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=Text=
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{{#Wiki_filter:e AVERAGE DA, LY UN, T PafER IVEL Comp I eted by **::"*:.,Pe I I White Month *APRIL 1988 Day Average Daily . (MWe-NET) 1 1089 2 1072 3 1065 4 1088 5 1093 6 1094 7 1092 8 1096 9 1083 10 1091 ' ' 11 1090 l:l 1119 13 1104 " " 14 .. 1095 15 1074 16 1094-Pg. 8.1-7 Rl '8805200103 880430 PDR ADOCK 05000311 R DCD Power Level *. Docket Unit Name* Date Telephone Extension Day Average Daily (MWe-NET)
{{#Wiki_filter:e AVERAGE DA, LY UN, T PafER IVEL Docket No~      50-311 Unit Name*      Salem i 2 Date            Apri I 10, 1988 Comp I eted by **::"*:.,Pe I I White                           Telephone      609-935-6000 Extension 4451 Month         *APRIL 1988 Day Average Daily Power Level                        Day Average Daily Power Level
' . 17 1100 18 1095 19 1095 20 1110 21 684 22 0 23 0 24 924 25 1079 26 1100 27 1114 28 1097 29 1099 30 1091 31 . * .. 50-311 Salem i 2 Apri I 10, 1988 609-935-6000 4451 Power Level s *. ! *:. *=-c .. -.. 
                . (MWe-NET)                                          (MWe-NET) 1         1089                                         17          1100 2         1072                                         18          1095 3         1065                                         19          1095 4         1088                                         20          1110 5         1093                                         21            684 6         1094                                         22            0                    s
.. e 0PERATING DATA REPORT Docket No.' 50-311 Date Completed by -**Pell White Operating Status Telephone 935-6000 Extension 4451 -------1. 2. 3. 4. 5. 6. 7. 8. Unit Name Salem No. 2 Reporting Period April 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) II'1rr Design Electrical Rating (Net MWe) 11T3" Maxim'ilm Dependable Capacity(Gross Maximum Dependable Capacity (Net MWe) ITifO Notes If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________
                                                                                            *:. *=- *~
: 9. Power Level to Which Restricted, if any (Net MWe) N/A
7         1092                                         23            0              .... -
: 10. Reasons for Restrictions, if any N/A 11 .. 12. 13. 14. 15. 16. ' ' 17. 18. 19. 20. 21. 22. 23. 24. This Month Year to Date Hours in Reporting Period 719 No. of Hrs. Reactor was Critical 689.3 Reactor Reserve Shutdown Hrs. -.....,0 __ _ Hours Generator On-Line 664.04 Unit Reserve Shutdown Hours O Gross Thermal Energy Generated (MWH) 2249256 Gross Elec. Energy Generated (MWH) 750550 Net Elec. Energy Generated (MWH) 719576 Unit Service Factor 92.4 Unit Availability Factor 92.4 Factor ** (usingMDCNet) 90.5 Unit Capacity Factor 2903 28 73. 3 0 2844.34 0 9570418 3190410 3062440 98.o 98.o 95.4 57408 35236. 2 0 4126.14 0 55220939 34819940 33081818 59.4 59.4 52.1 (using DER Net) 89.8 94.6 51.7 Unit Forced Outage Rate Shutdowns scheduled over next Refuelin . Outa e Scheduled to 7. 6 2 29. 3 6 months (type, date and duration of each) be in 9-1-88 and lastin for 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-1-7.RZ Completed by No. Date 0078 4-21-BtS 0079 4-22-88 1 F: Forced S: Scheduled 1;. '. I'*' 1* : i!) *,; ***:*; 1 .. ,:. lltlIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1988 Uock.et No
c 8         1096                                         24            924 9         1083                                         25          1079 10         1091                                         26          1100
* Unit Name Date Telephone Extension
      ' 11
.)U-.ll 1 Salem No.2 Pell White ... *.
        '         1090                                         27          1114 l:l       1119                                         28        1097 13         1104                                         29        1099 1095                                          30          1091 14   .
*. . * .* :_ 'i: * :
15         1074                                         31 16       1094-Pg. 8.1-7 Rl
* 1 ...... ::,:
'8805200103 880430 PDR ADOCK 05000311 R                     DCD
* Method of Duration Shutting Type Hours Reason Down 1 F F 2 Reactor 22.7 A 3 32.27 A 3 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction License Event Report E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain
*"' System Code 4 CB CB 3 Method I-Manual Component Code 5 INSTRU HT EX CH 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther .. .. , ..
10 6 1988 60 -935-6 00 4451 Cause and Corrective Action to Prevent Recurrence REACTOR COOLANT FLOW INDICATION STEM GENERATOR LEVEL 4 t:xhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit Salem as Source e*
* WO NO 870609036 870713077 870729104 871016130 871202144 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2 23SW228 FAILURE DESCRIPTION:
REPLACE/ RESTORE LINE 1619 UPSTREAM 23SW228 TO ORIGINAL FORM 2 2MS219 FAILURE DESCRIPTION:
VALVE LEAKS THRU, CUT OUT VALVE AND REPLACE 2 22 AUX FEED PUMP FAILURE DESCRIPTION:
EXCESSIVE LEAKAGE 2 21 SERVICE WATER PUMP FAILURE DESCRIPTION:
DECLARED INOPERABLE DUE TO LOW FLOW. 2 23SW2 FAILURE DESCRIPTION:
LEAKING PAST ITS SEAT, REMOVE EXISTING VALVE & REPLACE. 
,.o SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880211069 2 21CV16 2 FAILURE DESCRIPTION:
LEAKING DIAPHRAM/REPLACE.
880216092 2 22 BAT PUMP FAILURE DESCRIPTION:
MECHANICAL SEAL LEAKING/REWORK FAILED MECHANICAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.
880307088 2 22SW133 FAILURE DESCRIPTION:
NO/FLOW/DISASSEMABLE
& INSPECT 880316078 2 2SJ300 FAILURE DESCRIPTION:
LEAK THROUGH/REMOVE INSULATION/FA-127. 


