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* AVERAGE DAILY UNIT POWER LEVEL | * AVERAGE DAILY UNIT POWER LEVEL Docket No. | ||
Unit Name 50-27 2 | |||
-saieffi#-1-*----- | |||
11 10 83 | Date *s - 4:. 8a Completed by Pell White Telephone 6cr9::93-5___ 6_0_oo-* | ||
13 1108 | Extension 4451 Month JULY 1988 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1095 17 1074 2 1102 18 1087 3 1099 19 1060 4 1098 20 1071 5 1090 21 1080 6 1113 22 1082 7 10 82 | ||
-----*-~* | |||
- | 23 1074 8 - - 1100 24 1086 9 1084 25 1080 10 1090 26 1090 11 10 83 27 | ||
- * - 1044 12 1083 28 1088 13 1108 29 1066 14 1077 30 1051 15 10 61 31 1067 16 1097 P. 8.1-7 Rl | |||
. | * OPERATING DATA REPORT | ||
* Docket No .50-272 Date: 8--~4--~8~8...---~~~- | |||
Telephone: 935-6000 Completed by Pell White Extension: ~4~4~5~1,..--~~~~~~ | |||
Operating Status | |||
: 1. Unit Name Salem No. 1 Notes | |||
: 2. Reporting Period July 1988 | |||
: | : 3. Licensed Thermal Power (MWt) 3411 | ||
: 15. Unit Reserve Shutdown Hours 0 16. Gross Thermal Energy Generated | : 4. Nameplate Rating (Gross MWe) 1170 | ||
------(MWH) 2541662.4 | : 5. Design Electrical Rating (Net MWe) 1115 | ||
: 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 | |||
----~~~-~~-~ | |||
: 10. Reasons for Restrictions, if any N/A | |||
~~~~~~--~~~-~~~-~~-~~ | |||
This Month Year to Date Cumulative | |||
: 11. Hours in Reporting Period 744 5111 97200 | |||
: 12. No. of Hrs. Reactor was Critical 744 3423.3 6112735 | |||
: 13. Reactor Reserve Shutdown Hrs. 0 0 0 | |||
: 14. Hours Generator On-Line ~--=7~4~4,,_--- 33 49. 2 59140.9 | |||
1 | : 15. Unit Reserve Shutdown Hours 0 0 0 | ||
: 16. Gross Thermal Energy Generated ------ | |||
(MWH) 2541662.4 11292842.8 18 3561851. 6 | |||
: 17. Gross Elec. Energy Generated (MWH) 839880 3778840 60973330 | |||
1 | : 18. Net Elec. Energy Generated (MWH) 805491 3601183 57997392 | ||
: 19. Unit Service Factor 100 65.6 60.8 2 0. Unit Availability Factor 100 65.6 60.8 | |||
: 21. Unit Capacity Factor (using MDC Net) 97.9 63.7 53.9 | |||
: 22. Unit Capacity Factor (using DER Net) 97 .1 63.2 53.5 2 3. Unit Forced Outage Rate 0 1.1 23 *. 2 | |||
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each) | |||
N/A | |||
1 | : 25. If shutdown at end of Report Period, Estimated Date of Startup: | ||
N/A 8-l-7.R2 | |||
UNIT SHUTDOWN AND POWER REDUCTIONS D o c ke t No . 5 0 - 2 7 2 | |||
~~~~~~~~~ | |||
REPORT MONTH JULY 1988 Unit Name Salem No.1 Date August 4, 1988 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 Reactor Report Code 4 Code 5 Prevent Recurrence N/A 1 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 G-Operational Error-explain H-Other-explain 5-Load Reduction 9-0ther Event Report (LER) File (NUREG 0161) | |||
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO ~~~-U_N_I_T~-E~QUIPMENT IDENTIFICATION 870401046 1 lA SWG 97 FAILURE DESCRIPTION: NOT ATTACHED TO PIPE PLEASE REPAIR. | |||
DA TE : -- | 870602041 1 11 S.W.P. | ||
609/339-4455 DESCRIPTION This modification added five high range main steam line monitors. | FAILURE DESCRIPTION: HANGER MISSING. REPLACE HANGER. | ||
The monitors are qualified for post-accident operation. | 870708038 1 12CCHX FAILURE DESCRIPTION: HAS NO FLOW IN AUTO/CORRECT. HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT. | ||
This modification installed a "cross type" vortex breaker beneath the bellmouth of No. 16 Service Water Pump to inhibit cavitation. | 880120046 1 13SW24 880208141 1 | ||
This modification replaced the instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident. | FAILURE DESCRIPTION: | ||
1S27C DAMAGE VALVE BODY/REPLACE/MK. NO. M-114 FAILURE DESCRIPTION: HOLE IN PIPE BEFORE 15SW274/REPAIR. | |||
* | |||
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880428101 1 11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: INOPERABLE/REPLACE. | |||
880526040 1 lB DIESEL FAILURE DESCRIPTION: LINE TO TURBO./LEAK/REWORK. THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO. | |||
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 - | 880613104 1 1ABV15 FAILURE DESCRIPTION: SUPPLY REG/BLOWING AIR/REPLACE. | ||
The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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. | 880620078 1 lRlB FAILURE DESCRIPTION: MONITOR IN WARN/INVESTIGATE AND REPAIR. | ||
The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed. | 880705143 | ||
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. | * 1 1CC71 FAILURE DESCRIPTION: LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT. | ||
This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients. | |||
This modification did not alter any plant process or discharge or affect the | SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION | ||
-------~ | |||
