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| issue date = 02/29/1996
| issue date = 02/29/1996
| title = Monthly Operating Rept for Feb 1996 for Salem Generating Station Unit 2.W/960315 Ltr
| title = Monthly Operating Rept for Feb 1996 for Salem Generating Station Unit 2.W/960315 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:-
{{#Wiki_filter:PS~G              -
Public 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 March 15, 1996 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating report for the month of February is being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin General Manager -Salem Operations Regional Administrator USNRC, Region I ' 631 Park Avenue King of Prussia, PA 19046 ---96o3i 90344-960229 PDR ADOCK 05000311 R PDR The power is in your hands. ---------.._, 95-2168 REV. 6/94 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-311 Unit Name: Salem #2 Date: 03/10/96 Completed by: Robert Phillips Telephone:
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 15, 1996 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 report for the month of February is being sent to you.
339-2735 *j, Month February 1996 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 15 0 31 16 0 P. 8.1-7 Rl 
ti~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
                                      ~- -  -- ------.._,
- - -96o3i 90344-960229 PDR       ADOCK 05000311 R                         PDR The power is in your hands.
95-2168 REV. 6/94


----OPERATING DATA REPORT Docket No: Date: Completed by: Robert Phillips Telephone:
AVERAGE DAILY UNIT POWER LEVEL Docket No.:      50-311 Unit Name:        Salem #2 Date:            03/10/96 Completed by:    Robert Phillips                    Telephone:        339-2735
Operating Status 1. Unit Name saiem No. 2 Notes 2. Reporting Period February 1996 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 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 NA This Month Year to 696 1440 0 0 0 0 0 0 0 0 0 0 0 0 -2950 -6135 0 0 0 0 0 0 0 0 100 100 Date 50-311 03/10/96 339-2735 since Last N/A Cumulative 126073 78083.6 0 75229.5 0 187781005 78648898 7473498 59.7 59.7 53.6 53.2 25.6 24. Shutdowns scheduled over next 6 months (type, date and duration of each) We are presently forced beyond the scheduled refueling outage. 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-l-7.R2 NO. DATE 3859 02-01-96 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 696 F.C Reason A-Equipment Failure (explain)
                                                                    *j, Month    February    1996 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 15            0                              31 16            0 P. 8.1-7 Rl
B-Maintenance or Test C-Refueling D-Requlatory Restriction UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH February 1996 METHOD OF SHUTTING DOYN REACTOR 4 LICENSE EVENT REPORT # ----------
 