PLANT MODIFICATIONS REPORT MONTH APRIL 1988 *OCR NO. 2SC-13 23 2SM-00188A PRINCIPAL SYSTEM Containment Spray Service Water
e  0PERATING DATA REPORT Docket No.' 50-311 Date          -T-A-Er-i-*1.--.1~0~,-1-9-g-9 Telephone 935-6000 Completed by -**Pell White                              Extension 4451 Operating Status
* Design Change Request DOCKET NO.: 50-311 UNIT NAME: Salem 2 DATE: May 10,1988 COMPLETED BY: J. Ronatalvy TELEPHONE:
: 1. Unit Name                        Salem No. 2        Notes
609/339-4455 DESCRIPTION This modification installed drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing. This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve.
: 2. Reporting Period                April 1988
MAJOR PLANT MODIFIC,IONS REPORT MONTH -APRIL 1988 *DCR SAFETY EVALUATION 10 CFR 50.59 DOCJT NO: 50-272 UNIT NAME:
: 3. Licensed Thermal Power (MWt)                3411
DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE:
: 4. Nameplate Rating (Gross MWe)                II'1rr
(609)339-4455 2SC-1323 This design change did not increase the probability or consequences of an accident.
: 5. Design Electrical Rating (Net MWe)          11T3"
By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification.
: 6. Maxim'ilm Dependable Capacity(Gross MWe)~
This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
: 7. Maximum Dependable Capacity (Net MWe) ITifO
2SM-00188A This modification did not alter the original design of the system. The duo check valve is no longer manufactured by TRW but is now made by Clow. A review of the design specifications show that the new valve is identical in every way to the old one. This modification did not alter plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________~N~/~A~---------
* DCR -Design Change Request
: 9. Power Level to Which Restricted, if any (Net MWe)              N/A
-. ' ) . SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING  
                                                                -------------------------~
: 10. Reasons for Restrictions, if any          N/A
                                          ---------------------~--------------~
This Month        Year to Date            C~lative 11 .. Hours in Reporting Period              719            2903                57408
: 12. No. of Hrs. Reactor was Critical        689.3          28 73. 3              35236. 2
: 13. Reactor Reserve Shutdown Hrs.      -.....,0_ __            0                          0
: 14. Hours Generator On-Line                664.04        2844.34          4126.14
: 15. Unit Reserve Shutdown Hours              O                0                        0
: 16. Gross Thermal Energy Generated
' '            (MWH)                        2249256          9570418            55220939
: 17. Gross Elec. Energy Generated (MWH)                          750550        3190410            34819940
: 18. Net Elec. Energy Generated (MWH)        719576        3062440            33081818
: 19. Unit Service Factor                      92.4          98.o                    59.4
: 20. Unit Availability Factor                  92.4            98.o                  59.4
: 21. Unit~Capacity Factor
      ** (usingMDCNet)                          90.5          95.4                    52.1
: 22. Unit Capacity Factor (using DER Net)                      89.8          94.6                    51.7
: 23. Unit Forced Outage Rate                    7. 6            2                    29. 3
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refuelin . Outa e Scheduled to be in 9-1-88 and lastin for
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A 8-1-7.RZ
 
