ML18093B028: Difference between revisions

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=Text=
=Text=
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* AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month JULY 1988 Day Average Daily Power Level (MWe-NET) 1 1095 --*---------
* AVERAGE DAILY UNIT POWER LEVEL Docket No.
2 1102 -3 1099 4 1098 5 1090 ---------6 1113 7 10 82 8 1100 --------9 1084 --*---------
Unit Name 50-27 2
10 1090 ------------
                                                                    -saieffi#-1-*-----
11 10 83 12 1083 ------------**---
Date          *s - 4:. 8a Completed by        Pell White                      Telephone 6cr9::93-5___  6_0_oo-*
13 1108 --**---------
Extension 4451 Month      JULY 1988 Day Average Daily Power Level                Day Average Daily Power Level (MWe-NET)                                    (MWe-NET) 1        1095                                    17          1074
14 1077 15 10 61 16 1097 --*--P. 8.1-7 Rl Day Docket No. Unit Name Date Telephone Extension 50-27 2 -saieffi#-1
      --*---------
-*-----*s -4:. 8a 6cr9::93-5
2        1102
___ 6_0 _o o-* 4451 Average Daily Power Level (MWe-NET) 17 1074 18 1087 19 1060 20 1071 21 1080 22 1082 23 1074 24 1086 25 1080 26 1090 27 1044 -*------28 1088 29 1066 30 1051 31 1067
            -
. ' *
18          1087 3        1099                                    19          1060 4        1098                                    20          1071 5        1090                                   21          1080
* OPERATING DATA REPORT Docket No .50-272 Date:
      ---------
Completed by Pell White Telephone:
6        1113                                    22          1082 7        10 82
935-6000 Extension:
      -----*-~*
Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period July 1988 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)ll49 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A
23          1074 8    - - 1100
: 9. Power Level to Which Restricted, if any (Net MWe) N/A
          ------
: 10. Reasons for Restrictions, if any N/A This Month 11. Hours in Reporting Period 744 12. No. of Hrs. Reactor was Critical 744 13. Reactor Reserve Shutdown Hrs. 0 14. Hours Generator On-Line
24          1086 9        1084
: 15. Unit Reserve Shutdown Hours 0 16. Gross Thermal Energy Generated  
      --*---------
------(MWH) 2541662.4
25          1080 10       1090
: 17. Gross Elec. Energy Generated (MWH) 839880 18. Net Elec. Energy Generated (MWH) 805491 19. Unit Service Factor 100 2 0. Unit Availability Factor 100 21. Unit Capacity Factor (using MDC Net) 97.9 22. Unit Capacity Factor (using DER Net) 97 .1 2 3. Unit Forced Outage Rate 0 Year to Date 5111 3423.3 0 33 49. 2 0 11292842.8 3778840 3601183 65.6 65.6 63.7 63.2 1.1 Cumulative 97200 6112735 0 59140.9 0 18 3561851. 6 60973330 57997392 60.8 60.8 53.9 53.5 23 *. 2 24. Shutdowns scheduled over next 6 months (type, date and duration of each) N/A 25. If shutdown at end of Report Period, Estimated Date of Startup: N/A 8-l-7.R2 Completed by No. Date N/A 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1988 D o c ke t No . 5 0 -2 7 2 Unit Name Date Telephone Extension Salem No.1 Pell White Type 1 Duration Hours Reason 2 Method of Shutting Down Reactor License Event Report 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Code 4 3 Method 1-Manual Component Code 5 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther August 4, 1988 609-935-6000 44 51 ** Cause and Corrective Action to Prevent Recurrence 4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
      ------------
* 5 Exhibit 1 Salem as Source
26          1090 11        10 83                                  27
* PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO IDENTIFICATION 870401046 870602041 870708038 880120046 880208141 1 lA SWG 97 FAILURE DESCRIPTION:
                                                        - * - 1044
NOT ATTACHED TO PIPE PLEASE REPAIR. 1 11 S.W.P. FAILURE DESCRIPTION:
                                                              -----
HANGER MISSING. REPLACE HANGER. 1 12CCHX FAILURE DESCRIPTION:
12        1083
HAS NO FLOW IN AUTO/CORRECT.
      ------  ------**---
HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT. 1 13SW24 FAILURE DESCRIPTION:
28          1088 13        1108                                    29          1066
DAMAGE VALVE BODY/REPLACE/MK.
      --**---------
NO. M-114 1 1S27C FAILURE DESCRIPTION:
14        1077                                    30           1051 15        10 61                                  31           1067 16        1097
HOLE IN PIPE BEFORE 15SW274/REPAIR.  
      --*--
-------* -, *
P. 8.1-7 Rl
* WO NO 880428101 880526040 880613104 880620078 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1 11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:
 
