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| issue date = 11/30/1996
| issue date = 11/30/1996
| title = Monthly Operating Rept for Nov 1996 for Salem 1.W/961213 Ltr
| title = Monthly Operating Rept for Nov 1996 for Salem 1.W/961213 Ltr
| author name = GARCHOW D F, HELLER R, PHILLIPS R
| author name = Garchow D, Heller R, Phillips R
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:L . ' e
{{#Wiki_filter:.'             PS~G e
* 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 SALEMN0.1 DOCKET NO: 50-272 December 13, 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 November is being sent to you. RH:vls Enclosures c Mr. H. J. Miller Sincerely
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit December 13, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMN0.1 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 report for the month of November is being sent to you.
: yours, General Manager -Salem Operations
Sincerely yours,
*Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046 --
                                                        '/IJ.£~chow General Manager -
-----( ---9b-12l90t9f 961130 PDR ADOCK 05000272 R PDR The power is in your hands. 95-2168 REV. 6/94
Salem Operations RH:vls Enclosures c       Mr. H. J. Miller
' I e OPERATING DATA REPORT * .' ' Docket No: 50-272 Date: 12/10/96 Completed by: Robert Phillips Telephone:
                  *Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046
339-2735 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period November 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
                          --  --~------ - ----
: 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
( --- 9b-12l90t9f 961130 PDR ADOCK 05000272 R                         PDR The power is in your hands.
{MWH} 17. Gross Elec. Energy Generated
95-2168 REV. 6/94 L
{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 24. Shutdowns scheduled over next 6 Refueling extension.
This Month 720 0 0 0 0 0 0 -2764 0 0 0 0 100 months (type, Year to Date 8040 0 0 0 0 0 0 -27105 0 0 0 0 100 Cumulative 170257 104380.5 0 100388.3 0 318062229 105301000 100177808 58.9 58.9 53.2 52.7 25.8 date and duration of each) 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-1-7.R2 