lltlIT SHUTDOWN AND POWER REDUCTIONS                                    Uock.et No * .)U-.ll 1 REPORT MONTH APRIL 1988                                               Unit Name Salem No.2 Date          A~ril 10 1988 Completed by                  Pell White                                                                                  Telephone 60 -935-6 600
                                                          ~.; ... *. ,*:~. *~!'    *.                                    Extension 4451
                                                            . *.* :_ 'i: *: *1......::,: ~
* Method of Duration            Shutting                          License                                Cause and Corrective No.        Date              Type    Hours  Reason        Down                            Event      System    Component              Action to 1                  2      Reactor                            Report Code 4            Code 5        Prevent Recurrence REACTOR COOLANT FLOW 0078    4-21-BtS              F      22.7    A                    3                                    CB          INSTRU        INDICATION STEM GENERATOR
* 0079    4-22-88                F      32.27    A                  3                                    CB          HT EXCH      LEVEL e*
1                                2 Reason                                                            3 Method                4                5 t:xhibit G        Exhibit F: Forced                          A-Equipment Failure-explain                                        I-Manual                Instructions      Salem as S: Scheduled                      B-Maintenance or Test                                              2-Manual Scram.          for Prepara-      Source C-Refueling                                                        3-Automatic Scram.      tion of Data D-Regulatory Restriction                                            4-Continuation of        Entry Sheets E-Operator Training & Licensing Exam                                  Previous Outage        for Licensee 1;.
I'*'      1*
F-Administrative                                                    5-Load Reduction        Event Report
: i!)            *,;      G-Operational Error-explain                                        9-0ther                  (LER) File
      ***:*; 1 .. , : .
H-Other-explain                                                                              (NUREG 0161)
 
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO    UNIT  EQUIPMENT IDENTIFICATION 870609036 2  23SW228 FAILURE DESCRIPTION:  REPLACE/ RESTORE LINE 1619 UPSTREAM 23SW228 TO ORIGINAL FORM 870713077 2  2MS219 FAILURE DESCRIPTION:  VALVE LEAKS THRU, CUT OUT VALVE AND REPLACE 870729104 2  22 AUX FEED PUMP FAILURE DESCRIPTION:  EXCESSIVE LEAKAGE 871016130 2  21 SERVICE WATER PUMP FAILURE DESCRIPTION:  DECLARED INOPERABLE DUE TO LOW FLOW.
871202144 2  23SW2 FAILURE DESCRIPTION:  LEAKING PAST ITS SEAT, REMOVE EXISTING VALVE &
REPLACE.
 
                                                                                            ,.o SALEM UNIT 2 WO NO    UNIT  EQUIPMENT IDENTIFICATION 880211069 2  21CV16 2 FAILURE DESCRIPTION:  LEAKING DIAPHRAM/REPLACE.
880216092 2  22 BAT PUMP FAILURE DESCRIPTION:  MECHANICAL SEAL LEAKING/REWORK FAILED MECHANICAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.
880307088 2  22SW133 FAILURE DESCRIPTION:  NO/FLOW/DISASSEMABLE & INSPECT 880316078 2  2SJ300 FAILURE DESCRIPTION:  LEAK THROUGH/REMOVE INSULATION/FA-127.
 