zz 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
~----  - -- - ~-
H-Other (Explain)
OPERATING DATA REPORT Docket No: 50-311 Date:       03/10/96 Completed by:     Robert Phillips                   Telephone: 339-2735 Operating Status
COMPONENT CODE 5 DOCKET NO. : _,5...,0:..,*..:::3_,_1
: 1. Unit Name                         saiem No. 2     Notes
_,_1 UN IT NAME: Salem #2 DATE: 03-10-96 COMPLETED BY: Robert Phillips TELEPHONE:
: 2. Reporting Period               February 1996
609-339-2735  
: 3. Licensed Thermal Power (MWt)             3411
; CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE . zzzz Refueling Schedule Exceeded 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit 1 -Same Source
: 4. Nameplate Rating (Gross MWe)             1170
* 10CFR50.59 EVALUATIONS MONTH: FEBRUARY 1996 DOCKET NO: UNIT NAME: 50-311 SALEM2 03/10/96 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE:
: 5. Design Electrical Rating (Net MWe)       1115
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
: 6. Maximum Dependable Capacity(Gross MWe) 1149
The Station Operations Review Committee has reviewed and concurs with these evaluations.  
: 7. Maximum Dependable Capacity (Net MWe)     1106
: 1. Temporary Modifications (TMOD) 96-008 2. Procedures S2.0P-SO.AR-0001(Z) "Installation Of Blind Flange In Place Of The 2SW26 Isolation Valve To Turbine Generating Area Service Water" -The purpose of this temporary modification is to remove the 2SW26 valve and replace it with a blind flange assembly.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason             NA
The blind flanges are intended to provide the isolation function of the 2SW26 after it is removed for maintenance purposes and to provide external flood and security protection for Service Water (SW) Bay #4 during ongoing maintenance.
: 9. Power Level to Which Restricted, if any (Net MWe)           N/A
The modification allows the return to service of SW "Bay #2 and its associated nuclear header as well as maintain Bay #4 and its associated nuclear header available for station operational needs. The installation of a series of blind flanges in place of the 2SW26 valve does not reduce the margin of safety. (SORC 96-027) "Condenser Air Removal System Operation" Rev. 4 -This procedure revision allows outage schedule flexibility for work performed on Turbine Building Systems. This change allows Demineralized Water System hookup/alignment for temporary cooling to 23 Vacuum Pump. This is necessary for Circulating Water Pump operation to maintain an available radioactive liquid release flowpath.
: 10. Reasons for Restrictions, if any             NA This Month    Year to Date  Cumulative
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-017)
: 11. Hours in Reporting Period             696          1440      126073
. . REFUELING INFORMATION MONTH: FEBRUARY 1996 MONTH: FEBRUARY 1996 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
: 12. No. of Hrs. Rx. was Critical           0              0      78083.6
50-311 SALEM2 03/10/96 R. HELLER 609-339-5162  
: 13. Reactor Reserve Shutdown Hrs.           0              0          0
: 1. Refueling information has changed from last month: YES _. _. NO . X . 2. Scheduled date for next refueling:
: 14. Hours Generator On-Line                 0              0      75229.5
11/02/95 Scheduled date for restart following refueling:
: 15. Unit Reserve Shutdown Hours             0              0          0
09/11/96 3. a. Will Technical Specification changes or other license amendments be required?
: 16. Gross Thermal Energy Generated (MWH)                           0              0    187781005 Gross Elec. Energy Generated (MWH)                           0              0    78648898
YES.
: 18. Net Elec. Energy Gen. (MWH)         -2950          -6135      7473498
NOT DETERMINED TO DATE . X . b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 19. Unit Service Factor                     0              0        59.7
YES. .NO. X . If no, when is it scheduled? (to be determined)  
: 20. Unit Availability Factor                 0              0        59.7
: 5. Scheduled date(s) for submitting proposed licensing action: . n/a 6. Important licensing considerations associated with refueling:  
: 21. unit capacity Factor (using MDC Net)                     0              0        53.6
: 7. Number of Fuel Assemblies:  
: 22. Unit Capacity Factor (using DER Net)                     0              0        53.2
: a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:
: 23. Unit Forced Outage Rate               100           100         25.6
Future spent fuel storage capacity:  
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
: 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
We are presently forced beyond the scheduled refueling outage.
8-1-7.R4 0 749 1632 1632 March2012 
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
.... ,., . ' .... ' .... SALEM GENERATING STATION MONTHLY OPERATING  
Under review.
8-l-7.R2
 
UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH February 1996                                               DOCKET NO. : _,5. .,0:. ,*. : :3_,_1_,_1=----
UN IT NAME: Salem #2 DATE: 03-10-96 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING        LICENSE DURATION                                                                  COMPONENT              CAUSE AND CORRECTIVE ACTION NO.          DATE    TYPE 1      (HOURS)        REASON 2 DOYN REACTOR EVENT REPORT #
SYSTEM CODE 4    CODE 5                    TO PREVENT RECURRENCE                         .
3859      02-01-96  F          696            F.C            4              ----------      zz        zzzz             Refueling Schedule Exceeded 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 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)
 
10CFR50.59 EVALUATIONS                                 DOCKET NO:          50-311 MONTH: FEBRUARY 1996                                   UNIT NAME:         SALEM2 DATE:        03/10/96 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. Temporary Modifications (TMOD) 96-008                   "Installation Of Blind Flange In Place Of The 2SW26 Isolation Valve To Turbine Generating Area Service Water"
                            - The purpose of this temporary modification is to remove the 2SW26 valve and replace it with a blind flange assembly. The blind flanges are intended to provide the isolation function of the 2SW26 after it is removed for maintenance purposes and to provide external flood and security protection for Service Water (SW) Bay #4 during ongoing maintenance. The modification allows the return to service of SW "Bay #2 and its associated nuclear header as well as maintain Bay #4 and its associated nuclear header available for station operational needs. The installation of a series of blind flanges in place of the 2SW26 valve does not reduce the margin of safety. (SORC 96-027)
: 2. Procedures S2.0P-SO.AR-0001(Z)          "Condenser Air Removal System Operation" Rev. 4 - This procedure revision allows outage schedule flexibility for work performed on Turbine Building Systems. This change allows Demineralized Water System hookup/alignment for temporary cooling to 23 Vacuum Pump. This is necessary for Circulating Water Pump operation to maintain an available radioactive liquid release flowpath. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-017)
 