DAILY UNIT POWER LEVEL --Docket No.: 50-272 Unit Name: Salem #1 Date: 12/10/96 Completed by: Robert Phillips Telephone:
      '  I e    OPERATING DATA REPORT
339-2735 Month November 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 0 15 0 31 16 0 P. 8.1-7 Rl NO. DATE 4092 11/01/96 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 720 F c Reason A-Equipment Failure (explain)
* Docket No:    50-272 Date:        12/10/96 Completed by:          Robert Phillips                  Telephone:    339-2735 Operating Status
B-Maintenance or Test C-Refueling D-Requlatory Restriction 4 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH November 1996 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT SYSTEM REPORT # CODE 4 ----------
: 1.      Unit Name                        Salem No. 1    Notes
H J 3 'Method: 1-Manual 2-Manual Scram 3-Automatic Scram E-Operator Training & License Examination F-Administrative 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
: 2.      Reporting Period              November 1996
H-Other (Explain)
: 3.      Licensed Thermal Power {MWt}              3411
COMPONENT CODE 5 DOCKET NO. : _,5::.::0..,_-=27:..=2:.,,.,..
: 4.      Nameplate Rating {Gross MWe}              1170
__ _ UNIT NAME: Salem #1 DATE: 12/10/96 COMPLETED BY: Robert Phillips
: 5.      Design Electrical Rating (Net MWe}        1115
* TELEPHONE:
: 6.      Maximum Dependable Capacity(Gross MWe} 1149
609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 2422 Nuclear Steam Generator Systems. 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 -Same Source 10CFR50.59 EVALUATIONS MONTH: NOVEMBER 1996 DOCKET NO: UNIT NAME: 50-272 SALEM 1 CONTACT: TELEPHONE:
: 7.      Maximum Dependable Capacity (Net MWe} 1106
R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
: 8.      If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason        NA
The Station Operations Review Committee has reviewed and concurs with these evaluations.  
: 9.      Power Level to Which Restricted, if any (Net MWe}          N/A
: 1. Procedures SC.SA-AP.ZZ-0055(Q)
: 10. Reasons for Restrictions, if any        ~~~~~~~---"-"N+-=A'--~~~~~~~~~~
NC.NA-AP.ZZ-OOOl(Q) "Outage Risk Management" Rev. 2 -This revision has been issued to incorporate lessons from approximately 8 months of utilizing the Shutdown Safety Plan (SSP) concept as our means to manage outage risk. The major features of this revision are: 1.) Clarified when a Contingency Plan is required for emergent issues; 2.) Clarified when AVAILABLE equipment may be removed from service; 3.) Clarified protected area posting requirements; 4.) Provided direction on handling activities approved for work during the outage but which can not be scheduled in accordance with the SSP. The Outage Shift Management Team will code "RSE" until the SSP revision is processed; 5.) Prohibited single Service Water header operation in Modes 4 and 5; and 6.) Deleted the requirement for SORC approval of SSP revisions.
This Month  Year to Date    Cumulative
Added Nuclear Safety Review member to the Restart Assessment Team and added Operations Manager approval.
: 12.      Hours in Reporting Period            720          8040          170257
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161) "Nuclear Procedure System" Rev. 10 -This revision established a four-level procedure system. Nuclear Policies (NPs) and Nuclear Business Procedures (NBPs) will not be part of the four-level procedure system and will either be incorporated into the appropriate document or deleted as outlined in the implementation requirements.
: 12.      No. of Hrs. Rx. was Critical          0              0          104380.5
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161) 10CFR50.59 EVALUATIONS MONTH: NOVEMBER 1996 DOCKET NO: UNIT NAME: 50-272 SALEM 1 NC.NA-AP .ZZ-0005(Q)  
: 13.      Reactor Reserve Shutdown Hrs.          0              0              0
: 2. Safety Evaluations CONTACT: TELEPHONE:
: 14.      Hours Generator On-Line                0              0          100388.3
R. HELLER 609-3 3 9-5162 "Station Operating Practices" Rev. 7 -This revision is an extensive re-write of this procedure.
: 15.      Unit Reserve Shutdown Hours            0              0              0
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161) TSC.OP-SO.CA-OlOl(Q) "Maintaining Control Air System During Station Air System Manifold Replacement" Rev. 0 -Implementation of this activity allowed a portion of the station air discharge manifold to be replaced while still providing control air to users in various plant locations.
: 16.      Gross Thermal Energy Generated
Service was provided utilizing temporary air compressors installed via approved temporary modifications and existing Operations procedures.
{MWH}                          0              0        318062229
In addition, both the Unit 1 and 2 Emergency Control Area Air Conditioning Systems and the air compressor were available on standby in the manual mode or in auto operation.
: 17.      Gross Elec. Energy Generated
This activity was implemented with both units in the defueled Mode. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-166) UFSAR "96-127 -Control Air System Clarification" -The Salem UFSAR is being clarified due to a statement made in Section 9 .3 .1.2.1 which indicates that two compressors are required to provide 100% air to the Plant, while only one compressor is enough to provide 100% of the air load. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-117)
{MWH}                          0              0        105301000
' ' REFUELING INFORMATION MONTH: NOVEMBER 1996 MONTH : NOVEMBER 1996 DOCKET NO: UNIT NAME: CONTACT: TELEPHONE:
: 18.      Net Elec. Energy Gen. (MWH}        -2764        -27105        100177808
50-272 SALEM 1 R. HELLER 609-339-5162 Refueling information has changed from last month: YES _. _. NO . X . Scheduled date for next refueling: (to be determined)
: 19.      Unit Service Factor                    0              0              58.9
Scheduled date for restart following refueling: (to be determined)  
: 20.      Unit Availability Factor              0              0              58.9
: 21.      Unit Capacity Factor (using MDC Net)                  0                0            53.2
: 22. Unit Capacity Factor (using DER Net}                  0                0            52.7
: 23. Unit Forced outage Rate                  100            100            25.8
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling extension.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
Under review.
8-1-7.R2
 
AVE~    DAILY UNIT POWER LEVEL   --
Docket No.:   50-272 Unit Name:     Salem #1 Date:         12/10/96 Completed by:     Robert Phillips                     Telephone:     339-2735 Month       November   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             0 15             0                               31 16             0 P. 8.1-7 Rl
 
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH November 1996                                           DOCKET NO. : _,5::.::0..,_-=27:..=2:.,,.,.._ __
UNIT NAME: Salem #1 DATE: 12/10/96 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 4092    11/01/96  F          720            F c            4              ----------      HJ      2422           Nuclear Steam Generator Systems.
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        CNUREG-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:            50-272 MONTH: NOVEMBER 1996                                     UNIT NAME:           SALEM 1 CONTACT:         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. Procedures SC.SA-AP.ZZ-0055(Q)           "Outage Risk Management" Rev. 2 - This revision has been issued to incorporate lessons from approximately 8 months of utilizing the Shutdown Safety Plan (SSP) concept as our means to manage outage risk. The major features of this revision are:
1.) Clarified when a Contingency Plan is required for emergent issues; 2.) Clarified when AVAILABLE equipment may be removed from service; 3.) Clarified protected area posting requirements; 4.) Provided direction on handling activities approved for work during the outage but which can not be scheduled in accordance with the SSP. The Outage Shift Management Team will code "RSE" until the SSP revision is processed; 5.) Prohibited single Service Water header operation in Modes 4 and 5; and 6.) Deleted the requirement for SORC approval of SSP revisions. Added Nuclear Safety Review member to the Restart Assessment Team and added Operations Manager approval. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 96-161)
NC.NA-AP.ZZ-OOOl(Q)          "Nuclear Procedure System" Rev. 10 - This revision established a four-level procedure system. Nuclear Policies (NPs) and Nuclear Business Procedures (NBPs) will not be part of the four-level procedure system and will either be incorporated into the appropriate document or deleted as outlined in the implementation requirements. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161)
 