I~JOR PLANT MODIFICATIONS            DOCKET NO.: 50-311 REPORT MONTH APRIL 1988                UNIT NAME:   Salem 2 DATE:   May 10,1988 COMPLETED BY:   J. Ronatalvy TELEPHONE: 609/339-4455
  *OCR NO.        PRINCIPAL SYSTEM        DESCRIPTION 2SC-13 23            Containment        This modification installed Spray              drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing.
2SM-00188A          Service Water      This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve.
* Design Change Request
 
MAJOR PLANT MODIFIC,IONS                   DOCJT NO: 50-272 REPORT MONTH - APRIL 1988                  UNIT NAME: ~S-a~l-e-m~-2~--~~
DATE:       May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455
    *DCR  SAFETY EVALUATION 10 CFR 50.59 2SC-1323             This design change did not increase the probability or consequences of an accident. By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification. This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
2SM-00188A           This modification did not alter the original design of the system. The duo check valve is no longer manufactured by TRW but is now made by Clow. A review of the design specifications show that the new valve is identical in every way to the old one. This modification did not alter a~y plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
* DCR - Design Change Request
 
      ) .
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT NO. 2 APRIL 1988 The Unit began the period operating at 100% power and continued to operate at full power until April 21, 1988, when the Unit tripped due to a spike on a Reactor Coolant Pump flow transmitter during maintenance.
  - UNIT NO. 2 APRIL 1988 SALEM UNIT NO. 2 The Unit began the period operating at 100% power and continued to operate at full power until April 21, 1988, when the Unit tripped due to a spike on a Reactor Coolant Pump flow transmitter during maintenance. During startup, the Unit tripped due to a level spike on No. 23 Steam Generator caused by the EH Control System. Following repairs to the EH Control system, startup was commenced with the Unit achieving full power on April 24, 1988. The Unit continued to operate at full power for the remainder of the period. The primary to secondary leak rate calculation for Nos. 22 and 24 Steam Generators continues to indicate less than ten gallons per day.
During startup, the Unit tripped due to a level spike on No. 23 Steam Generator caused by the EH Control System. Following repairs to the EH Control system, startup was commenced with the Unit achieving full power on April 24, 1988. The Unit continued to operate at full power for the remainder of the period. The primary to secondary leak rate calculation for Nos. 22 and 24 Steam Generators continues to indicate less than ten gallons per day.
 
REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: J. Ronafalvy DATE: Max 10, 1988 TELEPHONE:
REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY:     J. Ronafalvy                     DATE: Max 10, 1988 TELEPHONE: 609)935-6000 EXTENSION --,.4~4=5=5~~~~~~-
609)935-6000 EXTENSION Month APRIL 1988 1. Refueling information has changed from last month: YES NO X 2. Scheduled date for next refueling:
Month   APRIL 1988
September 3, 1988 3. Scheduled date for restart following refueling:
: 1. Refueling information has changed from last month:
November 2,1988 4. A) Will Technical Specification changes or other license amendments be required?
YES             NO   X
YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 2. Scheduled date for next refueling:         September 3, 1988
YES NO X If no, when is it scheduled?
: 3. Scheduled date for restart following refueling: November 2,1988
August, 1988 5. Scheduled date(s) for submitting proposed licensing action: August 1988 if required 6. Important licensing considerations associated with refueling:
: 4. A)   Will Technical Specification changes or other license amendments be required?
: 7. 8. 9. NONE Number of Fuel Assemblies:
YES           NO   X B)   Has the reload fuel design been reviewed by the Station Operating Review Committee?
A) Inc ore B) In Spent Fuel Storage Present licensed spent fuel storage capacity:
YES             NO   X If no, when is it scheduled?     August, 1988
Future spent fuel storage capacity:
: 5. Scheduled date(s) for submitting proposed licensing action:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
August 1988 if required
8-l-7.R4 19 3 224 1170 1170 March 2003 
: 6. Important licensing considerations associated with refueling:
NONE
: 7. Number of Fuel Assemblies:
A)   Inc ore                                               19 3 B)   In Spent Fuel Storage                                 224
: 8. Present licensed spent fuel storage capacity:               1170 Future spent fuel storage capacity:                         1170
: 9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:                                       March 2003 8-l-7.R4


Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555  
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 14, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555


