
& INSPECT 880316078 2 2SJ300 FAILURE DESCRIPTION:
LEAK THROUGH/REMOVE INSULATION/FA-127.
PLANT MODIFICATIONS REPORT MONTH APRIL 1988 *OCR NO. 2SC-13 23 2SM-00188A PRINCIPAL SYSTEM Containment Spray Service Water
- Design Change Request DOCKET NO.: 50-311 UNIT NAME: Salem 2 DATE: May 10,1988 COMPLETED BY: J. Ronatalvy TELEPHONE:
609/339-4455 DESCRIPTION This modification installed drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing. This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve.
MAJOR PLANT MODIFIC,IONS REPORT MONTH -APRIL 1988 *DCR SAFETY EVALUATION 10 CFR 50.59 DOCJT NO: 50-272 UNIT NAME:
DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE:
(609)339-4455 2SC-1323 This design change did not increase the probability or consequences of an accident.
By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification.
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.
2SM-00188A This modification did not alter the original design of the system. The duo check valve is no longer manufactured by TRW but is now made by Clow. A review of the design specifications show that the new valve is identical in every way to the old one. This modification did not alter 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. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-UNIT NO. 2 APRIL 1988 The Unit began the period operating at 100% power and continued to operate at full power until April 21, 1988, when the Unit tripped due to a spike on a Reactor Coolant Pump flow transmitter during maintenance.
During startup, the Unit tripped due to a level spike on No. 23 Steam Generator caused by the EH Control System. Following repairs to the EH Control system, startup was commenced with the Unit achieving full power on April 24, 1988. The Unit continued to operate at full power for the remainder of the period. The primary to secondary leak rate calculation for Nos. 22 and 24 Steam Generators continues to indicate less than ten gallons per day.
REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: J. Ronafalvy DATE: Max 10, 1988 TELEPHONE:
609)935-6000 EXTENSION Month APRIL 1988 1. Refueling information has changed from last month: YES NO X 2. Scheduled date for next refueling:
September 3, 1988 3. Scheduled date for restart following refueling:
November 2,1988 4. A) Will Technical Specification changes or other license amendments be required?
YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X If no, when is it scheduled?
August, 1988 5. Scheduled date(s) for submitting proposed licensing action: August 1988 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 19 3 224 1170 1170 March 2003
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. 2 DOCKET NO. 50-311 May 14, 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 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 /,z,4. j.Y I, \* 95-2189 (11 M) 12-84