INOPERABLE/REPLACE.
    .'
1 lB DIESEL FAILURE DESCRIPTION:
* OPERATING DATA REPORT
LINE TO TURBO./LEAK/REWORK.
* Docket No .50-272 Date: 8--~4--~8~8...---~~~-
THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO. 1 1ABV15 FAILURE DESCRIPTION:
Telephone: 935-6000 Completed by      Pell White                          Extension: ~4~4~5~1,..--~~~~~~
SUPPLY REG/BLOWING AIR/REPLACE.
Operating Status
1 lRlB FAILURE DESCRIPTION:
: 1. Unit Name                         Salem No. 1       Notes
MONITOR IN WARN/INVESTIGATE AND REPAIR. .! 880705143
: 2. Reporting Period                 July 1988
* 1 1CC71 FAILURE DESCRIPTION:
: 3. Licensed Thermal Power (MWt)               3411
LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT.
: 4. Nameplate Rating (Gross MWe)               1170
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880718085 880718121 880727080 900714001 1 lC D-G FAILURE DESCRIPTION:
: 5. Design Electrical Rating (Net MWe)         1115
TURBO AIR COMP/NOT STARTING/TROUBLESHOOT.
: 6. Maximum Dependable Capacity(Gross MWe)ll49
1 1R41A FAILURE DESCRIPTION:
: 7. Maximum Dependable Capacity (Net MWe) 1106
PLNT VNT PART RAD MONITOR IS FAILED. TROUBLESHOOT/REWORK.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason     N/A
1 14 LOOP FAILURE DESCRIPTION:
                          ~~-~~~~-~~~~~~~~~--~~~--~-~-~
14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH. 1 12 S.W. PUMP FAILURE DESCRIPTION:
: 9. Power Level to Which Restricted, if any (Net MWe)               N/A
INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP. * *
                                                              ----~~~-~~-~
* MAJOR PLANT MODIFICATIONS REPORT MONTH JULY 1988 *OCR NO. lEC-1181 lEC-2188 lSM-0091 lSM-0472 PRINCIPAL SYSTEM Radiation Monitoring Service Water PASS Air Regulator Component Cooling
: 10. Reasons for Restrictions, if any       N/A
* DCR -Design Change Request
                                        ~~~~~~--~~~-~~~-~~-~~
* DOCKET NO.: 50-272 UNIT NAME:
This Month       Year to Date    Cumulative
DA TE : --A U9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE:
: 11. Hours in Reporting Period               744           5111            97200
609/339-4455 DESCRIPTION This modification added five high range main steam line monitors.
: 12. No. of Hrs. Reactor was Critical         744           3423.3          6112735
The monitors are qualified for post-accident operation.
: 13. Reactor Reserve Shutdown Hrs.             0                0                0
This modification installed a "cross type" vortex breaker beneath the bellmouth of No. 16 Service Water Pump to inhibit cavitation.
: 14. Hours Generator On-Line             ~--=7~4~4,,_---    33 49. 2        59140.9
This modification replaced the instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident.
: 15. Unit Reserve Shutdown Hours               0                0               0
This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump.
: 16. Gross Thermal Energy Generated     ------
*
(MWH)                         2541662.4       11292842.8      18 3561851. 6
* MAJOR PLANT MODIFICATIONS REPORT MONTH JULY 1988 DOCKET NO. 50-272 UNIT NAME:  
: 17. Gross Elec. Energy Generated (MWH)                         839880           3778840        60973330
*DCR lEC-1181 lEC-2188 lSM-0091 lSM-0472 DATE: August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:
: 18. Net Elec. Energy Generated (MWH)       805491           3601183        57997392
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 -------This modification added monitors to detect any possible activity in the Main Steam lines. 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.
: 19. Unit Service Factor                       100             65.6          60.8 2 0. Unit Availability Factor                 100             65.6          60.8
The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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.
: 21. Unit Capacity Factor (using MDC Net)                     97.9             63.7            53.9
The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed.
: 22. Unit Capacity Factor (using DER Net)                     97 .1           63.2            53.5 2 3. Unit Forced Outage Rate                     0               1.1          23 *. 2
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.
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients.
N/A
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.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
* DCR -Design Change Request SALEM UNIT NO. 1 *
N/A 8-l-7.R2
 
