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| number = ML18093A943
| number = ML18093A943
| issue date = 06/30/1988
| issue date = 06/30/1988
| title = Monthly Operating Rept for June 1988 for Salem Unit 1. W/880713 Ltr
| title = Monthly Operating Rept for June 1988 for Salem Unit 1
| author name = White P, Zupko J
| author name = White P, Zupko J
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:..,
{{#Wiki_filter:.
AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name  Salem ff 1 Date        July 10, 1988 Completed by     Pell White                       Telephone 609-935-6000 Extension 4451 Month     JUNE 1988 Day Average Daily Power Level              Day Average Daily Power Level (MWe-NET)                                (MWe-NET) 1         10 66                               17        1094 2         1102                                 18        1100 3         1082                                 19        1093 4         972                                 20        1122 5         1089                                 21        1075 6         1102                                 22        1100 7         1108                                 23        1085 8         1110                                 24        1075 9         1111                                 25        1116 10       1106                                 26        1063 11       11 20                               27        1039 12       1086                                 28        1103 13       1109                                 29        1101 14       1120                                 30        1090 15       10 96                               31 16       1096 P. 8.1-7 Rl
AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month JUNE 1988 Day Average Daily Power Level (MWe-NET) 1 10 66 2
1102 3
1082 4
972 5
1089 6
1102 7
1108 8
1110 9
1111 10 1106 11 11 20 12 1086 13 1109 14 1120 15 10 96 16 1096 P. 8.1-7 Rl Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 1094 18 1100 19 1093 20 1122 21 1075 22 1100 23 1085 24 1075 25 1116 26 1063 27 1039 28 1103 29 1101 30 1090 31 50-272 Salem ff 1 July 10, 1988 609-935-6000 4451 Power Level


