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Day Average Daily Power Level (MWe-NET) 1 847 17 1106 2 994 18 1120 3 1111 19 1124 4 1120 20 1118 5 1106 21 1116 6 1120 22 1134 7 1079 23 1102 8 938 24 1086 9 902 25 1126 10 1026 26 1123 11 824 27 1123 12 552 28 1124 13 520 29 1103 14 744 30. 1117 15 1098 31 1117 16 1122 P. 8.1-7 Rl | Day Average Daily Power Level (MWe-NET) 1 847 17 1106 2 994 18 1120 3 1111 19 1124 4 1120 20 1118 5 1106 21 1116 6 1120 22 1134 7 1079 23 1102 8 938 24 1086 9 902 25 1126 10 1026 26 1123 11 824 27 1123 12 552 28 1124 13 520 29 1103 14 744 30. 1117 15 1098 31 1117 16 1122 P. 8.1-7 Rl | ||
* > ' OPERATING DATA REPORT Docket No: 50-272 Date: 1/10/95 Completed by: Mike Morroni Telephope: | * > ' OPERATING DATA REPORT Docket No: 50-272 Date: 1/10/95 Completed by: Mike Morroni Telephope: | ||
339-5142 Operating status 1. Unit Name Salem No. 1 Notes 2. Reporting Period December 1994 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating {Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 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) NIA 10. Reasons for Restrictions, if any | 339-5142 Operating status 1. Unit Name Salem No. 1 Notes 2. Reporting Period December 1994 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating {Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 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) NIA 10. Reasons for Restrictions, if any | ||
: 12. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 744 0 744 0 2357760.0 797350 764414 100 100 92.9 92.1 0 Year to Date 8760 6587.6 0 5868.3 0 19279588.8 6075180 5744611 67.0 67.0 59.3 58.8 25.9 Cumulative 153457 101719.6 0 97756.2 0 310051902.8 102611150 97682164 63.7 63.7 57.6 57.1 21.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start 4-8-95 and last 60 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: N A. | : 12. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 744 0 744 0 2357760.0 797350 764414 100 100 92.9 92.1 0 Year to Date 8760 6587.6 0 5868.3 0 19279588.8 6075180 5744611 67.0 67.0 59.3 58.8 25.9 Cumulative 153457 101719.6 0 97756.2 0 310051902.8 102611150 97682164 63.7 63.7 57.6 57.1 21.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start 4-8-95 and last 60 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: N A. | ||
NO. DATE 2001 12-01-94 2022 12-09-94 2028 12-11-94 2058 12-14-94 2105 12-07-94 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 6.0 A F 9.6 A F 62.8 A F 16.6 A F 14.6 A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1994 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # 5 ---------HF 5 ---------IB 5 ---------HF 5 ---------HF 5 ---------HF --SYSTEM CODE 4 2 3 Reason A-Equipment Failure (explain) | NO. DATE 2001 12-01-94 2022 12-09-94 2028 12-11-94 2058 12-14-94 2105 12-07-94 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 6.0 A F 9.6 A F 62.8 A F 16.6 A F 14.6 A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1994 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # 5 ---------HF 5 ---------IB 5 ---------HF 5 ---------HF 5 ---------HF --SYSTEM CODE 4 2 3 Reason A-Equipment Failure (explain) | ||
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* 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1994 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/95 DATE: COMPLETED BY: TELEPHONE: | * 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1994 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/95 DATE: COMPLETED BY: TELEPHONE: | ||
R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. | R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. | ||
The Station Operations Review Committee has reviewed and concurs with these evaluations. | The Station Operations Review Committee has reviewed and concurs with these evaluations. | ||
: 1. Design Change Packages (DCP) lEC-3393, Pkg. 2 1 SC-2269, Pkg. 7 "Room Cooler Drain Piping" -The purpose of this DCP is to install drain piping on the Safety Injection Pump Room Cooler to prevent condensate drip on equipment. | : 1. Design Change Packages (DCP) lEC-3393, Pkg. 2 1 SC-2269, Pkg. 7 "Room Cooler Drain Piping" -The purpose of this DCP is to install drain piping on the Safety Injection Pump Room Cooler to prevent condensate drip on equipment. | ||
The room cooler condensate will be routed to the nearest floor drain. This piping does not perform any safety related function and is not important to safety. Drain systems within the Auxiliary Building are considered part of the contaminated system. However, the liquid normal handled by the room cooler condensate drain line is not considered to be contaminated. | The room cooler condensate will be routed to the nearest floor drain. This piping does not perform any safety related function and is not important to safety. Drain systems within the Auxiliary Building are considered part of the contaminated system. However, the liquid normal handled by the room cooler condensate drain line is not considered to be contaminated. | ||