UNIT SHUTDOWN AND POWER REDUCTIONS      D o c ke t No . 5 0 - 2 7 2
                                                                                        ~~~~~~~~~
REPORT MONTH JULY 1988                  Unit Name Salem No.1 Date          August 4, 1988 Completed by Pell White                                                  Telephone 609-935-6000 Extension 44 51
                                                                                                              **
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 N/A
* 1              2 Reason                                3 Method              4 Exhibit G          5 Exhibit 1 F: Forced        A-Equipment Failure-explain            1-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 F-Administrative G-Operational Error-explain H-Other-explain 5-Load Reduction 9-0ther Event Report (LER) File (NUREG 0161)
* PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG
                                                                                            -,
SALEM UNIT 1 WO NO  ~~~-U_N_I_T~-E~QUIPMENT IDENTIFICATION 870401046 1  lA SWG 97 FAILURE DESCRIPTION:  NOT ATTACHED TO PIPE PLEASE REPAIR.
870602041 1  11 S.W.P.
FAILURE DESCRIPTION:  HANGER MISSING. REPLACE HANGER.
* 870708038 1   12CCHX FAILURE DESCRIPTION: HAS NO FLOW IN AUTO/CORRECT. HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT.
880120046 1  13SW24 880208141 1
FAILURE DESCRIPTION:
1S27C DAMAGE VALVE BODY/REPLACE/MK. NO. M-114
* FAILURE DESCRIPTION: HOLE IN PIPE BEFORE 15SW274/REPAIR.
                                  -------*
 
SALEM UNIT 1 WO NO     UNIT  EQUIPMENT IDENTIFICATION 880428101 1   11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: INOPERABLE/REPLACE.
880526040 1   lB DIESEL FAILURE DESCRIPTION: LINE TO TURBO./LEAK/REWORK. THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO.
                                                                                    .!
880613104 1   1ABV15 FAILURE DESCRIPTION: SUPPLY REG/BLOWING AIR/REPLACE.
880620078 1   lRlB FAILURE DESCRIPTION: MONITOR IN WARN/INVESTIGATE AND REPAIR.
880705143
* 1   1CC71 FAILURE DESCRIPTION: LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT.
 