      '                    e OPERATING DATA REPORT Docket No .50-272 Date: ~J~u~l~y~l.,....,....u-,--.1~9~9~9...-~
Completed by e
Telephone: 935-6000 Completed by        Pell White                        Extension: ~4~4-5~1~~~~~~~
OPERATING DATA REPORT Pell White Operating Status Docket No.50-272 Date:  
Operating Status
~J~u~l~y~l.,....,....u-,--.1~9~9~9...-~
: 1. Unit Name                         Salem No. 1       Notes
Telephone: 935-6000 Extension: ~4~4-5~1~~~~~~~
: 2. Reporting Period                   June 1988
: 1.
: 3. Licensed Thermal Power (MWt)               3411
Unit Name Salem No. 1 Notes
: 4. Nameplate Rating (Gross MWe)               1170
: 2.
: 5. Design Electrical Rating (Net MWe)         1115
Reporting Period June 1988
: 6. Maximum Dependable Capacity(Gross MWe)ll49
: 3.
: 7. Maximum Dependable Capacity (Net MWe) 1106
Licensed Thermal Power (MWt) 3411
: 8.     If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason       N/A
: 4.
                              ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
Nameplate Rating (Gross MWe) 1170
: 9. Power Level to Which Restricted, if any (Net MWe)               N/A
: 5.
                                                                ~~~--'--~~~~~~~~
Design Electrical Rating (Net MWe) 1115
: 10. Reasons for Restrictions, if any           N/A
: 6.
                                            ~---'~~~~~~~~~~~~~~~~~~~~
Maximum Dependable Capacity(Gross MWe)ll49
This Month     Year to Date               Cumulative 1 1. Hours in Reporting Period               720           4367                       96456
: 7.
: 12. No. of Hrs. Reactor was Critical         72 0         26 88. 3                   60383.4
Maximum Dependable Capacity (Net MWe) 1106
: 13. Reactor Reserve Shutdown Hrs.             0               u                             0
: 8.
: 14. Hours Generator On-Line                   720           26 05. 2                   58396.9 15
If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A  
* Unit Reserve Shutdown Hours               0               0                             0
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
: 16. Gross Thermal Energy Gen era ted (MWH)                         2445290.4       8751180.4               181020189.2 1 7. Gross Elec. Energy Generated (MWH)                           818230         2938960                   60133450 1 8. Net Elec. Energy Generated (MWH)         785534         2795692                   57191901
: 9.
: 19. Unit Service Factor                         100             59.7                       60.5
Power Level to Which Restricted, if any (Net MWe)
: 20. Unit Availability Factor                     100             59.7                       60.5
N/A  
: 21. Unit Capacity Factor (using MDC Net)                     98. 6           57.9                       53.6
~~~--'--~~~~~~~~
: 22. Unit Capacity Factor (using DER Net)                     97. 8           57.4                       53.2 2 3. Unit Forced Outage Rate                       0               1.4                       23.4
: 10. Reasons for Restrictions, if any N/A  
: 24. Shutdowns scheduled over next 6 months       (type, date and duration of each)
~---'~~~~~~~~~~~~~~~~~~~~
This Month Year to Date Cumulative 1 1. Hours in Reporting Period 720 4367 96456
: 12. No. of Hrs. Reactor was Critical 72 0 26 88. 3 60383.4
: 13. Reactor Reserve Shutdown Hrs.
0 u
0
: 14. Hours Generator On-Line 720 26 05. 2 58396.9 1 5
* Unit Reserve Shutdown Hours 0
0 0
: 16. Gross Thermal Energy Gen era ted (MWH) 2445290.4 8751180.4 181020189.2 1 7. Gross Elec. Energy Generated (MWH) 818230 2938960 60133450 1 8. Net Elec. Energy Generated (MWH) 785534 2795692 57191901
: 19. Unit Service Factor 100 59.7 60.5
: 20. Unit Availability Factor 100 59.7 60.5
: 21. Unit Capacity Factor (using MDC Net)
: 98. 6 57.9 53.6
: 22. Unit Capacity Factor (using DER Net)
: 97. 8 57.4 53.2 2 3. Unit Forced Outage Rate 0
1.4 23.4
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A
N/A
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/ A 8-l-7.R2
N/ A 8-l-7.R2  


UNIT SHUTDOWN AND POWER REDUCTIONS       Docket No.50-272
Completed by No.
                                                                                      ~~~~~~~~-
Date 0106 6-26-88 1
REPORT MONTH JUNE 1988                  Unit Name Salem No.l Date      July 10, 198'8 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    Rep art Code 4    Code 5      Prevent Recurrence Hope Creek Power 0106  6-26-88  F        6.3      A        5                EA                    Feed to Circulators 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                       5-Load Reduction    Event Report G-Operational Error-explain           9-0ther            (LER) File H-Other-explain                                           (NUREG 0161)
F: Forced S: Scheduled Pell White Duration Type Hours 1
F 6.3 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1988 Method of Shutting Reason Down 2
Reactor A
5 License Event Rep art System Code 4 EA Docket No.50-272  
~~~~~~~~-
Unit Name Date Telephone Extension Salem No.l July 10, 198'8 609-935-6000 44 51 Component Code 5 Cause and Corrective Action to Prevent Recurrence Hope Creek Power Feed to Circulators 2 Reason 3 Method 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source 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 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther


MAJOR PLANT MODIFICATIONS           DOCKET NO.: 50-272 REPORT MONTH    JUNE 1988            UNIT NAME:   *-=s-a__,,l_e_m____,1:--------
MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1988
DATE:     July 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:   609/339-4455
*OCR NO.
  *OCR NO.        PRINCIPAL SYSTEM      DESCRIPTION lSM-0283          Fire Protection    This modification replaced the automatic transfer switch for fire pump control.
PRINCIPAL SYSTEM lSM-0283 Fire Protection lSM-0350 Containment Spray lSM-0351 Boiler Feed
lSM-0350          Containment Spray  This modification installed drain valves on the Contain-ment side of Valves 11 & 12 CS48 to allow draining of the valve bodies for leak rate testing.
~ DCR - Design Change Request DOCKET NO.:
lSM-0351          Boiler Feed        This modification replaced the spools on Valves 12 & 14 BF19 due to the original counter-bore machining encroaching upon the minimum wall thickness.
50-272 UNIT NAME:  
~  DCR - Design Change Request
*-=s-a__,,l_e_m____,1:--------
DATE:
July 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:
609/339-4455 DESCRIPTION This modification replaced the automatic transfer switch for fire pump control.
This modification installed drain valves on the Contain-ment side of Valves 11 & 12 CS48 to allow draining of the valve bodies for leak rate testing.
This modification replaced the spools on Valves 12 & 14 BF19 due to the original counter-bore machining encroaching upon the minimum wall thickness.  


