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| issue date = 09/30/1995
| issue date = 09/30/1995
| title = Monthly Operating Rept for Sept 1995 for Salem Unit 2.W/ 951011 Ltr
| title = Monthly Operating Rept for Sept 1995 for Salem Unit 2.W/ 951011 Ltr
| author name = HELLER R, PHILLIPS R, WARREN C
| author name = Heller R, Phillips R, Warren C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:I I e Pul:llic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 2 DOCKET NO: 50-311 October 11, 1995 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 September are being sent to you. *' RH:vls Enclosures C Mr. Thomas T. Martin Sincerely
{{#Wiki_filter:r.-:~                                  e PS~G I
: yours, General Manager -Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4 The power ic in uni 1r _ _ __ _ 9510190091 950930 PDR ADOCK 05000311 R PDR 95-2168 REV. 6/94   
I Pul:llic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit October 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 September are being sent to you.
.,
Sincerely yours,
DAILY UNIT POWER Docket No.: Unit Name: Date: Completed.by:
                                                        ~en~
Robert Phillips Telephone:
              *'                                       General Manager -
Month September 1995 50-311 Salem #2 10/10/95 339-2735 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 16 0 P. 8.1-7 Rl OPERATING DATA REPORT Docket No: 50-311 Date: 10/10/95 Complet:ed by: Robert Phillips Telephone:
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 The power ic in uni 1r l-i~nd!'; _ ____
339-2735 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period September 1995 3. Licensed Thermal Power (MWt) 3411 4**
9510190091 950930 PDR ADOCK 05000311                                                           95-2168 REV. 6/94 R                      PDR
* 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
 
: 9. Power Level to Which Restricted, if any (Net MWe) 10. Reasons for Restrictions, if any 11. 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 This Month 720 0 0 0 0 0 0 -4042 0 0 0 0 100 NA Year to Date 6551 2468.4 0 2261. 6 0 6807220.8 2198890 2029658 34.5 34.5 28.0 27.8 60.6 N/A Cumulative 122424 78083.6 0 75229.5 0 187781005 78648898 74753202 61.4 61.4 55.2 54.7 24.0 24. Shutdowns scheduled over next 6 months (type, date and duration of each) continuation of forced outage. 25. If shutdown at end of Report Period, Estimated Date of Startup: To be determined.
  .,                         A~GE  DAILY UNIT POWER LEVE~
8-1-7.R2 NO. DATE 2692 9-1-95 F 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH: SEPTEMBER 1995 DURATION TYPE 1 (HOURS) REASON 2 720 A Reason A-Equipment Failure (explain)
Docket No.:   50-311 Unit Name:     Salem #2 Date:         10/10/95 Completed.by:     Robert Phillips                   Telephone:     339-2735 Month     September   1995 Day Average Daily -Power Level               Day Average Daily Power Level (MWe-NET)                                 (MWe-NET) 1             0                             17           0 2             0                             18           0
B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR 4 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
: 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 16               0 P. 8.1-7 Rl
H-Other (Explain)
 
