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=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. 2 DOCKET NO: 50-311 May 12, 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 April are being sent to you. RH:vls Enclosures C Mr. Thomas T. Martin Sincerely yours, John C. Summers General Manager -Salem Operations Regional Administrator USNRC, Region I 631 Park Avenue King of Prussia, PA 19046 8-1-7.R4  
)           PS~G                *
-95o-sfao:i13
* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit May 12, 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 April are being sent to you.
* 950430* *-----. I PDR 05000311 . R PDR
Sincerely yours,
* The power is in yow-hands. 95-2168 REV. 6/94
                                                      ~John C. Summers General Manager -
. " .ERAGE DAILY UNIT POWER Completed by: Robert Phillips Month April 1995 Day Average Daily Power Level (MWe-NET) 1 878 2 1033 3 989 4 1074 5 1081 6 1059 7 1061 8 1072 9 1068 10 1063 11 1069 12 1068 13 1076 14 1087 15 1079 16 1101 P. 8.1-7 Rl Day Docket No.: 50-311 Unit Name: Salem #2 Date: 05-10-95 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
339-2735 Average Daily Power Level (MWe-NET) 17 1047 18 1077 19 1090 20 1101 21 1055 22 1094 23 1108 24 1070 25 1089 26 1086 27 1117 28 1130 29 1015 30 1096 31 
(~---  -95o-sfao:i13
*"
* 950430* *-----.
* OPERATING DATA REPORT * ., Docket No: Date: Completed by: Robert Phillips Telephone:
PDR     ADOC~      05000311 I.       R                       PDR
Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period APRIL 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 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 Date 719 2879 719 1557.40 0 0 719 1350.63 0 0 2422168.8 3834614.4 799620 1226450 767911 1131135 100 46.9 100 46.9 96.6 35.5 95.8 35.2 0 34.5 50-311 05/10/95 339-2735 since Last N/A Cumulative 118752 77172.62 0 74318.55 0 184808398.6 77676458 73854679 62.6 62.6 56.2 55.8 22.0 24. Shutdowns scheduled over next 6 months (type, date and duration of each) None. 25. If shutdown at end of Report Period, Estimated Date of Startup: N A. 8-1-7.R2 NO. DATE 2439 4-1-95 F 1 2 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1995 DURATION TYPE 1 (HOURS) REASON 2 2.23 B Reason A-Equipment Failure (explain)
* The power is in yow- hands.
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)
95-2168 REV. 6/94
H-Other (Explain)
 