MAJOR PLANT MODIFICATIONS         DOCKET NO. 50-272 REPORT MONTH JUNE 1988            UNIT NAME : Sal_e_m_..,1,_--------
MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1988 DOCKET NO.
DATE:   July 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455
50-272 UNIT NAME :
    *DCR          SAFETY EVALUATION 10 CFR 50.59 lSM-0283            This modification does not change the design basis or normal operation of the fire pump automatic transfer switch. The replacement switch is different due to the original being obsolete.
Sal_e_m_..,1,_--------
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 lSM-0283 lSM-0350 lSM-0531 DATE:
lSM-0350            The addition of drain valves to the downstream side of Valves 11 & 12 CS48 allow draining of the lines for Type "C" Testing. System and component operations have not been affected. This modifi-cation did not alter any plant process or dis-charge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
July 10, 1988 COMPLETED BY:
lSM-0531            The replacement of the spools ensured the spools continue to meet the required wall thickness. The replacement spools are made of a material with superior corrosion/erosion resistance to that of the original spools. This modification did not
J. Ronafalvy TELEPHONE:
* alter any plant process or discharge or affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This modification does not change the design basis or normal operation of the fire pump automatic transfer switch.
* DCR - Design Change Request
The replacement switch is different due to the original being obsolete.
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.
The addition of drain valves to the downstream side of Valves 11 & 12 CS48 allow draining of the lines for Type "C" Testing.
System and component operations have not been affected.
This modifi-cation did not alter any plant process or dis-charge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
The replacement of the spools ensured the spools continue to meet the required wall thickness.
The replacement spools are made of a material with superior corrosion/erosion resistance to that of the original spools.
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  


PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO    UNIT EQUIPMENT IDENTIFICATION 880119077 1   RX BYPASS BKR-A FAILURE DESCRIPTION: DOESN'T ALARM WHEN RACKED IN TROUBLESHOOT 880217114 1   RX TRIP BRK FAILURE DESCRIPTION: "B"P250 INPUT CIRCUT/TROUBLESHOOT AND REWORK.
WO NO 880119077 880217114 880405132 880416083 880602092 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
880405132 1   2CC19 6 FAILURE DESCRIPTION: PACKING LEAK/REPACK/ A-255.
RX BYPASS BKR-A FAILURE DESCRIPTION:
880416083 1   2C D/G PT VOLT ALARM FAILURE DESCRIPTION: ALARMED DURING RUN / TROUBLESHOOT.
DOESN'T ALARM WHEN RACKED IN TROUBLESHOOT 1
e 880602092 1   22 CHL WTR PUMP FAILURE DESCRIPTION: BEARINGS RUNNING HOT/REPLACE BEARINGS.
RX TRIP BRK FAILURE DESCRIPTION:  
"B"P250 INPUT CIRCUT/TROUBLESHOOT AND REWORK.
1 2CC19 6 FAILURE DESCRIPTION:
PACKING LEAK/REPACK/ A-255.
1 2C D/G PT VOLT ALARM FAILURE DESCRIPTION:
ALARMED DURING RUN / TROUBLESHOOT.
1 22 CHL WTR PUMP FAILURE DESCRIPTION:
BEARINGS RUNNING HOT/REPLACE BEARINGS.
e


SALEM UNIT 1 WO NO    UNIT EQUIPMENT IDENTIFICATION 880609079 1   22CV15 3 FAILURE DESCRIPTION: BONNET LEAKING/ REPLACE BONNET.
WO NO 880609079 880609116 880610045 880622078 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
880609116 1  21 DEBORATING DEMIN BED FAILURE DESCRIPTION:   21 DEBORATING DEMIN BED RESIN FOR eves TO BE SLUICED.
22CV15 3 1
880610045 1   22 BAT PUMP FAILURE DESCRIPTION: MECHANICAL SEAL LEAKING/ REWORK. FAILED MECHANCIAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.
FAILURE DESCRIPTION:
880622078 1   2C VITAL INSTRUMENT INVERTER FAILURE DESCRIPTION: FAILED / TROUBLESHOOT.
BONNET LEAKING/ REPLACE BONNET.
21 DEBORATING DEMIN BED FAILURE DESCRIPTION:
21 DEBORATING DEMIN BED RESIN FOR eves TO BE SLUICED.
1 22 BAT PUMP FAILURE DESCRIPTION:
MECHANICAL SEAL LEAKING/ REWORK.
FAILED MECHANCIAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.
1 2C VITAL INSTRUMENT INVERTER FAILURE DESCRIPTION:
FAILED / TROUBLESHOOT.  


