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* Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 | Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit September 11, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | ||
* Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 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 August are being sent to you. | |||
*--__ | Sincerely yi! | ||
~en~ | |||
General Manager - | |||
Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4 | |||
-~, | |||
9509190121 950911 PDR ADOCK 05000311 | |||
_R._.. ___ ......... *-- __ *--**--~--****--*---PPB . | |||
The power is in your hands. | |||
95-2168 REV. 6/94 | |||
_ __j | |||
DAILY UNIT POWER Docket No.: 50-311 Unit Name: Salem #2 Date: 09/11/95 | ~ERAGE DAILY UNIT POWER LE~ | ||
* | Docket No.: 50-311 Unit Name: Salem #2 Date: 09/11/95 Completed* by: Robert Phillips Telephone: 339-2735 Month August 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl | ||
339-2735 Month August 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl OPERATING DATA REPORT Docket No: | |||
Operating Status L Unit Name Salem No. 2 Notes 2 . Reporting Period August, 1995 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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictions, if any ii. 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) 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 | ~ OPERATING DATA REPORT ~ | ||
: 25. If shutdown at end of Report Period, Estimated Date of Startup: To be determined. | Docket No: 50-311 Completed by: Robert Phillips Date: | ||
8-1-7.R2 | Telephone: | ||
09/11/95 339-2735 Operating Status L Unit Name Salem No. 2 Notes | |||
: 2. Reporting Period August, 1995 | |||
: 3. Licensed Thermal Power (MWt) 3411 | |||
: 4. Nameplate Rating (Gross MWe) 1170 | |||
609-339-2735 . CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CKTBRK BREAKER FAILURE 1-9 500KV 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 | : 5. Design Electrical Rating (Net MWe) 1115 | ||
: 6. Maximum Dependable Capacity(Gross MWe) 1149 | |||
: 7. Maximum Dependable Capacity (Net MWe) 1106 | |||
The Station Operations Review Committee has reviewed and concurs with these evaluations. | : 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA | ||
: 1. Design Change Packages (DCP) The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. | : 9. Power Level to Which Restricted, if any (Net MWe) N/A | ||
For the next several months, during this transition phase, we anticipate few new DCPs to report. 2EC-3372, Pkg. 1 "Enhance 2 RMS Computer Alarm Reliability" Rev. 0 -The purpose of this design change is to implement corrections to the Interdata 7/32 assembly language software used to drive the annunciator. | : 10. Reasons for Restrictions, if any N A This Month Year to Date Cumulative ii. Hours in Reporting Period 744 5831 121704 | ||
Changes are to assure messages defining changes in RMS status will be provided to the Met Package, driving the RIS reflash relays, providing inputs to the 2RP 1 RMS annunciator, and thus to the A6 window on the overhead annunciator. | : 12. No. of Hrs. Rx. was Critical 0 2468.4 78083.6 | ||
The RMS computers have no effect on any physical parameters relating to the fission product barriers. | : 13. Reactor Reserve Shutdown Hrs. 0 0 0 | ||
There is no reduction in the margin of safety relating to any fuel cladding, RCS boundary pressures or stresses, or containment pressure boundary. (SORC 95-082) | : 14. Hours Generator On-Line 0 2261.6 75229.5 | ||
: 15. Unit Reserve Shutdown Hours 0 0 0 | |||
50-311 SALEM2 09/10/95 R.HELLER 609-339-5162 | : 16. Gross Thermal Energy Generated (MWH) 0 6807220.8 187781005 Gross Elec. Energy Generated (MWH) 0 2198890 78648898 | ||
: 1. Refueling information has changed from last month: YES | : 18. Net Elec. Energy Gen. (MWH) -7400 2033700 74757244 | ||
Scheduled date for restart following refueling: | : 19. Unit Service Factor 0 38.8 61. 8 | ||
2nd quarter 1996 3. a. Will Technical Specification changes or other license amendments be required? | : 20. Unit Availability Factor 0 38.8 61. 8 | ||
YES_ NO NOT DETERMINED TO DATE X b. Has the reload fuel design been reviewed by the Station Operating Review Committee? | : 21. Unit Capacity Factor (using MDC Net) 0 31. 5 55.5 | ||
YES NO X If no, when is it scheduled? (to be determined) | : 22. Unit Capacity Factor (using DER Net) 0 31. 3 55.1 | ||