REFUELING INFORMATION                                 DOCKET NO:         50-311 MONTH: FEBRUARY 1996                                   UNIT NAME:         SALEM2 DATE:       03/10/96 COMPLETED BY:            R. HELLER TELEPHONE:          609-339-5162 MONTH: FEBRUARY 1996
: 1. Refueling information has changed from last month: YES _._. NO .       X .
: 2. Scheduled date for next refueling: 11/02/95 Scheduled date for restart following refueling: 09/11/96
: 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. Incore                                                                     0
: b. In Spent Fuel Storage                                                   749
: 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:               March2012 8-1-7.R4
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 2 FEBRUARY 1996 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, the Unit will remain shutdown pending completion of the following actions:
  - UNIT 2 FEBRUARY 1996 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, the Unit 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 10:03, 23 February 2020

Monthly Operating Rept for Feb 1996 for Salem Generating Station Unit 2.W/960315 Ltr
ML18101B273
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/29/1996
From: Heller R, Phillips R, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9603190344
Download: ML18101B273 (7)
v • d • e


Text

PS~G -

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 15, 1996 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 report for the month of February is being sent to you.

ti~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

~- - -- ------.._,

- - -96o3i 90344-960229 PDR ADOCK 05000311 R PDR The power is in your hands.

95-2168 REV. 6/94

AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-311 Unit Name: Salem #2 Date: 03/10/96 Completed by: Robert Phillips Telephone: 339-2735

  • j, Month February 1996 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 15 0 31 16 0 P. 8.1-7 Rl

~---- - -- - ~-

OPERATING DATA REPORT Docket No: 50-311 Date: 03/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name saiem No. 2 Notes
2. Reporting Period February 1996
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 NA This Month Year to Date Cumulative
11. Hours in Reporting Period 696 1440 126073
12. No. of Hrs. Rx. was Critical 0 0 78083.6
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 75229.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 187781005 Gross Elec. Energy Generated (MWH) 0 0 78648898
18. Net Elec. Energy Gen. (MWH) -2950 -6135 7473498
19. Unit Service Factor 0 0 59.7
20. Unit Availability Factor 0 0 59.7
21. unit capacity Factor (using MDC Net) 0 0 53.6
22. Unit Capacity Factor (using DER Net) 0 0 53.2
23. Unit Forced Outage Rate 100 100 25.6
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently forced beyond the scheduled refueling outage.

25. If shutdown at end of Report Period, Estimated Date of Startup:

Under review.

8-l-7.R2

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH February 1996 DOCKET NO. : _,5. .,0:. ,*. : :3_,_1_,_1=----

UN IT NAME: Salem #2 DATE: 03-10-96 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE DURATION COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 DOYN REACTOR EVENT REPORT #

SYSTEM CODE 4 CODE 5 TO PREVENT RECURRENCE .

3859 02-01-96 F 696 F.C 4 ---------- zz zzzz Refueling Schedule Exceeded 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 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)

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: FEBRUARY 1996 UNIT NAME: SALEM2 DATE: 03/10/96 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. Temporary Modifications (TMOD)96-008 "Installation Of Blind Flange In Place Of The 2SW26 Isolation Valve To Turbine Generating Area Service Water"

- The purpose of this temporary modification is to remove the 2SW26 valve and replace it with a blind flange assembly. The blind flanges are intended to provide the isolation function of the 2SW26 after it is removed for maintenance purposes and to provide external flood and security protection for Service Water (SW) Bay #4 during ongoing maintenance. The modification allows the return to service of SW "Bay #2 and its associated nuclear header as well as maintain Bay #4 and its associated nuclear header available for station operational needs. The installation of a series of blind flanges in place of the 2SW26 valve does not reduce the margin of safety. (SORC 96-027)

2. Procedures S2.0P-SO.AR-0001(Z) "Condenser Air Removal System Operation" Rev. 4 - This procedure revision allows outage schedule flexibility for work performed on Turbine Building Systems. This change allows Demineralized Water System hookup/alignment for temporary cooling to 23 Vacuum Pump. This is necessary for Circulating Water Pump operation to maintain an available radioactive liquid release flowpath. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-017)

REFUELING INFORMATION DOCKET NO: 50-311 MONTH: FEBRUARY 1996 UNIT NAME: SALEM2 DATE: 03/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 MONTH: FEBRUARY 1996

1. Refueling information has changed from last month: YES _._. NO . X .
2. Scheduled date for next refueling: 11/02/95 Scheduled date for restart following refueling: 09/11/96
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. Incore 0
b. In Spent Fuel Storage 749
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: March2012 8-1-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 FEBRUARY 1996 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, the Unit 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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