LICENSE EVENT SYSTEM REPORT # CODE 4 --------SH 3 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 a DOCKET NO.:
OPERATING DATA REPORT Docket No: 50-311 Date:       10/10/95 Complet:ed by:     Robert Phillips                   Telephone: 339-2735 Operating Status
UNIT NAME:
: 1. Unit Name                         Salem No. 2     Notes
DATE: 10-10-95 COMPLETED BY: Robert Phillips .TELEPHONE:
: 2. Reporting Period               September 1995
609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CKT BRK Breaker Failure 1-9 500KV 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit 1 -Same Source 10CFR50.59 EVALUATIONS MONTH: SEPTEMBER 1995 DOCKET NO: UNIT NAME: 50-311 SALEM2 10/10/95 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE:
: 3. Licensed Thermal Power (MWt)             3411 4**
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
* Nameplate Rating (Gross MWe)             1170
The Station Operations Review Committee has reviewed and concurs with these evaluations.
: 5. Design Electrical Rating (Net MWe)       1115
: 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.
: 6. Maximum Dependable capacity(Gross MWe) 1149
For the next several months, during this transition phase, we anticipate few new DCPs to report: 2. Procedures S2.MD-FR.230-0001 (Q) "2F-2H 230 Volt Bus Crossfeed," Rev. 0 -This procedure provides the instructions necessary to install temporary power cables between 2H 230 Volt group bus and 2F 230 Volt group bus during respective Station Power Transformer (SPT)outages or 4160-240/139V transformer outages. During 22SPT outage or 4160-240/139V Transformer 2XFR1F5DBY outage, breaker 2HY is closed and breaker 2FY is open, resulting in 2F 230 Volt bus being powered from 2H 230 Volt bus. During 21SPT outage or 4160-240/139V Transformer 2XFRIH5DBY outage, breaker 2FY is closed and breaker 2HY is open, resulting in 2H 230 Volt bus being powered from 2F 230 Volt bus. Busses 2H and 2F (230V AC group busses) are not covered by Technical Specifications.
: 7. Maximum Dependable Capacity (Net MWe) 1106
Neither the busses nor the equipment supplied by the busses affect the margin of safety as defined in the bases of the Technical Specifications. (SORC 95-100)
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason.~~~~~__,N~A=-~---'-~~~~~~~~~~~~~~~~~
REFUELING INFORMATION MONTH: SEPTEMBER 1995 MONTH: SEPTEMBER 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
: 9. Power Level to Which Restricted, if any (Net MWe)           N/A
50-311 SALEM2 10/10/95 R.HELLER 609-339-5162
: 10. Reasons for Restrictions, if any               NA This Month    Year to Date  Cumulative
: 1. Refueling information has changed from last month: YES __ NO _ _.X'""'---
: 11. Hours in Reporting Period             720          6551      122424
: 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)         -4042        2029658    74753202
: 19. Unit service Factor                     0            34.5        61.4
: 20. Unit Availability Factor               0            34.5        61.4
: 21. Unit Capacity Factor (using MDC Net)                   0            28.0        55.2
: 22. Unit Capacity Factor (using DER Net)                   0            27.8        54.7
: 23. Unit Forced Outage Rate                 100           60.6       24.0
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each) continuation of forced outage.
: 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: SEPTEMBER 1995                                                   DOCKET NO.:  -=-50~-,...=3'"-'1""'"1-=---
UNIT NAME:  -'-Sa~l-..oe=m~#2~*--
DATE:   10-10-95 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 a                  TO PREVENT RECURRENCE 2692      9-1-95    F          720            A              4              --------        SH        CKT BRK         Breaker Failure 1-9 500KV 1              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 (LER) 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)
 
10CFR50.59 EVALUATIONS                                 DOCKET NO:            50-311 MONTH: SEPTEMBER 1995                                   UNIT NAME:           SALEM2 DATE:          10/10/95 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:
: 2. Procedures S2.MD-FR.230-0001 (Q)         "2F-2H 230 Volt Bus Crossfeed," Rev. 0 - This procedure provides the instructions necessary to install temporary power cables between 2H 230 Volt group bus and 2F 230 Volt group bus during respective Station Power Transformer (SPT)outages or 4160-240/139V transformer outages. During 22SPT outage or 4160-240/139V Transformer 2XFR1F5DBY outage, breaker 2HY is closed and breaker 2FY is open, resulting in 2F 230 Volt bus being powered from 2H 230 Volt bus. During 21SPT outage or 4160-240/139V Transformer 2XFRIH5DBY outage, breaker 2FY is closed and breaker 2HY is open, resulting in 2H 230 Volt bus being powered from 2F 230 Volt bus.
Busses 2H and 2F (230V AC group busses) are not covered by Technical Specifications. Neither the busses nor the equipment supplied by the busses affect the margin of safety as defined in the bases of the Technical Specifications.
(SORC 95-100)
 
