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| issue date = 12/31/1995
| issue date = 12/31/1995
| title = Monthly Operating Rept for Dec 1995 for Salem Generating Station Unit 1.W/960115 Ltr
| title = Monthly Operating Rept for Dec 1995 for Salem Generating Station Unit 1.W/960115 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=
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* 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. 1 DOCKET NO: 50-272 GMS-96-0010 January 15, 1996 In compliance with Section 6.9.1.6J Reporting Requirements for the Salem Technical Specifications, the original copy of 1 the monthly operating report for the month of December 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 9601  
* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit January 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET NO: 50-272 GMS-96-0010 In compliance with Section 6.9.1.6J Reporting Requirements for the Salem Technical 1
--------\
Specifications, the original copy of the monthly operating report for the month of December is being sent to you.
PDR ADOCK 05000272 R PDR 190C43 The power is in your hands. 95-2168 REV. 6/94 o T AVERA. DAILY UNIT POWER LEVEL
                                                ~~~
* Docket No.: 50-272 Unit Name: Salem #1 Date: 01/10/96 Completed by: Robert Phillips Telephone:
General Manager -
339-2735 Month December 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
Salem Operations RH:vls Enclosures C       Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King ofPrussia, PA 19046 9601 F:?o269----<fs123T-~----~-------- --------\
* OPERATING DATA REPORT
PDR ADOCK 05000272 R                        PDR 190C43 The power is in your hands.
* Docket No: Date: Completed by: Robert Phillips Telephone:
95-2168 REV. 6/94
Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period December 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 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 (MWH) 17. 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 744 . 0 0 0 0 0 0 -2639 0 0 0 0 0 NA Year to Date 8760. 2660.9 0 2632.1 0 8010326.4 2689850 2522749 30.0 30.0 26.0 25.8 56.3 50-272 01/l0/96 339-2735 since Last N/A Cumulative 162217 104380.5 0 100388.3 0 318062229.2 105301000 100204913 61.8 6L8 55.8 55.4 22.9 24. Shutdowns scheduled over next 6 months (type, date and duration of each) We are presently in a scheduled extension of refueling outage. 25. If shutdown at end of Report Period, Estimated Date of startup: Under review. 8-l-7.R2 NO. DATE 3642 12-1-95 s 3824 12-14-95 s 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 312 c 432 c Reason A-Equipment Failure (explain)
o T AVERA. DAILY UNIT POWER LEVEL
B-Maintenance or Test C-Refueling D-Requlatory Restriction 4 4 UNIT SHUTDOWN AND POWER .REDUCTIONS REPORT MONTH December 1995 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # ---------zz ---------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)
* Docket No.:    50-272 Unit Name:    Salem #1 Date:          01/10/96 Completed by:    Robert Phillips                  Telephone:    339-2735 Month        December    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
H-Other (Explain)
 