SALEM UNIT 1 WO NO      UNIT  EQUIPMENT IDENTIFICATION
      -------~
880718085 1   lC D-G FAILURE DESCRIPTION: TURBO AIR COMP/NOT STARTING/TROUBLESHOOT.
880718121
* 1   1R41A FAILURE DESCRIPTION: PLNT VNT PART RAD MONITOR IS FAILED.
TROUBLESHOOT/REWORK.
880727080 1   14 LOOP FAILURE DESCRIPTION: 14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH.
900714001 1   12 S.W. PUMP FAILURE DESCRIPTION: INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP.
                                                                                      *
* MAJOR PLANT MODIFICATIONS
* DOCKET NO.:    50-272 REPORT MONTH   JULY 1988           UNIT NAME:      -S-a~l-e-m--1------
DA TE : --AU9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE:   609/339-4455
*OCR NO.        PRINCIPAL SYSTEM      DESCRIPTION lEC-1181          Radiation          This modification added five Monitoring          high range main steam line monitors. The monitors are qualified for post-accident operation.
lEC-2188          Service Water      This modification installed a "cross type" vortex breaker beneath the bellmouth of No.
16 Service Water Pump to inhibit cavitation.
lSM-0091          PASS Air            This modification replaced the Regulator          instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident.
lSM-0472          Component Cooling  This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump.
* DCR - Design Change Request
 
                *
* MAJOR PLANT MODIFICATIONS         DOCKET NO. 50-272 REPORT MONTH JULY 1988            UNIT NAME:   Sa~l-e_m__,1=--------
DATE:   August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:   609/339-4455
    *DCR
            - - - -SAFETY
                    - - - EVALUATION 10 CFR 50.59 lEC-1181            This modification added monitors to detect any possible activity in the Main Steam lines. 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.
lEC-2188            The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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.
lSM-0091            The addition of this new regulator   will allow the PASS System to operate at accident   temperatures as it was originally designed. 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.
lSM-0472            This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients. 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.
* DCR - Design Change Request
 
                  *
* SALEM GENERATING STATION MONTHLY OPERATING  
* SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT NO. 1 JULY 1988 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation.
  - UNIT NO. 1 JULY 1988 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation.
.. ' *
 
* REFUELING INFORMATION DOCKET NO.: COMPLETED BY: J. Ronafalvy UNIT NAME: 50-272 Salem 1 DATE: TELEPHONE:
.. '
EXTENSION:
                        *
August 10, 19 88 609/935-6000 4497 Month JULY 1988 1. Refueling information has changed from last month: YES NO X -----2. Scheduled date for next refueling:
* REFUELING INFORMATION DOCKET NO.:   50-272 COMPLETED BY:       J. Ronafalvy           UNIT NAME: Salem 1 DATE: August 10, 19 88 TELEPHONE:  609/935-6000 EXTENSION:  4497 Month   JULY 1988
April 15, 1989 3. Scheduled date for restart following refueling:
: 1. Refueling information has changed from last month:
May 30, 1989 4. A) B) Will Technical Specification changes or other license amendments be required?
YES               NO     X
YES NO ----NOT DETERMINED TO DATE X Has the reload fuel design been reviewed by the Station Operating Review Committee?
                                                  -----
YES NO X If no, when is it scheduled?
: 2. Scheduled date for next refueling:       April 15, 1989
February 1989 5. Scheduled date(s) for submitting proposed licensing action:
: 3. Scheduled date for restart following refueling: May 30, 1989
if required 6. Important licensing considerations associated with refueling:
: 4. A)   Will Technical Specification changes or other license amendments be required?
NONE 7. Number of Fuel Assemblies:
YES --~
A) Inc ore B) In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:
NO - - - -
Future spent fuel storage capacity:
NOT DETERMINED TO DATE     X B)    Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 9. Date of last refueling that can be discharged to spent fuel pool assuming the present 19 3 464 1170 1170 licensed capacity:
YES           NO     X If no, when is it scheduled? February 1989
_September 2001 8-l-7.R4
: 5. Scheduled date(s) for submitting proposed licensing action:
-1. *
                            -~-February if required
* 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  
: 6. Important licensing considerations associated with refueling:
NONE
: 7. Number of Fuel Assemblies:
A)   Inc ore                                             19 3 B)   In Spent Fuel Storage                               464
: 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:                                 _September 2001 8-l-7.R4
 
-1.
OPS~G
* Public Service Electric and Gas Company P.O. Box E
* Hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555