: 5. Scheduled date(s) for submitting proposed licensing action: | : 23. Unit Forced Outage Rate 100 54.9 23.4 | ||
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each) | |||
To be determined. | |||
: 25. If shutdown at end of Report Period, Estimated Date of Startup: | |||
To be determined. | |||
8-1-7.R2 | |||
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1995 DOCKET NO.: _,5""'0'""'--=3_,_1..:. .1~-- | |||
UNIT NAME: Salem #2 DATE: 9-10-95 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF . | |||
SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 2692 8-1-95 F 744 A 4 SH CKTBRK BREAKER FAILURE 1-9 500KV 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual *Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161) | |||
E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain) | |||
10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1995 UNIT NAME: SALEM2 DATE: 09/10/95 COMPLETED BY: R. HELLER TELEPHONE: 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) | |||
The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report. | |||
2EC-3372, Pkg. 1 "Enhance 2 RMS Computer Alarm Reliability" Rev. 0 - The purpose of this design change is to implement corrections to the Interdata 7/32 assembly language software used to drive the annunciator. Changes are to assure messages defining changes in RMS status will be provided to the Met Package, driving the RIS reflash relays, providing inputs to the 2RP 1 RMS annunciator, and thus to the A6 window on the overhead annunciator. The RMS computers have no effect on any physical parameters relating to the fission product barriers. There is no reduction in the margin of safety relating to any fuel cladding, RCS boundary pressures or stresses, or containment pressure boundary. | |||
(SORC 95-082) | |||
REFUELING INFORMATION MONTH: AUGUST 1995 DOCKET NO: | |||
UNIT NAME: | |||
50-311 SALEM2 DATE: 09/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH: AUGUST 1995 | |||
: 1. Refueling information has changed from last month: YES ____NO __X~~ | |||
: 2. Scheduled date for next refueling: (to be determined) | |||
Scheduled date for restart following refueling: 2nd quarter 1996 | |||
: 3. 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? (to be determined) | |||
: 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 of Fuel Assemblies: | : 7. Number of Fuel Assemblies: | ||
: a. lncore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity: | : a. lncore _193_ | ||
Future spent fuel storage capacity: | : b. In Spent Fuel Storage 556 | ||
: 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: | : 8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632 | ||
8-1-7.R4 | : 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4 | ||
SALEM GENERATING STATION MONTHLY OPERATING | |||
==SUMMARY== | ==SUMMARY== | ||
-UNIT 2 AUGUST 1995 SALEM UNIT NO. 2 The Unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units will remain shutdown pending completion of the following actions: | - UNIT 2 AUGUST 1995 SALEM UNIT NO. 2 The Unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units will remain shutdown pending completion of the following actions: | ||
* Appropriately address long standing equipment reliability and operability issues | * Appropriately address long standing equipment reliability and operability issues | ||
* After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner | * After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner | ||
* After the restart review, meet with the NRC and communicate the results of that review I I J}} | * After the restart review, meet with the NRC and communicate the results of that review I | ||
I J}} |
Latest revision as of 05:40, 3 February 2020
ML18101B002 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 08/31/1995 |
From: | Warren C Public Service Enterprise Group |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9509190121 | |
Download: ML18101B002 (7) | |
Text
,-
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit September 11, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
- Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 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 August are being sent to you.
Sincerely yi!
~en~
General Manager -
Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4
-~,
9509190121 950911 PDR ADOCK 05000311
_R._.. ___ ......... *-- __ *--**--~--****--*---PPB .