COMPONENT CODE 5 DOCKET NO. :
Completed by:
__ _ UNIT NAME: Salem #1 DATE: 01/10/96 COMPLETED BY: Robert Phillips TELEPHONE:
* OPERATING DATA REPORT Robert Phillips Docket No:
609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzzzz Refueling Outage zzzzzz Scheduled extension to refueling outage 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File 5 Exhibit 1 -Same Source . . ' (NUREG-0161)
Date:
* 
Telephone:
-------------------------------------------
50-272 01/l0/96 339-2735 Operating Status
*
: 1. Unit Name                        Salem No. 1    Notes
* 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/96 R.HELLER 609-339-5162 DATE:
: 2. Reporting Period              December 1995
* COMPLETED BY: TELEPHONE:
: 3. Licensed Thermal Power {MWt)               3411
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
: 4. 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) lEC-3322, Pkg. 4 lEC-3323, Pkg .. 2 "Service Water Pipe Replacement  
: 6. Maximum Dependable Capacity(Gross MWe) 1149
-Auxiliary Building Nuclear Header i2" Rev. 0 -This package replaces portions of the supply and return piping for 12A and 12B Component Cooling Exchanger (CCHX) from the 12 Service Water (SW) header. It replaces carbon steel cement or coal tar epoxy lined pipe (spec. 27C) with 6% molybdemiin austenitic stainless steel pipe (spec. 27F) and maintains the current pipe routing. This package replaces portions of the SW supply and return headers for 12A and 12B CCHX in the Auxiliary building at floor elevation 84'-0." There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95.-108) "Service Water Large Bore Pipe-Replacement" Rev. 2 -This modification upgrades the material for Service Water (SW) system piping. Due to corrective maintenance activities on valve 13 SW20 and the current system outage schedule constraint, it is necessary to establish an interim system configuration and boundaries without 13 SW20 to facilitate the restoration of the No. 12 SW Header. The system will be restored to original flow configuration by re-installing the refurbished 13 SW20 valve and the associated p.iping spools during a later header 12 outage with completion of SW DCP, lEC-3323, Pkg. 3, Rev. 1. The interim configuration, by replacing the turbine crosstie isolation valve with a blind flange, maintains the design basis and safety related function of the system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-146)
: 7. Maximum Dependable Capacity (Net MWe)     1106
*
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason        NA
* 10CFR50.59 EVALUATIONS MONTH: DECEMBER 1995 DOCKET NO: UNIT NAME: 50-272 SALEM 1 01/10/96 (Cont'd) 4. Safety Evaluation (S/E) W/O 940524110 DATE: COMPLETED BY: TELEPHONE:
: 9. Power Level to Which Restricted, if any (Net MWe)            N/A
R. HELLER 609-339-5162 "Freeze Seal of the Spray Additive Tank (SAT) Sample Line to Valve 1CS30" -The proposal is to install a temporary freeze seal on the 3/4", stainless steel, Spray Additive Tank (SAT) local sample line, upstream of the sample isolation valve, 1CS30. The installation of a freeze seal will allow approximately 4000 gallons of30% wt. Sodium Hydroxide (NaOH) solution to remain in the SAT (1CSE5) while maintenance of the sample line isolation valve is performed.
: 10. Reasons for Restrictions, if any                  NA This Month    Year to Date    Cumulative
: 12. Hours in Reporting Period            744 .         8760.         162217
: 12. No. of Hrs. Rx. was critical          0           2660.9        104380.5
: 13. Reactor Reserve Shutdown Hrs.          0              0              0
: 14. Hours Generator On-Line                0          2632.1        100388.3
: 15. Unit Reserve*Shutdown Hours            0              0              0
: 16. Gross Thermal Energy Generated (MWH)                          0        8010326.4     318062229.2
: 17. Gross Elec. Energy Generated
{MWH)                          0          2689850        105301000
: 18. Net Elec. Energy Gen. {MWH)        -2639        2522749        100204913
: 19. Unit Service Factor                    0              30.0            61.8
: 20. Unit Availability Factor              0              30.0            6L8
: 21. Unit Capacity Factor (using MDC Net)                   0              26.0          55.8
: 22. Unit Capacity Factor (using DER Net)                   0              25.8          55.4
: 23. Unit Forced Outage Rate                0              56.3          22.9
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
We are presently in a scheduled extension of refueling outage.
: 25. If shutdown at end of Report Period, Estimated Date of startup:
Under review.
8-l-7.R2
 
UNIT SHUTDOWN AND POWER .REDUCTIONS REPORT MONTH December 1995                                              DOCKET NO. : _,5::..:D:...-~27:.:2,___ __
UNIT NAME: Salem #1 DATE: 01/10/96 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING        LICENSE                                                                                            .
DURATION                      DOWN            EVENT            SYSTEM    COMPONENT              CAUSE AND CORRECTIVE ACTION 2
NO.          DATE    TYPE 1 (HOURS)      REASON        REACTOR          REPORT #        CODE 4     CODE 5                    TO PREVENT RECURRENCE 3642      12-1-95    s          312            c              4              ---------       zz        zzzzzz          Refueling Outage 3824      12-14-95  s          432            c              4              ---------       zz        zzzzzz          Scheduled extension to refueling outage
                                                                                                                                                                                    ' ~
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:
* 50-272 MONTH: DECEMBER 1995                                     UNIT NAME:             SALEM 1 DATE:          01/10/96
* 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. Design Change Packages (DCP) lEC-3322, Pkg. 4           "Service Water Pipe Replacement - Auxiliary Building Nuclear Header i2" Rev. 0 - This package replaces portions of the supply and return piping for 12A and 12B Component Cooling H~at Exchanger (CCHX) from the 12 Service Water (SW) header. It replaces carbon steel cement or coal tar epoxy lined pipe (spec. 27C) with 6% molybdemiin austenitic stainless steel pipe (spec. 27F) and maintains the current pipe routing. This package replaces portions of the SW supply and return headers for 12A and 12B CCHX in the Auxiliary building at floor elevation 84'-0." There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 95.-108) lEC-3323, Pkg .. 2        "Service Water Large Bore Pipe-Replacement" Rev. 2 - This modification upgrades the material for Service Water (SW) system piping. Due to corrective maintenance activities on valve 13 SW20 and the current system outage schedule constraint, it is necessary to establish an interim system configuration and boundaries without 13 SW20 to facilitate the restoration of the No. 12 SW Header. The system will be restored to original flow configuration by re-installing the refurbished 13 SW20 valve and the associated p.iping spools during a later header 12 outage with completion of SW DCP, lEC-3323, Pkg. 3, Rev. 1. The interim configuration, by replacing the turbine crosstie isolation valve with a blind flange, maintains the design basis and safety related function of the system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-146)
 