10CFR50.59 EVALUATIONS                           DOCKET NO:          50-272 MONTH: NOVEMBER 1996                             UNIT NAME:           SALEM 1 CONTACT:          R. HELLER TELEPHONE:          609-3 3 9-5162 NC.NA-AP .ZZ-0005(Q) "Station Operating Practices" Rev. 7 - This revision is an extensive re-write of this procedure. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161)
: 2. Safety Evaluations TSC.OP-SO.CA-OlOl(Q) "Maintaining Control Air System During Station Air System Manifold Replacement" Rev. 0 - Implementation of this activity allowed a portion of the station air discharge manifold to be replaced while still providing control air to users in various plant locations. Service was provided utilizing temporary air compressors installed via approved temporary modifications and existing Operations procedures. In addition, both the Unit 1 and 2 Emergency Control Area Air Conditioning Systems and the air compressor were available on standby in the manual mode or in auto operation. This activity was implemented with both units in the defueled Mode. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-166)
UFSAR                 "96-127 - Control Air System Clarification" - The Salem UFSAR is being clarified due to a statement made in Section 9 .3 .1.2.1 which indicates that two compressors are required to provide 100% air to the Plant, while only one compressor is enough to provide 100% of the air load. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-117)
 
REFUELING INFORMATION                                 DOCKET NO:         50-272 MONTH: NOVEMBER 1996                                   UNIT NAME:         SALEM 1 CONTACT:         R. HELLER TELEPHONE:          609-339-5162 MONTH : NOVEMBER 1996 Refueling information has changed from last month: YES _._. NO . X         .
Scheduled date for next refueling: (to be determined)
Scheduled date for restart following refueling: (to be determined)
: a. Will Technical Specification changes or other license amendments be required?
: a. Will Technical Specification changes or other license amendments be required?
YES.
YES.       .NO~.-~
NOT DETERMINED TO DATE . X . b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
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?
Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:
YES.       .NO. X   .
Number of Fuel Assemblies:  
If no, when is it scheduled? (to be determined)
: a. Incore b. In Spent Fuel Storage Present licensed spent fuel storage capacity:
Scheduled date(s) for submitting proposed licensing action: .     n/a Important licensing considerations associated with refueling:
Future spent fuel storage capacity:
Number of Fuel Assemblies:
Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
: a. Incore                                                                     0
0 989 1632 1632 November 2008
: b. In Spent Fuel Storage                                                   989 Present licensed spent fuel storage capacity:                             1632 Future spent fuel storage capacity:                                       1632 Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:             November 2008
, ,, ' ' SALEM GENERATING STATION MONTHLY OPERATING  
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 1 NOVEIV1BER 1996 SALEM UNIT NO. 1 The Unit is in a refueling and Steam Generator replacement outage and 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 1 NOVEIV1BER 1996 SALEM UNIT NO. 1 The Unit is in a refueling and Steam Generator replacement outage and 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 the 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 the 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 05:23, 3 February 2020

Monthly Operating Rept for Nov 1996 for Salem 1.W/961213 Ltr
ML18102A673
Person / Time
Site: Salem PSEG icon.png
Issue date: 11/30/1996
From: Garchow D, Heller R, Phillips R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9612190191
Download: ML18102A673 (8)
v • d • e


Text

.' PS~G e

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit December 13, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMN0.1 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 report for the month of November is being sent to you.

Sincerely yours,

'/IJ.£~chow General Manager -

Salem Operations RH:vls Enclosures c Mr. H. J. Miller

  • Regional Administrator USNRC, Region I 475 Allendale Road King of Prussia, PA 19046

-- --~------ - ----

( --- 9b-12l90t9f 961130 PDR ADOCK 05000272 R PDR The power is in your hands.