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* REFl)ELING INFORMATION MONTH: DECEMBER 1994 MONTH : DECEMBER 1994 | * REFl)ELING INFORMATION MONTH: DECEMBER 1994 MONTH : DECEMBER 1994 | ||
* DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE: | * DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE: | ||
50-272 SALEM 1 01/10/95 R.HELLER 609-339-5162 | 50-272 SALEM 1 01/10/95 R.HELLER 609-339-5162 | ||
: 1. Refueling information has changed from last month: YES __ NO _A_ 2. Scheduled date for next refueling: | : 1. Refueling information has changed from last month: YES __ NO _A_ 2. Scheduled date for next refueling: | ||
April 8. 1995 3. -Scheduled date for restart following refueling: | April 8. 1995 3. -Scheduled date for restart following refueling: | ||
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YES NO_L Ifno, when is it scheduled? | YES NO_L Ifno, when is it scheduled? | ||
March 1995 5. Scheduled date(s) for submitting proposed licensing action: ___ __;:N'-'-'-/-=A= | March 1995 5. Scheduled date(s) for submitting proposed licensing action: ___ __;:N'-'-'-/-=A= | ||
___ _ 6. Important licensing considerations associated with refueling: | ___ _ 6. Important licensing considerations associated with refueling: | ||
: 7. Number ofFuel Assemblies: | : 7. Number ofFuel Assemblies: | ||
: a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity: | : a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity: | ||
Future spent fuel storage capacity: | Future spent fuel storage capacity: | ||
: 9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: | : 9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: | ||
8-l-7.R4 193 732 _1632_ 1632 September 2008 | 8-l-7.R4 193 732 _1632_ 1632 September 2008 |
Revision as of 15:23, 25 April 2019
ML18101A467 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 12/31/1994 |
From: | HELLER R, SUMMERS J C Public Service Enterprise Group |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9501230289 | |
Download: ML18101A467 (8) | |
Text
. e ,.0 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit January 13, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 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 December are being sent to you. The following sections are included:
RH:vls Enclosures Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions 10CFR50.59 Evaluations Operating Summary Refueling Information John C. Summers General Manager -Salem Operations C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue -King of Prussia, PA 19046 8-1-7.R4 ,---.,--------------
--
9501230289 941231 I _ PDR ADOCK 05000272 ,.R _ -_ .. _ _ -PDR. The power is in your handS:-' -4 " **
I REV. 6/94
\-' .ERAGE DAILY UNIT POWER LE41l !JI Docket No.: Unit Name: Date: Completed by: Mike Morroni Telephone:
Month December 1994 50-272 Salem #1 1/10/95 339-5142 Day Average Daily Power Level (MWe-NET)
Day Average Daily Power Level (MWe-NET) 1 847 17 1106 2 994 18 1120 3 1111 19 1124 4 1120 20 1118 5 1106 21 1116 6 1120 22 1134 7 1079 23 1102 8 938 24 1086 9 902 25 1126 10 1026 26 1123 11 824 27 1123 12 552 28 1124 13 520 29 1103 14 744 30. 1117 15 1098 31 1117 16 1122 P. 8.1-7 Rl
- > ' OPERATING DATA REPORT Docket No: 50-272 Date: 1/10/95 Completed by: Mike Morroni Telephope:
339-5142 Operating status 1. Unit Name Salem No. 1 Notes 2. Reporting Period December 1994 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating {Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 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) NIA 10. Reasons for Restrictions, if any
- 12. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 744 0 744 0 2357760.0 797350 764414 100 100 92.9 92.1 0 Year to Date 8760 6587.6 0 5868.3 0 19279588.8 6075180 5744611 67.0 67.0 59.3 58.8 25.9 Cumulative 153457 101719.6 0 97756.2 0 310051902.8 102611150 97682164 63.7 63.7 57.6 57.1 21.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling outage scheduled to start 4-8-95 and last 60 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: N A.
NO. DATE 2001 12-01-94 2022 12-09-94 2028 12-11-94 2058 12-14-94 2105 12-07-94 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 6.0 A F 9.6 A F 62.8 A F 16.6 A F 14.6 A UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1994 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # 5 ---------HF 5 ---------IB 5 ---------HF 5 ---------HF 5 ---------HF --SYSTEM CODE 4 2 3 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 FILTER INSTRU PUMP XX PUMPXX FILTER 4 CIRC. DOCKET NO.