10CFR50.59 EVALUATIONS
* DOCKET NO:
* 50-272 MONTH: DECEMBER 1995                                 UNIT NAME:           SALEM 1 DATE:        01/10/96 COMPLETED BY:              R. HELLER TELEPHONE:            609-339-5162 (Cont'd)
: 4. Safety Evaluation (S/E)
W/O 940524110         "Freeze Seal of the Spray Additive Tank (SAT) Sample Line to Valve 1CS30" - The proposal is to install a temporary freeze seal on the 3/4", stainless steel, Spray Additive Tank (SAT) local sample line, upstream of the sample isolation valve, 1CS30. The installation of a freeze seal will allow approximately 4000 gallons of30% wt. Sodium Hydroxide (NaOH) solution to remain in the SAT (1CSE5) while maintenance of the sample line isolation valve is performed.
The only components affected are part of the Containment Spray System. As the Containment Spray System is not required to be operable in Modes 5, 6 or defueled, and this proposal will only be used during these modes, the margin of safety as defined in the bases of the Technical Specifications will not be compromised. (SORC 95-152)
The only components affected are part of the Containment Spray System. As the Containment Spray System is not required to be operable in Modes 5, 6 or defueled, and this proposal will only be used during these modes, the margin of safety as defined in the bases of the Technical Specifications will not be compromised. (SORC 95-152)
* REFUELING INFORMATION MONTH: DECEMBER 1995 MONTH : DECEMBER 1995
 
* DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
REFUELING INFORMATION
50-272 SALEM 1 01/10/96 R.HELLER 609-339-5162 Refueling information has changed from last month: YES . X . NO ..._. Scheduled date for next refueling:
* DOCKET NO:
09/10/95 Scheduled date for restart following refueling:
* 50-272 MONTH: DECEMBER 1995                                    UNIT NAME:            SALEM 1 DATE:          01/10/96 COMPLETED BY:                R.HELLER TELEPHONE:              609-339-5162 MONTH : DECEMBER 1995 Refueling information has changed from last month: YES . X         . NO . ._.-~
06/30/96 a. Will Technical Specification changes or other license amendments be required?
Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: 06/30/96
YES.
: a. Will Technical Specification changes or other license amendments be required?
NOT DETERMINED TO DATE . X . b. Has the reload fuel design been reviewed by the Station Operating Review Committee?  
YES.       .NO~.----"""
*. 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:
NOT DETERMINED TO DATE .             X   .
Number of Fuel Assemblies: .a. Incore b. In Spent Fuel Storage Present licensed spent fuel storage capacity:
: b. Has the reload fuel design been reviewed by the Station Operating Review Committee? *.
Future spent fuel storage capacity:
YES.       .NO. X   .
Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
If no, when is it scheduled? (to be determined )
8-l-7.R4 0 1005 1632 1632 September 2008 
Scheduled date(s) for submitting proposed licensing action: .       n/a Important licensing considerations associated with refueling:
*
Number of Fuel Assemblies:
* SALEM GENERATING STATION MONTHLY OPERATING  
  .a. Incore                                                                       0
: b. In Spent Fuel Storage                                                     1005 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:               September 2008 8-l-7.R4
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 1 DECEMBER 1995 SALEMUNITNO.
  - UNIT 1 DECEMBER 1995 SALEMUNITNO. 1 The Unit is in a refueling outage and 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:
1 The Unit is in a refueling outage and 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: e Appropriately address long standing equipment reliability and operability issues
e 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 05:37, 3 February 2020

Monthly Operating Rept for Dec 1995 for Salem Generating Station Unit 1.W/960115 Ltr
ML18101B174
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/31/1995
From: Heller R, Phillips R, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GMS-96-0010, GMS-96-10, NUDOCS 9601190269
Download: ML18101B174 (8)
v • d • e


Text

PS~G

' .) v

  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit January 15, 1996 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn.: Document Control Desk MONTHLY OPERATING REPORT SALEMNO. 1 DOCKET NO: 50-272 GMS-96-0010 In compliance with Section 6.9.1.6J Reporting Requirements for the Salem Technical 1