==Dear Sir:==
==Dear Sir:==
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 August 10, 1988 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 July 1988 are being sent to you. RH:sl 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. Pii::-1: 9 . General Manager -Salem Operations 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 ' \ 95-2189 (11 M) 12-84}}
 
MONTHLY OPERATING REPORT SALEM NO. 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 reports for the month of July 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. Pii::-1: 9.
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 95-2189 (11 M) 12-84}}

Revision as of 12:29, 21 October 2019

Monthly Operating Rept for Jul 1988 for Salem Unit 1. W/880810 Ltr
ML18093B028
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/31/1988
From: Ronafalvy J, White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8808220217
Download: ML18093B028 (11)
v • d • e


Text

  • AVERAGE DAILY UNIT POWER LEVEL Docket No.

Unit Name 50-27 2

-saieffi#-1-*-----

Date *s - 4:. 8a Completed by Pell White Telephone 6cr9::93-5___ 6_0_oo-*

Extension 4451 Month JULY 1988 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1095 17 1074

--*---------

2 1102

-

18 1087 3 1099 19 1060 4 1098 20 1071 5 1090 21 1080

6 1113 22 1082 7 10 82

*-~*

23 1074 8 - - 1100

24 1086 9 1084

--*---------

25 1080 10 1090

26 1090 11 10 83 27

- * - 1044

12 1083

------**---

28 1088 13 1108 29 1066

--**---------

14 1077 30 1051 15 10 61 31 1067 16 1097

--*--

P. 8.1-7 Rl

.'

  • OPERATING DATA REPORT
  • Docket No .50-272 Date: 8--~4--~8~8...---~~~-

Telephone: 935-6000 Completed by Pell White Extension: ~4~4~5~1,..--~~~~~~

Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period July 1988
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)ll49
7. Maximum Dependable Capacity (Net MWe) 1106
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 Cumulative

11. Hours in Reporting Period 744 5111 97200
12. No. of Hrs. Reactor was Critical 744 3423.3 6112735
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line ~--=7~4~4,,_--- 33 49. 2 59140.9
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated ------

(MWH) 2541662.4 11292842.8 18 3561851. 6

17. Gross Elec. Energy Generated (MWH) 839880 3778840 60973330
18. Net Elec. Energy Generated (MWH) 805491 3601183 57997392
19. Unit Service Factor 100 65.6 60.8 2 0. Unit Availability Factor 100 65.6 60.8
21. Unit Capacity Factor (using MDC Net) 97.9 63.7 53.9
22. Unit Capacity Factor (using DER Net) 97 .1 63.2 53.5 2 3. Unit Forced Outage Rate 0 1.1 23 *. 2
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A