880718085 1 lC D-G FAILURE DESCRIPTION: TURBO AIR COMP/NOT STARTING/TROUBLESHOOT. | |||
880718121 1 1R41A FAILURE DESCRIPTION: PLNT VNT PART RAD MONITOR IS FAILED. | |||
TROUBLESHOOT/REWORK. | |||
880727080 1 14 LOOP FAILURE DESCRIPTION: 14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH. | |||
900714001 1 12 S.W. PUMP FAILURE DESCRIPTION: INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP. | |||
MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH JULY 1988 UNIT NAME: -S-a~l-e-m--1------ | |||
DA TE : --AU9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455 | |||
*OCR NO. PRINCIPAL SYSTEM DESCRIPTION lEC-1181 Radiation This modification added five Monitoring high range main steam line monitors. The monitors are qualified for post-accident operation. | |||
lEC-2188 Service Water This modification installed a "cross type" vortex breaker beneath the bellmouth of No. | |||
16 Service Water Pump to inhibit cavitation. | |||
lSM-0091 PASS Air This modification replaced the Regulator instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident. | |||
lSM-0472 Component Cooling This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump. | |||
* DCR - Design Change Request | |||
MAJOR PLANT MODIFICATIONS DOCKET NO. 50-272 REPORT MONTH JULY 1988 UNIT NAME: Sa~l-e_m__,1=-------- | |||
DATE: August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455 | |||
*DCR | |||
- - - -SAFETY | |||
- - - EVALUATION 10 CFR 50.59 lEC-1181 This modification added monitors to detect any possible activity in the Main Steam lines. 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. | |||
lEC-2188 The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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. | |||
lSM-0091 The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed. 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. | |||
lSM-0472 This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients. 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 GENERATING STATION MONTHLY OPERATING | |||
==SUMMARY== | ==SUMMARY== | ||
-UNIT NO. 1 JULY 1988 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation. | - UNIT NO. 1 JULY 1988 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation. | ||
REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: August 10, 19 88 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month JULY 1988 | |||
: 1. Refueling information has changed from last month: | |||
August 10, 19 88 609/935-6000 4497 Month JULY 1988 1. Refueling information has changed from last month: YES NO X | YES NO X | ||
April 15, 1989 3. Scheduled date for restart following refueling: | : 2. Scheduled date for next refueling: April 15, 1989 | ||
May 30, 1989 4. A) | : 3. Scheduled date for restart following refueling: May 30, 1989 | ||
YES NO ----NOT DETERMINED TO DATE X Has the reload fuel design been reviewed by the Station Operating Review Committee? | : 4. A) Will Technical Specification changes or other license amendments be required? | ||
YES NO X If no, when is it scheduled? | YES --~ | ||
February 1989 5. Scheduled date(s) for submitting proposed licensing action: | NO - - - - | ||
if required 6. Important licensing considerations associated with refueling: | NOT DETERMINED TO DATE X B) Has the reload fuel design been reviewed by the Station Operating Review Committee? | ||
NONE 7. Number of Fuel Assemblies: | YES NO X If no, when is it scheduled? February 1989 | ||
A) Inc ore B) In Spent Fuel Storage 8. Present licensed spent fuel storage capacity: | : 5. Scheduled date(s) for submitting proposed licensing action: | ||
Future spent fuel storage capacity: | -~-February if required | ||
: 9. Date of last refueling that can be discharged to spent fuel pool assuming the present | : 6. Important licensing considerations associated with refueling: | ||
_September 2001 8-l-7.R4 | NONE | ||
-1. | : 7. Number of Fuel Assemblies: | ||
A) Inc ore 19 3 B) In Spent Fuel Storage 464 | |||
: 8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170 | |||
: 9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: _September 2001 8-l-7.R4 | |||
-1. | |||
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | |||
==Dear Sir:== | ==Dear Sir:== | ||
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 | |||
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 July 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. Pii::-1: 9. | |||
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}} |
Latest revision as of 07:33, 3 February 2020
ML18093B028 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 07/31/1988 |
From: | Ronafalvy J, White P, Zupko J Public Service Enterprise Group |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
NUDOCS 8808220217 | |
Download: ML18093B028 (11) | |
Text
- AVERAGE DAILY UNIT POWER LEVEL Docket No.