LICENSE EVENT SYSTEM REPORT # CODE 4 ------------
  . "
HB 3 Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 DOCKET NO. : UN IT NAME: Salem #2 DATE: 5-10-95 , COMPLETED BY: Robert PH'il l i PS *, TELEPHONE:
                          .ERAGE DAILY UNIT POWER LE~
609-339-2735
Docket No.:  50-311 Unit Name:    Salem #2 Date:        05-10-95 Completed by:     Robert Phillips                   Telephone:    339-2735 Month     April       1995 Day Average Daily Power Level              Day Average Daily Power Level (MWe-NET)                                (MWe-NET) 1           878                           17        1047 2           1033                           18        1077 3           989                           19        1090 4           1074                           20        1101 5         1081                             21        1055 6         1059                             22        1094 7         1061                             23        1108 8         1072                             24        1070 9         1068                             25        1089 10         1063                             26        1086 11         1069                             27        1117 12         1068                             28        1130 13         1076                             29        1015 14         1087                             30        1096 15         1079                             31 16         1101 P. 8.1-7 Rl
-CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE PUMP XX NUCLER STEAM GENERATOR FEEDPUMP # 21 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: APRIL 1995 DOCKET NO: UNIT NAME: 50-311 SALEM2 05/10/95 DATE: COMPLETED BY: TELEPHONE:
      *"
R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
* OPERATING DATA REPORT
The Station Operations Review Committee has reviewed and concurs with these evaluations.
* Docket No:
: 1. Deficiency Reports (DIR), Use-As-Is S-2-SW-MSE-0851 "Salem Unit 2 Service Water Chiller Condenser Recirc Piping Fastener Material" Rev. 0 -This evaluation address concerns relating to the use of potentially inappropriate bolting in the Salem Service Water System identified in Problem Report (PR) 951105025.
Date:
Specifically, this evaluation deals with the flanged connections for No. 22 and 23 Chiller condenser Recirculation Pump Discharge Check Valves (22SW99 and 23 SW99) of Salem Unit No. 2. The bolting used in these flanged connections was found to be ASTM A193 Gr. B8 austenetic stainless steel instead of ASTM Al93 Gr. B7 carbon steel. The nuts were a mixture of carbon steel and austenetic stainless steel. This evaluation, with supporting calculations and analyses, assesses the use of the stainless steel for the subject fasteners and verifies that its use will have no adverse effects on the design parameters or operability of the SW system. Stress and corrosion of the stainless steel were also addressed and found to be acceptable.
50-311 05/10/95 Completed by:         Robert Phillips                    Telephone:    339-2735 Operating Status
There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-041) 
: 1.      Unit Name                          Salem No. 2      Notes
. ..
: 2.      Reporting Period                APRIL        1995
* REFUELING INFORMATION MONTH: APRIL 1995 MONTH: APRIL 1995
: 3.      Licensed Thermal Power (MWt)                3411
* DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
: 4.      Nameplate Rating (Gross MWe)                1170
50-311 SALEM2 05/10/95 R.HELLER 609-339-5162
: 5.     Design Electrical Rating (Net MWe)          1115
: 1. Refueling information has changed from last month: YES=NO X 2. Scheduled date for next refueling:
: 6.     Maximum Dependable Capacity(Gross MWe) 1149
April 6, 1996 Scheduled date for restart following refueling:
: 7.     Maximum Dependable Capacity (Net MWe)       1106
June 5, 1996 3. a. Will Technical Specification changes or other license amendments be required?
: 8.       If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason      NA
NOT DETERMINED TO DATE X b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 9.      Power Level to Which Restricted, if any (Net MWe)             N/A
YES NO X If no, when is it scheduled?
: 10. Reasons for Restrictions, if any                NA This Month    Year to Date    Cumulative
April 1996 5. Scheduled date(s) for submitting proposed licensing action:
: 11. Hours in Reporting Period              719          2879        118752
___ _ 6. Important licensing considerations associated with refueling:
: 12. No. of Hrs. Rx. was Critical           719          1557.40      77172.62
: 13. Reactor Reserve Shutdown Hrs.             0              0            0
: 14. Hours Generator On-Line                 719          1350.63      74318.55
: 15. Unit Reserve Shutdown Hours               0              0            0
: 16. Gross Thermal Energy Generated (MWH)                   . 2422168.8      3834614.4    184808398.6 Gross Elec. Energy Generated (MWH)                       799620        1226450      77676458
: 18. Net Elec. Energy Gen. (MWH)           767911        1131135      73854679
: 19. Unit Service Factor                     100          46.9          62.6
: 20. Unit Availability Factor                 100          46.9          62.6
: 21. Unit Capacity Factor (using MDC Net)                   96.6            35.5        56.2
: 22. Unit Capacity Factor (using DER Net)                   95.8            35.2        55.8
: 23. Unit Forced Outage Rate                     0              34.5        22.0
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
None.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
N A.
8-1-7.R2
 