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

N/A 8-l-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS D o c ke t No . 5 0 - 2 7 2

~~~~~~~~~

REPORT MONTH JULY 1988 Unit Name Salem No.1 Date August 4, 1988 Completed by Pell White Telephone 609-935-6000 Extension 44 51

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 N/A

  • 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-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 F-Administrative G-Operational Error-explain H-Other-explain 5-Load Reduction 9-0ther Event Report (LER) File (NUREG 0161)
  • PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG

-,

SALEM UNIT 1 WO NO ~~~-U_N_I_T~-E~QUIPMENT IDENTIFICATION 870401046 1 lA SWG 97 FAILURE DESCRIPTION: NOT ATTACHED TO PIPE PLEASE REPAIR.

870602041 1 11 S.W.P.

FAILURE DESCRIPTION: HANGER MISSING. REPLACE HANGER.

  • 870708038 1 12CCHX FAILURE DESCRIPTION: HAS NO FLOW IN AUTO/CORRECT. HAS NO FLOW WHEN TEMP CONTROLLER REACHES SET POINT.

880120046 1 13SW24 880208141 1

FAILURE DESCRIPTION:

1S27C DAMAGE VALVE BODY/REPLACE/MK. NO. M-114

  • FAILURE DESCRIPTION: HOLE IN PIPE BEFORE 15SW274/REPAIR.

*

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880428101 1 11 WASTE GAS COMPRESSOR FAILURE DESCRIPTION: INOPERABLE/REPLACE.

880526040 1 lB DIESEL FAILURE DESCRIPTION: LINE TO TURBO./LEAK/REWORK. THERE IS A LEAK ON THE 1/2" COOLING LINE TO THE TURBO.

.!

880613104 1 1ABV15 FAILURE DESCRIPTION: SUPPLY REG/BLOWING AIR/REPLACE.

880620078 1 lRlB FAILURE DESCRIPTION: MONITOR IN WARN/INVESTIGATE AND REPAIR.

880705143

  • 1 1CC71 FAILURE DESCRIPTION: LTDWN CTL VLV/NOT CONTROLLING/TROUBLESHOOT.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION

~

880718085 1 lC D-G FAILURE DESCRIPTION: TURBO AIR COMP/NOT STARTING/TROUBLESHOOT.

880718121

  • 1 1R41A FAILURE DESCRIPTION: PLNT VNT PART RAD MONITOR IS FAILED.

TROUBLESHOOT/REWORK.

880727080 1 14 LOOP FAILURE DESCRIPTION: 14 REACTOR COOLANT LOOP T AVE/DELTA T HAS FAILED HIGH.

900714001 1 12 S.W. PUMP FAILURE DESCRIPTION: INSP./PULL AND REPLACE WITH SPARE. PULL 12 SERVICE WTR PUMP AND INSTALL REBUILT PUMP.

  • MAJOR PLANT MODIFICATIONS
  • DOCKET NO.: 50-272 REPORT MONTH JULY 1988 UNIT NAME: -S-a~l-e-m--1------

DA TE : --AU9: us t 10 I 19 8 8 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • OCR NO. PRINCIPAL SYSTEM DESCRIPTION lEC-1181 Radiation This modification added five Monitoring high range main steam line monitors. The monitors are qualified for post-accident operation.

lEC-2188 Service Water This modification installed a "cross type" vortex breaker beneath the bellmouth of No.

16 Service Water Pump to inhibit cavitation.

lSM-0091 PASS Air This modification replaced the Regulator instrument air regulating valves with valves better suited to the environmental conditions postulated to exist during an accident.

lSM-0472 Component Cooling This modification installed an OFF Delay Relay in the control circuitry of Valve 1CC131 to prevent closure of the valve due to the resulting pressure transient caused by starting a Service Water pump.

  • DCR - Design Change Request
  • MAJOR PLANT MODIFICATIONS DOCKET NO. 50-272 REPORT MONTH JULY 1988 UNIT NAME: Sa~l-e_m__,1=--------

DATE: August 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • DCR

- - - -SAFETY

- - - EVALUATION 10 CFR 50.59 lEC-1181 This modification added monitors to detect any possible activity in the Main Steam lines. 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.

lEC-2188 The vortex breaker is actually a flow guide which does not affect the quantity or quality of the Service Water flow beyond design. 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.

lSM-0091 The addition of this new regulator will allow the PASS System to operate at accident temperatures as it was originally designed. 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.

lSM-0472 This modification to the valve control circuitry enhanced the reliability of the system to withstand flow transients. 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.

  • DCR - Design Change Request
  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 JULY 1988 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at full power for the entire period. As of July 27, 1988, the Unit achieved 100 days of continuous operation.

.. '

  • REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 1 DATE: August 10, 19 88 TELEPHONE: 609/935-6000 EXTENSION: 4497 Month JULY 1988
1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: April 15, 1989
3. Scheduled date for restart following refueling: May 30, 1989
4. 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? February 1989

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

-~-February 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 464

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: _September 2001 8-l-7.R4

-1.

OPS~G

  • Public Service Electric and Gas Company P.O. Box E
  • Hancocks Bridge, New Jersey 08038 Salem Generating Station August 10, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 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 reports for the month of July 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. Pii::-1: 9.

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 95-2189 (11 M) 12-84

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