Unit Name 50-27 2
-saieffi#-1-*-----
Date *s - 4:. 8a Completed by Pell White Telephone 6cr9::93-5___ 6_0_oo-*
Extension 4451 Month JULY 1988 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1095 17 1074 2 1102 18 1087 3 1099 19 1060 4 1098 20 1071 5 1090 21 1080 6 1113 22 1082 7 10 82
*-~*
23 1074 8 - - 1100 24 1086 9 1084 25 1080 10 1090 26 1090 11 10 83 27
- * - 1044 12 1083 28 1088 13 1108 29 1066 14 1077 30 1051 15 10 61 31 1067 16 1097 P. 8.1-7 Rl
- OPERATING DATA REPORT
- Docket No .50-272 Date: 8--~4--~8~8...---~~~-
Telephone: 935-6000 Completed by Pell White Extension: ~4~4~5~1,..--~~~~~~
Operating Status
- 1. Unit Name Salem No. 1 Notes
- 2. Reporting Period July 1988
- 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)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
~~~-~~-~
- 10. Reasons for Restrictions, if any N/A
~~~~~~--~~~-~~~-~~-~~
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 5111 97200
- 12. No. of Hrs. Reactor was Critical 744 3423.3 6112735
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line ~--=7~4~4,,_--- 33 49. 2 59140.9
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated ------
(MWH) 2541662.4 11292842.8 18 3561851. 6
- 17. Gross Elec. Energy Generated (MWH) 839880 3778840 60973330
- 18. Net Elec. Energy Generated (MWH) 805491 3601183 57997392
- 19. Unit Service Factor 100 65.6 60.8 2 0. Unit Availability Factor 100 65.6 60.8
- 21. Unit Capacity Factor (using MDC Net) 97.9 63.7 53.9
- 22. Unit Capacity Factor (using DER Net) 97 .1 63.2 53.5 2 3. Unit Forced Outage Rate 0 1.1 23 *. 2
- 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-l-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS D o c ke t No . 5 0 - 2 7 2
~~~~~~~~~
REPORT MONTH JULY 1988 Unit Name Salem No.1 Date August 4, 1988 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 Reactor Report Code 4 Code 5 Prevent Recurrence N/A 1 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 G-Operational Error-explain H-Other-explain 5-Load Reduction 9-0ther Event Report (LER) File (NUREG 0161)
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO ~~~-U_N_I_T~-E~QUIPMENT IDENTIFICATION 870401046 1 lA SWG 97 FAILURE DESCRIPTION: NOT ATTACHED TO PIPE PLEASE REPAIR.
870602041 1 11 S.W.P.
FAILURE DESCRIPTION: HANGER MISSING. REPLACE HANGER.
870708038 1 12CCHX FAILURE DESCRIPTION: HAS NO FLOW IN AUTO/CORRECT. HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT.
880120046 1 13SW24 880208141 1
FAILURE DESCRIPTION:
1S27C DAMAGE VALVE BODY/REPLACE/MK. NO. M-114 FAILURE DESCRIPTION: HOLE IN PIPE BEFORE 15SW274/REPAIR.
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880428101 1 11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: INOPERABLE/REPLACE.
880526040 1 lB DIESEL FAILURE DESCRIPTION: LINE TO TURBO./LEAK/REWORK. THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO.
880613104 1 1ABV15 FAILURE DESCRIPTION: SUPPLY REG/BLOWING AIR/REPLACE.
880620078 1 lRlB FAILURE DESCRIPTION: MONITOR IN WARN/INVESTIGATE AND REPAIR.
880705143
- 1 1CC71 FAILURE DESCRIPTION: LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT.
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION
~
880718085 1 lC D-G FAILURE DESCRIPTION: TURBO AIR COMP/NOT STARTING/TROUBLESHOOT.
880718121 1 1R41A FAILURE DESCRIPTION: PLNT VNT PART RAD MONITOR IS FAILED.
TROUBLESHOOT/REWORK.
880727080 1 14 LOOP FAILURE DESCRIPTION: 14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH.
900714001 1 12 S.W. PUMP FAILURE DESCRIPTION: INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP.
MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH JULY 1988 UNIT NAME: -S-a~l-e-m--1------
DA TE : --AU9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455
- OCR NO. PRINCIPAL SYSTEM DESCRIPTION lEC-1181 Radiation This modification added five Monitoring high range main steam line monitors. The monitors are qualified for post-accident operation.
lEC-2188 Service Water This modification installed a "cross type" vortex breaker beneath the bellmouth of No.
16 Service Water Pump to inhibit cavitation.
lSM-0091 PASS Air This modification replaced the Regulator instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident.
lSM-0472 Component Cooling This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump.
- DCR - Design Change Request
MAJOR PLANT MODIFICATIONS DOCKET NO. 50-272 REPORT MONTH JULY 1988 UNIT NAME: Sa~l-e_m__,1=--------
DATE: August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455
- DCR
- - - -SAFETY
- - - EVALUATION 10 CFR 50.59 lEC-1181 This modification added monitors to detect any possible activity in the Main Steam lines. 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.
lEC-2188 The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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.
lSM-0091 The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed. 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.
lSM-0472 This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients. 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 GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 JULY 1988 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation.
REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: August 10, 19 88 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month JULY 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) 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 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:
NONE
- 7. Number of Fuel Assemblies:
A) Inc ore 19 3 B) In Spent Fuel Storage 464
- 8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
- 9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: _September 2001 8-l-7.R4
-1.
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1988 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 July 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. Pii::-1: 9.
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