The power is in your hands.
95-2168 REV. 6/94
_ __j
~ERAGE DAILY UNIT POWER LE~
Docket No.: 50-311 Unit Name: Salem #2 Date: 09/11/95 Completed* by: Robert Phillips Telephone: 339-2735 Month August 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl
~ OPERATING DATA REPORT ~
Docket No: 50-311 Completed by: Robert Phillips Date:
Telephone:
09/11/95 339-2735 Operating Status L Unit Name Salem No. 2 Notes
- 2. Reporting Period August, 1995
- 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 NA
- 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 ii. Hours in Reporting Period 744 5831 121704
- 12. No. of Hrs. Rx. was Critical 0 2468.4 78083.6
- 13. Reactor Reserve Shutdown Hrs. 0 0 0
- 14. Hours Generator On-Line 0 2261.6 75229.5
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 0 6807220.8 187781005 Gross Elec. Energy Generated (MWH) 0 2198890 78648898
- 18. Net Elec. Energy Gen. (MWH) -7400 2033700 74757244
- 19. Unit Service Factor 0 38.8 61. 8
- 20. Unit Availability Factor 0 38.8 61. 8
- 21. Unit Capacity Factor (using MDC Net) 0 31. 5 55.5
- 22. Unit Capacity Factor (using DER Net) 0 31. 3 55.1
- 23. Unit Forced Outage Rate 100 54.9 23.4
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
To be determined.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
To be determined.
8-1-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1995 DOCKET NO.: _,5""'0'""'--=3_,_1..:. .1~--
UNIT NAME: Salem #2 DATE: 9-10-95 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF .
SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 2692 8-1-95 F 744 A 4 SH CKTBRK BREAKER FAILURE 1-9 500KV 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual *Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)
E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)
10CFRS0.59 EVALUATIONS DOCKET NO: 50-311 MONTH: AUGUST 1995 UNIT NAME: SALEM2 DATE: 09/10/95 COMPLETED BY: R. HELLER TELEPHONE: 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)
The reporting ofDCP related 10CFR50.59 evaluations is being modified to address these items only after they have been implemented and turned over to Operations. For the next several months, during this transition phase, we anticipate few new DCPs to report.
2EC-3372, Pkg. 1 "Enhance 2 RMS Computer Alarm Reliability" Rev. 0 - The purpose of this design change is to implement corrections to the Interdata 7/32 assembly language software used to drive the annunciator. Changes are to assure messages defining changes in RMS status will be provided to the Met Package, driving the RIS reflash relays, providing inputs to the 2RP 1 RMS annunciator, and thus to the A6 window on the overhead annunciator. The RMS computers have no effect on any physical parameters relating to the fission product barriers. There is no reduction in the margin of safety relating to any fuel cladding, RCS boundary pressures or stresses, or containment pressure boundary.
(SORC 95-082)
REFUELING INFORMATION MONTH: AUGUST 1995 DOCKET NO:
UNIT NAME:
50-311 SALEM2 DATE: 09/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH: AUGUST 1995
- 1. Refueling information has changed from last month: YES ____NO __X~~
- 2. Scheduled date for next refueling: (to be determined)
Scheduled date for restart following refueling: 2nd quarter 1996
- 3. 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? (to be determined)
- 5. Scheduled date(s) for submitting proposed licensing action: ---~N'-"/~A=----
- 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
- a. lncore _193_
- b. In Spent Fuel Storage 556
- 8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
- 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT 2 AUGUST 1995 SALEM UNIT NO. 2 The Unit remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, both Units will remain shutdown pending completion of the following actions:
- Appropriately address long standing equipment reliability and operability issues
- After the work is completed, conduct a restart readiness review to determine for ourselves the ability of each Unit to operate in a safe, event free manner
- After the restart review, meet with the NRC and communicate the results of that review I
I J