Specifications, the original copy of the monthly operating report for the month of December is being sent to you.

~~~

General Manager -

Salem Operations RH:vls Enclosures C Mr. Thomas T. Martin Regional Administrator USNRC, Region I 631 Park Avenue King ofPrussia, PA 19046 9601 F:?o269----<fs123T-~----~-------- --------\

PDR ADOCK 05000272 R PDR 190C43 The power is in your hands.

95-2168 REV. 6/94

o T AVERA. DAILY UNIT POWER LEVEL

  • Docket No.: 50-272 Unit Name: Salem #1 Date: 01/10/96 Completed by: Robert Phillips Telephone: 339-2735 Month December 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

Completed by:

  • OPERATING DATA REPORT Robert Phillips Docket No:

Date:

Telephone:

50-272 01/l0/96 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period December 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 NA This Month Year to Date Cumulative
12. Hours in Reporting Period 744 . 8760. 162217
12. No. of Hrs. Rx. was critical 0 2660.9 104380.5
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 2632.1 100388.3
15. Unit Reserve*Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 8010326.4 318062229.2
17. Gross Elec. Energy Generated

{MWH) 0 2689850 105301000

18. Net Elec. Energy Gen. {MWH) -2639 2522749 100204913
19. Unit Service Factor 0 30.0 61.8
20. Unit Availability Factor 0 30.0 6L8
21. Unit Capacity Factor (using MDC Net) 0 26.0 55.8
22. Unit Capacity Factor (using DER Net) 0 25.8 55.4
23. Unit Forced Outage Rate 0 56.3 22.9
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently in a scheduled extension of refueling outage.

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

Under review.

8-l-7.R2

UNIT SHUTDOWN AND POWER .REDUCTIONS REPORT MONTH December 1995 DOCKET NO. : _,5::..:D:...-~27:.:2,___ __

UNIT NAME: Salem #1 DATE: 01/10/96 COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE .

DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 3642 12-1-95 s 312 c 4 --------- zz zzzzzz Refueling Outage 3824 12-14-95 s 432 c 4 --------- zz zzzzzz Scheduled extension to refueling outage

' ~

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:
  • 50-272 MONTH: DECEMBER 1995 UNIT NAME: SALEM 1 DATE: 01/10/96
  • 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. Design Change Packages (DCP) lEC-3322, Pkg. 4 "Service Water Pipe Replacement - Auxiliary Building Nuclear Header i2" Rev. 0 - This package replaces portions of the supply and return piping for 12A and 12B Component Cooling H~at Exchanger (CCHX) from the 12 Service Water (SW) header. It replaces carbon steel cement or coal tar epoxy lined pipe (spec. 27C) with 6% molybdemiin austenitic stainless steel pipe (spec. 27F) and maintains the current pipe routing. This package replaces portions of the SW supply and return headers for 12A and 12B CCHX in the Auxiliary building at floor elevation 84'-0." There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95.-108) lEC-3323, Pkg .. 2 "Service Water Large Bore Pipe-Replacement" Rev. 2 - This modification upgrades the material for Service Water (SW) system piping. Due to corrective maintenance activities on valve 13 SW20 and the current system outage schedule constraint, it is necessary to establish an interim system configuration and boundaries without 13 SW20 to facilitate the restoration of the No. 12 SW Header. The system will be restored to original flow configuration by re-installing the refurbished 13 SW20 valve and the associated p.iping spools during a later header 12 outage with completion of SW DCP, lEC-3323, Pkg. 3, Rev. 1. The interim configuration, by replacing the turbine crosstie isolation valve with a blind flange, maintains the design basis and safety related function of the system. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-146)

10CFR50.59 EVALUATIONS

  • DOCKET NO:
  • 50-272 MONTH: DECEMBER 1995 UNIT NAME: SALEM 1 DATE: 01/10/96 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd)
4. Safety Evaluation (S/E)

W/O 940524110 "Freeze Seal of the Spray Additive Tank (SAT) Sample Line to Valve 1CS30" - The proposal is to install a temporary freeze seal on the 3/4", stainless steel, Spray Additive Tank (SAT) local sample line, upstream of the sample isolation valve, 1CS30. The installation of a freeze seal will allow approximately 4000 gallons of30% wt. Sodium Hydroxide (NaOH) solution to remain in the SAT (1CSE5) while maintenance of the sample line isolation valve is performed.

The only components affected are part of the Containment Spray System. As the Containment Spray System is not required to be operable in Modes 5, 6 or defueled, and this proposal will only be used during these modes, the margin of safety as defined in the bases of the Technical Specifications will not be compromised. (SORC 95-152)

REFUELING INFORMATION

  • DOCKET NO:
  • 50-272 MONTH: DECEMBER 1995 UNIT NAME: SALEM 1 DATE: 01/10/96 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH : DECEMBER 1995 Refueling information has changed from last month: YES . X . NO . ._.-~

Scheduled date for next refueling: 09/10/95 Scheduled date for restart following refueling: 06/30/96

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 1005 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: September 2008 8-l-7.R4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 DECEMBER 1995 SALEMUNITNO. 1 The Unit is in a refueling outage and 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:

e 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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