==Dear Sir:==
==Dear Sir:==
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 May 14, 1988 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of April 1988 are being sent to you. Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, J. M. Zupko, Jr. General Manager -Salem Operations RH:sl cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 The Energy People /,z,4. j.Y I, \* 95-2189 (11 M) 12-84}}
 
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of April 1988 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, r~y-J. M. Zupko, Jr.
General Manager - Salem Operations RH:sl cc:       Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4
                                                                                    /,z,4.
j.Y I, The Energy People                                                                        \*
95-2189 (11 M) 12-84}}

Latest revision as of 07:43, 3 February 2020

Monthly Operating Rept for Apr 1988.W/880514 Ltr
ML18093A833
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/30/1988
From: Ronafalvy J, White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805200103
Download: ML18093A833 (10)
v • d • e


Text

e AVERAGE DA, LY UN, T PafER IVEL Docket No~ 50-311 Unit Name* Salem i 2 Date Apri I 10, 1988 Comp I eted by **::"*:.,Pe I I White Telephone 609-935-6000 Extension 4451 Month *APRIL 1988 Day Average Daily Power Level Day Average Daily Power Level

. (MWe-NET) (MWe-NET) 1 1089 17 1100 2 1072 18 1095 3 1065 19 1095 4 1088 20 1110 5 1093 21 684 6 1094 22 0 s

  • . *=- *~

7 1092 23 0 .... -

c 8 1096 24 924 9 1083 25 1079 10 1091 26 1100

' 11

' 1090 27 1114 l:l 1119 28 1097 13 1104 29 1099 1095 30 1091 14 .

15 1074 31 16 1094-Pg. 8.1-7 Rl

'8805200103 880430 PDR ADOCK 05000311 R DCD

e 0PERATING DATA REPORT Docket No.' 50-311 Date -T-A-Er-i-*1.--.1~0~,-1-9-g-9 Telephone 935-6000 Completed by -**Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period April 1988
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) II'1rr
5. Design Electrical Rating (Net MWe) 11T3"
6. Maxim'ilm Dependable Capacity(Gross MWe)~
7. Maximum Dependable Capacity (Net MWe) ITifO
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason ___________________~N~/~A~---------
9. Power Level to Which Restricted, if any (Net MWe) N/A

~

10. Reasons for Restrictions, if any N/A

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

This Month Year to Date C~lative 11 .. Hours in Reporting Period 719 2903 57408

12. No. of Hrs. Reactor was Critical 689.3 28 73. 3 35236. 2
13. Reactor Reserve Shutdown Hrs. -.....,0_ __ 0 0
14. Hours Generator On-Line 664.04 2844.34 4126.14
15. Unit Reserve Shutdown Hours O 0 0
16. Gross Thermal Energy Generated

' ' (MWH) 2249256 9570418 55220939

17. Gross Elec. Energy Generated (MWH) 750550 3190410 34819940
18. Net Elec. Energy Generated (MWH) 719576 3062440 33081818
19. Unit Service Factor 92.4 98.o 59.4
20. Unit Availability Factor 92.4 98.o 59.4
21. Unit~Capacity Factor
    • (usingMDCNet) 90.5 95.4 52.1
22. Unit Capacity Factor (using DER Net) 89.8 94.6 51.7
23. Unit Forced Outage Rate 7. 6 2 29. 3
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refuelin . Outa e Scheduled to be in 9-1-88 and lastin for

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

N/A 8-1-7.RZ

lltlIT SHUTDOWN AND POWER REDUCTIONS Uock.et No * .)U-.ll 1 REPORT MONTH APRIL 1988 Unit Name Salem No.2 Date A~ril 10 1988 Completed by Pell White Telephone 60 -935-6 600

~.; ... *. ,*:~. *~!' *. Extension 4451

. *.* :_ 'i: *: *1......::,: ~

  • Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence REACTOR COOLANT FLOW 0078 4-21-BtS F 22.7 A 3 CB INSTRU INDICATION STEM GENERATOR
  • 0079 4-22-88 F 32.27 A 3 CB HT EXCH LEVEL e*

1 2 Reason 3 Method 4 5 t:xhibit G Exhibit F: Forced A-Equipment Failure-explain I-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Refueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee 1;.