UN IT NAME:
DA TE: --'1"""-""""10=---"-9=-5 COMPLETED BY: Mike Morroni TELEPHONE:
... 3=3-.9_.-5..-1--4 ... 2 __ _ CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE WATER TRASH RAKE 1A & 1B S.E.C. INOPERABLE CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS CIRCULATING WATER TRASH RAKE 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 -Same Source CNUREG-0161)
-.
- 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1994 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/95 DATE: COMPLETED BY: TELEPHONE:
R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed and concurs with these evaluations.
- 1. Design Change Packages (DCP) lEC-3393, Pkg. 2 1 SC-2269, Pkg. 7 "Room Cooler Drain Piping" -The purpose of this DCP is to install drain piping on the Safety Injection Pump Room Cooler to prevent condensate drip on equipment.
The room cooler condensate will be routed to the nearest floor drain. This piping does not perform any safety related function and is not important to safety. Drain systems within the Auxiliary Building are considered part of the contaminated system. However, the liquid normal handled by the room cooler condensate drain line is not considered to be contaminated.
The proposed modification does not alter the design criteria, modes of operation, or function for which the contaminated drain system*is currently analyzed.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-094) "Circ. Water Slow Bus Transfer" -The purpose of this DCP is to provide the final connections between the two (2) new offsite power sources between the offsite transmission network and the Salem Unit #2 class IE distribution system (Vital buses 2A, 2B & 2C) and Unit #2 new CW* switchgear.
The modifications will improve the voltage profile on the vital and group busses. This has resulted in a change of the trip setpoint for the second level of undervoltage protection on the vital busses. This will increase the margin of safety between the setpoint value and the minimum allowable value and ensure safe operation of the vital equipment. (SORC 94-096)
- IOCER.50.59 EVALUATIONS MONTH: DECEMBER I994 DOCKET NO: UNIT NAME: 50-272 SALEM I Ol/I0/95 (Cont'd) IEA-1076, Pkg. I DATE: COMPLETED BY: TELEPHONE:
R. HELLER 609-339-5I62 "Resolution of DEF DES-90-0I 104" -The resolution of DEF DES-90-0I 104, requires that the fire rating of Fire areas IFA-AB-64A-I (I25VDC Battery Room IC Elevation 64') and 2FA-AB-64A-I (I25VDC Battery Room IC Elevation 64') ceilings be changed from 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This DCP will affect the Salem Fire Protection Report -General and Boundary Evaluation as well as drawing 601608. There is no expected effect due to the fact that the calculated equivalent fire severity in the fire hazard analysis is 43. 7 minutes. The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating is higher than the expected duration of the fire. Therefore, there is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 94-097)
- REFl)ELING INFORMATION MONTH: DECEMBER 1994 MONTH : DECEMBER 1994
- DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
50-272 SALEM 1 01/10/95 R.HELLER 609-339-5162
- 1. Refueling information has changed from last month: YES __ NO _A_ 2. Scheduled date for next refueling:
April 8. 1995 3. -Scheduled date for restart following refueling:
June 6. 1995 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_L Ifno, when is it scheduled?
March 1995 5. Scheduled date(s) for submitting proposed licensing action: ___ __;:N'-'-'-/-=A=
___ _ 6. Important licensing considerations associated with refueling:
- 7. Number ofFuel Assemblies:
- a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
- 9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
8-l-7.R4 193 732 _1632_ 1632 September 2008
- SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-UNIT 1 DECEMBER 1994 SALEM UNIT NO. 1 The Unit began the period in a power escalation following the return of#2 station power transformer to service. A brief load reduction occurred on December 1, 1994, due to the circulating water trash rake jamming. The rake was freed and the power escalation continued.
The Unit achieved 100% power on December 2, 1994, and continued to operate at full power until December 7, 1994, when load was reduced due to 13A & 13B circulators being taken out of service to free the trash rake. The Unit was restored to full power on December 8, 1994. On December 9, 1994, a Unit shutdown was initiated due to IA & lB SECs being declared inoperable.
Later, the SECs were declared operable and the Unit returned to full power on December 10, 1994. Excessive grass conditions recurred on December 11, 1994, and power was reduced to 58%. The Unit continued to operate at reduced power until December 14, 1994, when the grass conditions were cleared and a power es9alation commenced.
The Unit achieved 100% power on December 15, 1994, and continued to operate at full power throughout the remainder of the period.