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1995                                              DOCKET NO. : ~5~0""'-~3~1~1=----
UN IT NAME: Salem #2 DATE: 5-10-95         ,
COMPLETED BY: Robert PH'il l i PS *,
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 2439      4-1-95    F          2.23          B              4              ------------    HB        PUMP XX        NUCLER STEAM GENERATOR FEEDPUMP # 21 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:             50-311 MONTH: APRIL 1995                                      UNIT NAME:            SALEM2 DATE:        05/10/95 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. Deficiency Reports (DIR), Use-As-Is S-2-SW-MSE-0851          "Salem Unit 2 Service Water Chiller Condenser Recirc Piping Fastener Material" Rev. 0 - This evaluation address concerns relating to the use of potentially inappropriate bolting in the Salem Service Water System identified in Problem Report (PR) 951105025. Specifically, this evaluation deals with the flanged connections for No. 22 and 23 Chiller condenser Recirculation Pump Discharge Check Valves (22SW99 and 23 SW99) of Salem Unit No. 2.
The bolting used in these flanged connections was found to be ASTM A193 Gr. B8 austenetic stainless steel instead of ASTM Al93 Gr. B7 carbon steel. The nuts were a mixture of carbon steel and austenetic stainless steel. This evaluation, with supporting calculations and analyses, assesses the use of the stainless steel for the subject fasteners and verifies that its use will have no adverse effects on the design parameters or operability of the SW system. Stress and corrosion of the stainless steel were also addressed and found to be acceptable. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-041)
 
. .
REFUELING INFORMATION
* DOCKET NO:
* 50-311 MONTH: APRIL 1995                                      UNIT NAME:        SALEM2 DATE:      05/10/95 COMPLETED BY:          R.HELLER TELEPHONE:          609-339-5162 MONTH: APRIL 1995
: 1. Refueling information has changed from last month: YES=NO            X
: 2. Scheduled date for next refueling: April 6, 1996 Scheduled date for restart following refueling: June 5, 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? April 1996
: 5. Scheduled date(s) for submitting proposed licensing action:  ---~NIA._ _ __
: 6. Important licensing considerations associated with refueling:
: 7. Number of Fuel Assemblies:
: 7. Number of Fuel 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 of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
: 8. Present licensed spent fuel storage capacity:                           1632 Future spent fuel storage capacity:                                     1632
8-1-7.R4 193 556 1632 1632 March 2012 
: 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:               March 2012 8-1-7.R4
'*
 
I * ... *
...
    '* *-~*
I *
                                    *
* SALEM GENERATING STATION MONTHLYOPERATING
* SALEM GENERATING STATION MONTHLYOPERATING


==SUMMARY==
==SUMMARY==
-UNIT 2 APRJL 1995 SALEM UNIT NO. 2 The Unit began the period operating at reduced power while investigation into problems with 22 Steam Generator Feed Pump (SGFP) controls continued.
-UNIT 2 APRJL 1995 SALEM UNIT NO. 2 The Unit began the period operating at reduced power while investigation into problems with 22 Steam Generator Feed Pump (SGFP) controls continued. The SGFP was returned to service and power was increased to 95% on April 1, 1995. State point data collection was completed on April 3, 1995, and power was increased to 99%. The Unit continued to operate at essentially full power throughout the remainder of the period.}}
The SGFP was returned to service and power was increased to 95% on April 1, 1995. State point data collection was completed on April 3, 1995, and power was increased to 99%. The Unit continued to operate at essentially full power throughout the remainder of the period.}}

Revision as of 10:14, 21 October 2019

Monthly Operating Rept for Apr 1995 for Salem Unit 2.W/ 950512 Ltr
ML18101A704
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/30/1995
From: Phillips R, Summers J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9505180213
Download: ML18101A704 (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 May 12, 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 April are being sent to you.

Sincerely yours,

~John C. Summers 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

(~--- -95o-sfao:i13

  • 950430* *-----.

PDR ADOC~ 05000311 I. R PDR

  • The power is in yow- hands.