I'*' 1*

F-Administrative 5-Load Reduction Event Report

i!) *,; G-Operational Error-explain 9-0ther (LER) File
        • 1 .. ,
          .

H-Other-explain (NUREG 0161)

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 870609036 2 23SW228 FAILURE DESCRIPTION: REPLACE/ RESTORE LINE 1619 UPSTREAM 23SW228 TO ORIGINAL FORM 870713077 2 2MS219 FAILURE DESCRIPTION: VALVE LEAKS THRU, CUT OUT VALVE AND REPLACE 870729104 2 22 AUX FEED PUMP FAILURE DESCRIPTION: EXCESSIVE LEAKAGE 871016130 2 21 SERVICE WATER PUMP FAILURE DESCRIPTION: DECLARED INOPERABLE DUE TO LOW FLOW.

871202144 2 23SW2 FAILURE DESCRIPTION: LEAKING PAST ITS SEAT, REMOVE EXISTING VALVE &

REPLACE.

,.o SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880211069 2 21CV16 2 FAILURE DESCRIPTION: LEAKING DIAPHRAM/REPLACE.

880216092 2 22 BAT PUMP FAILURE DESCRIPTION: MECHANICAL SEAL LEAKING/REWORK FAILED MECHANICAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.

880307088 2 22SW133 FAILURE DESCRIPTION: NO/FLOW/DISASSEMABLE & INSPECT 880316078 2 2SJ300 FAILURE DESCRIPTION: LEAK THROUGH/REMOVE INSULATION/FA-127.

I~JOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH APRIL 1988 UNIT NAME: Salem 2 DATE: May 10,1988 COMPLETED BY: J. Ronatalvy TELEPHONE: 609/339-4455

  • OCR NO. PRINCIPAL SYSTEM DESCRIPTION 2SC-13 23 Containment This modification installed Spray drain valves on the Containment side of 21CS48 and 22CS48 to allow draining of valve bodies for leak rate testing. These valves have been added to the Technical specification requirement for leak rate testing.

2SM-00188A Service Water This design change replaced Valve 22SW99. As there were 4" mission duo check valve available, this valve was replace with a 4" Clow duo check valve.

  • Design Change Request

MAJOR PLANT MODIFIC,IONS DOCJT NO: 50-272 REPORT MONTH - APRIL 1988 UNIT NAME: ~S-a~l-e-m~-2~--~~

DATE: May 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455

  • DCR SAFETY EVALUATION 10 CFR 50.59 2SC-1323 This design change did not increase the probability or consequences of an accident. By allowing the testing of 21 & 22CS48 Valves, this design change increases safety by furthering Containment integrity verification. This modification did not alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

2SM-00188A This modification did not alter the original design of the system. The duo check valve is no longer manufactured by TRW but is now made by Clow. A review of the design specifications show that the new valve is identical in every way to the old one. This modification did not alter a~y plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request

) .

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 APRIL 1988 SALEM UNIT NO. 2 The Unit began the period operating at 100% power and continued to operate at full power until April 21, 1988, when the Unit tripped due to a spike on a Reactor Coolant Pump flow transmitter during maintenance. During startup, the Unit tripped due to a level spike on No. 23 Steam Generator caused by the EH Control System. Following repairs to the EH Control system, startup was commenced with the Unit achieving full power on April 24, 1988. The Unit continued to operate at full power for the remainder of the period. The primary to secondary leak rate calculation for Nos. 22 and 24 Steam Generators continues to indicate less than ten gallons per day.

REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: J. Ronafalvy DATE: Max 10, 1988 TELEPHONE: 609)935-6000 EXTENSION --,.4~4=5=5~~~~~~-

Month APRIL 1988

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 3, 1988
3. Scheduled date for restart following refueling: November 2,1988
4. A) Will Technical Specification changes or other license amendments be required?

YES NO X B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? August, 1988

5. Scheduled date(s) for submitting proposed licensing action:

August 1988 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Inc ore 19 3 B) In Spent Fuel Storage 224

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: March 2003 8-l-7.R4

OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 14, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of April 1988 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, r~y-J. M. Zupko, Jr.

General Manager - Salem Operations RH:sl cc: Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4

/,z,4.

j.Y I, The Energy People \*

95-2189 (11 M) 12-84

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