95-2168 REV. 6/94 L

' I e OPERATING DATA REPORT

  • Docket No: 50-272 Date: 12/10/96 Completed by: Robert Phillips Telephone: 339-2735 Operating Status
1. Unit Name Salem No. 1 Notes
2. Reporting Period November 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 ~~~~~~~---"-"N+-=A'--~~~~~~~~~~

This Month Year to Date Cumulative

12. Hours in Reporting Period 720 8040 170257
12. No. of Hrs. Rx. was Critical 0 0 104380.5
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 100388.3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated

{MWH} 0 0 318062229

17. Gross Elec. Energy Generated

{MWH} 0 0 105301000

18. Net Elec. Energy Gen. (MWH} -2764 -27105 100177808
19. Unit Service Factor 0 0 58.9
20. Unit Availability Factor 0 0 58.9
21. Unit Capacity Factor (using MDC Net) 0 0 53.2
22. Unit Capacity Factor (using DER Net} 0 0 52.7
23. Unit Forced outage Rate 100 100 25.8
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling extension.

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

Under review.

8-1-7.R2

AVE~ DAILY UNIT POWER LEVEL --

Docket No.: 50-272 Unit Name: Salem #1 Date: 12/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month November 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 0 15 0 31 16 0 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH November 1996 DOCKET NO. : _,5::.::0..,_-=27:..=2:.,,.,.._ __

UNIT NAME: Salem #1 DATE: 12/10/96 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 4092 11/01/96 F 720 F c 4 ---------- HJ 2422 Nuclear Steam Generator Systems.

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 CNUREG-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: 50-272 MONTH: NOVEMBER 1996 UNIT NAME: SALEM 1 CONTACT: 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. Procedures SC.SA-AP.ZZ-0055(Q) "Outage Risk Management" Rev. 2 - This revision has been issued to incorporate lessons from approximately 8 months of utilizing the Shutdown Safety Plan (SSP) concept as our means to manage outage risk. The major features of this revision are:

1.) Clarified when a Contingency Plan is required for emergent issues; 2.) Clarified when AVAILABLE equipment may be removed from service; 3.) Clarified protected area posting requirements; 4.) Provided direction on handling activities approved for work during the outage but which can not be scheduled in accordance with the SSP. The Outage Shift Management Team will code "RSE" until the SSP revision is processed; 5.) Prohibited single Service Water header operation in Modes 4 and 5; and 6.) Deleted the requirement for SORC approval of SSP revisions. Added Nuclear Safety Review member to the Restart Assessment Team and added Operations Manager approval. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 96-161)

NC.NA-AP.ZZ-OOOl(Q) "Nuclear Procedure System" Rev. 10 - This revision established a four-level procedure system. Nuclear Policies (NPs) and Nuclear Business Procedures (NBPs) will not be part of the four-level procedure system and will either be incorporated into the appropriate document or deleted as outlined in the implementation requirements. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161)

10CFR50.59 EVALUATIONS DOCKET NO: 50-272 MONTH: NOVEMBER 1996 UNIT NAME: SALEM 1 CONTACT: R. HELLER TELEPHONE: 609-3 3 9-5162 NC.NA-AP .ZZ-0005(Q) "Station Operating Practices" Rev. 7 - This revision is an extensive re-write of this procedure. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-161)

2. Safety Evaluations TSC.OP-SO.CA-OlOl(Q) "Maintaining Control Air System During Station Air System Manifold Replacement" Rev. 0 - Implementation of this activity allowed a portion of the station air discharge manifold to be replaced while still providing control air to users in various plant locations. Service was provided utilizing temporary air compressors installed via approved temporary modifications and existing Operations procedures. In addition, both the Unit 1 and 2 Emergency Control Area Air Conditioning Systems and the air compressor were available on standby in the manual mode or in auto operation. This activity was implemented with both units in the defueled Mode. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-166)

UFSAR "96-127 - Control Air System Clarification" - The Salem UFSAR is being clarified due to a statement made in Section 9 .3 .1.2.1 which indicates that two compressors are required to provide 100% air to the Plant, while only one compressor is enough to provide 100% of the air load. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 96-117)

REFUELING INFORMATION DOCKET NO: 50-272 MONTH: NOVEMBER 1996 UNIT NAME: SALEM 1 CONTACT: R. HELLER TELEPHONE: 609-339-5162 MONTH : NOVEMBER 1996 Refueling information has changed from last month: YES _._. NO . X .

Scheduled date for next refueling: (to be determined)

Scheduled date for restart following refueling: (to be determined)

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)

Scheduled date(s) for submitting proposed licensing action: . n/a Important licensing considerations associated with refueling:

Number of Fuel Assemblies:

a. Incore 0
b. In Spent Fuel Storage 989 Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632 Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: November 2008

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 NOVEIV1BER 1996 SALEM UNIT NO. 1 The Unit is in a refueling and Steam Generator replacement outage and 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 the 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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