95-2168 REV. 6/94

. "

.ERAGE DAILY UNIT POWER LE~

Docket No.: 50-311 Unit Name: Salem #2 Date: 05-10-95 Completed by: Robert Phillips Telephone: 339-2735 Month April 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 878 17 1047 2 1033 18 1077 3 989 19 1090 4 1074 20 1101 5 1081 21 1055 6 1059 22 1094 7 1061 23 1108 8 1072 24 1070 9 1068 25 1089 10 1063 26 1086 11 1069 27 1117 12 1068 28 1130 13 1076 29 1015 14 1087 30 1096 15 1079 31 16 1101 P. 8.1-7 Rl

.,

  • "
  • OPERATING DATA REPORT
  • Docket No:

Date:

50-311 05/10/95 Completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period APRIL 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
11. Hours in Reporting Period 719 2879 118752
12. No. of Hrs. Rx. was Critical 719 1557.40 77172.62
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 719 1350.63 74318.55
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) . 2422168.8 3834614.4 184808398.6 Gross Elec. Energy Generated (MWH) 799620 1226450 77676458
18. Net Elec. Energy Gen. (MWH) 767911 1131135 73854679
19. Unit Service Factor 100 46.9 62.6
20. Unit Availability Factor 100 46.9 62.6
21. Unit Capacity Factor (using MDC Net) 96.6 35.5 56.2
22. Unit Capacity Factor (using DER Net) 95.8 35.2 55.8
23. Unit Forced Outage Rate 0 34.5 22.0
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

None.

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

N A.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1995 DOCKET NO. : ~5~0""'-~3~1~1=----

UN IT NAME: Salem #2 DATE: 5-10-95 ,

COMPLETED BY: Robert PH'il l i PS *,

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 2439 4-1-95 F 2.23 B 4 ------------ HB PUMP XX NUCLER STEAM GENERATOR FEEDPUMP # 21 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)

-'

  • DOCKET NO: 50-311 MONTH: APRIL 1995 UNIT NAME: SALEM2 DATE: 05/10/95 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. Deficiency Reports (DIR), Use-As-Is S-2-SW-MSE-0851 "Salem Unit 2 Service Water Chiller Condenser Recirc Piping Fastener Material" Rev. 0 - This evaluation address concerns relating to the use of potentially inappropriate bolting in the Salem Service Water System identified in Problem Report (PR) 951105025. Specifically, this evaluation deals with the flanged connections for No. 22 and 23 Chiller condenser Recirculation Pump Discharge Check Valves (22SW99 and 23 SW99) of Salem Unit No. 2.

The bolting used in these flanged connections was found to be ASTM A193 Gr. B8 austenetic stainless steel instead of ASTM Al93 Gr. B7 carbon steel. The nuts were a mixture of carbon steel and austenetic stainless steel. This evaluation, with supporting calculations and analyses, assesses the use of the stainless steel for the subject fasteners and verifies that its use will have no adverse effects on the design parameters or operability of the SW system. Stress and corrosion of the stainless steel were also addressed and found to be acceptable. There is no reduction in the margin of safety as defined in the bases for any Technical Specification. (SORC 95-041)

. .

REFUELING INFORMATION

  • DOCKET NO:
  • 50-311 MONTH: APRIL 1995 UNIT NAME: SALEM2 DATE: 05/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH: APRIL 1995
1. Refueling information has changed from last month: YES=NO X
2. Scheduled date for next refueling: April 6, 1996 Scheduled date for restart following refueling: June 5, 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? April 1996

5. Scheduled date(s) for submitting proposed licensing action: ---~NIA._ _ __
6. Important licensing considerations associated with refueling:
7. Number of Fuel 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 of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March 2012 8-1-7.R4

...

'* *-~*

I *

  • SALEM GENERATING STATION MONTHLYOPERATING

SUMMARY

-UNIT 2 APRJL 1995 SALEM UNIT NO. 2 The Unit began the period operating at reduced power while investigation into problems with 22 Steam Generator Feed Pump (SGFP) controls continued. The SGFP was returned to service and power was increased to 95% on April 1, 1995. State point data collection was completed on April 3, 1995, and power was increased to 99%. The Unit continued to operate at essentially full power throughout the remainder of the period.

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