REFUELING INFORMATION                                 DOCKET NO:         50-311 MONTH: SEPTEMBER 1995                                 UNIT NAME:         SALEM2 DATE:     10/10/95 COMPLETED BY:          R.HELLER TELEPHONE:        609-339-5162 MONTH: SEPTEMBER 1995
: 1. Refueling information has changed from last month: YES_ _NO _ _.X'""'---
: 2. Scheduled date for next refueling: (to be determined)
: 2. Scheduled date for next refueling: (to be determined)
Scheduled date for restart following refueling:
Scheduled date for restart following refueling: 2nd quarter 1996
2nd quarter 1996 3. a. Will Technical Specification changes or other license amendments be required?
: 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 NOT DETERMINED TO DATE               X
YES NO X If no, when is it scheduled? (to be determined)
: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 5. Scheduled date( s) for submitting proposed licensing action: ___ __;:.N""""'/-"-'A=----
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 ofFuel Assemblies:
: 7. Number ofFuel Assemblies:
: a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:
: a. Incore                                                             _193 _ _
Future spent fuel storage capacity:
: b. In Spent Fuel Storage                                                   556
: 9. Date oflast 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 _193 __ 556 1632 1632 March 2012 SALEM GENERATING STATION MONTHLY OPERATING  
: 9. Date oflast 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 OCTOBER 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 OCTOBER 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}}
* After the restart review, meet with the NRC and communicate the results of that review}}

Latest revision as of 10:08, 21 October 2019

Monthly Operating Rept for Sept 1995 for Salem Unit 2.W/ 951011 Ltr
ML18101B050
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/30/1995
From: Heller R, Phillips R, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9510190091
Download: ML18101B050 (7)
v • d • e


Text

r.-:~ e PS~G I

I Pul:llic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit October 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 September are being sent to you.

Sincerely yours,

~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 The power ic in uni 1r l-i~nd!'; _ ____

9510190091 950930 PDR ADOCK 05000311 95-2168 REV. 6/94 R PDR

., A~GE DAILY UNIT POWER LEVE~

Docket No.: 50-311 Unit Name: Salem #2 Date: 10/10/95 Completed.by: Robert Phillips Telephone: 339-2735 Month September 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 16 0 P. 8.1-7 Rl

OPERATING DATA REPORT Docket No: 50-311 Date: 10/10/95 Complet:ed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period September 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.~~~~~__,N~A=-~---'-~~~~~~~~~~~~~~~~~
9. Power Level to Which Restricted, if any (Net MWe) N/A
10. Reasons for Restrictions, if any NA This Month Year to Date Cumulative
11. Hours in Reporting Period 720 6551 122424
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) -4042 2029658 74753202
19. Unit service Factor 0 34.5 61.4
20. Unit Availability Factor 0 34.5 61.4
21. Unit Capacity Factor (using MDC Net) 0 28.0 55.2
22. Unit Capacity Factor (using DER Net) 0 27.8 54.7
23. Unit Forced Outage Rate 100 60.6 24.0
24. Shutdowns scheduled over next 6 months (type, date and duration of each) continuation of forced outage.
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: SEPTEMBER 1995 DOCKET NO.: -=-50~-,...=3'"-'1""'"1-=---

UNIT NAME: -'-Sa~l-..oe=m~#2~*--

DATE: 10-10-95 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 a TO PREVENT RECURRENCE 2692 9-1-95 F 720 A 4 -------- SH CKT BRK Breaker Failure 1-9 500KV 1 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 (LER) 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)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: SEPTEMBER 1995 UNIT NAME: SALEM2 DATE: 10/10/95 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:

2. Procedures S2.MD-FR.230-0001 (Q) "2F-2H 230 Volt Bus Crossfeed," Rev. 0 - This procedure provides the instructions necessary to install temporary power cables between 2H 230 Volt group bus and 2F 230 Volt group bus during respective Station Power Transformer (SPT)outages or 4160-240/139V transformer outages. During 22SPT outage or 4160-240/139V Transformer 2XFR1F5DBY outage, breaker 2HY is closed and breaker 2FY is open, resulting in 2F 230 Volt bus being powered from 2H 230 Volt bus. During 21SPT outage or 4160-240/139V Transformer 2XFRIH5DBY outage, breaker 2FY is closed and breaker 2HY is open, resulting in 2H 230 Volt bus being powered from 2F 230 Volt bus.

Busses 2H and 2F (230V AC group busses) are not covered by Technical Specifications. Neither the busses nor the equipment supplied by the busses affect the margin of safety as defined in the bases of the Technical Specifications.

(SORC 95-100)

REFUELING INFORMATION DOCKET NO: 50-311 MONTH: SEPTEMBER 1995 UNIT NAME: SALEM2 DATE: 10/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH: SEPTEMBER 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 ofFuel Assemblies:
a. Incore _193 _ _
b. In Spent Fuel Storage 556
8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
9. Date oflast 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 OCTOBER 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
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