~.
~.
SALEM GENERATING STATION MONTHLY OPERATING  
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
- UNIT NO. 1 JUNE 1988 SALEM UNIT NO. 1 The Unit began the period operating at 100% power and continued to operate at full power until June 3, 1988, When power was briefly reduced to 85% for repairs to a feedwater heater. The Unit was restored to full power on June 5, 1988, and continued to operate at full power until June 26, 1988, when load was briefly reduced to repair "hot spots" in the temporary 13KV power feed from Hope Creek to Salem. On June 27, 1988, the Unit was restored to full power and continued to operate at that level for the remainder of the period.
UNIT NO. 1 JUNE 1988 The Unit began the period operating at 100% power and continued to operate at full power until June 3, 1988, When power was briefly reduced to 85% for repairs to a feedwater heater.
The Unit was restored to full power on June 5, 1988, and continued to operate at full power until June 26, 1988, when load was briefly reduced to repair "hot spots" in the temporary 13KV power feed from Hope Creek to Salem.
On June 27, 1988, the Unit was restored to full power and continued to operate at that level for the remainder of the period.  


PEFUELING INFORMATION DOCKET NO.:   50-272 COMPLETED BY:       J. Ronafalvy           UNIT NAME: Salem 1 DATE: July 10, 19 88 TELEPHONE:   609/935-6000 EXTENSION: 4497 Month   JUNE 1988
PEFUELING INFORMATION DOCKET NO.:
: 1. Refueling information has changed from last month:
50-272 COMPLETED BY:
YES               NO     X
J. Ronafalvy UNIT NAME:
: 2. Scheduled date for next refueling:       April 15, 1989
Salem 1 DATE:
: 3. Scheduled date for restart following refueling: May 30, 1989
July 10, 19 88 TELEPHONE:
: 4. A)   Will Technical Specification changes or other license amendments be required?
609/935-6000 EXTENSION:
YES           NO NOT DETERMINED TO DATE     X B)   Has the reload fuel design been reviewed by the Station Operating Review Committee?
4497 Month JUNE 1988
YES           NO     X If no, when is it scheduled? February 1989
: 1.
: 5. Scheduled date(s) for submitting proposed licensing action:
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
February if required
: 6. Important licensing considerations associated with refueling:
: 6.
NONE 7 0   Number of Fuel Assemblies:
Important licensing considerations associated with refueling:
A)   Inc ore                                             193 B)   In Spent Fuel Storage                               464
7 0
: 8. Present licensed spent fuel storage capacity:             11 70 Future spent tuel storage capacity:                       1170
: 8.
: 9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:                                   September 2001 8-l-7.R4
: 9.
NONE Number of Fuel Assemblies:
A)
Inc ore B)
In Spent Fuel Storage Present licensed spent fuel storage capacity:
Future spent tuel storage capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-l-7.R4 193 464 11 70 1170 September 2001


CPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 13, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
CPS~G 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  


==Dear Sir:==
==Dear Sir:==
 
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 July 13, 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 June 1988 are being sent to you.
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 June 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. <l:: t:!f 9..
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. <l::t:!f9. .
General Manager -
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
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
__J}}
__J}}

Latest revision as of 03:57, 6 January 2025

Monthly Operating Rept for June 1988 for Salem Unit 1
ML18093A943
Person / Time
Site: Salem 
Issue date: 06/30/1988
From: White P, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8807180365
Download: ML18093A943 (10)


Text

.

AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month JUNE 1988 Day Average Daily Power Level (MWe-NET) 1 10 66 2

1102 3

1082 4

972 5

1089 6

1102 7

1108 8

1110 9

1111 10 1106 11 11 20 12 1086 13 1109 14 1120 15 10 96 16 1096 P. 8.1-7 Rl Day Docket No.

Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 1094 18 1100 19 1093 20 1122 21 1075 22 1100 23 1085 24 1075 25 1116 26 1063 27 1039 28 1103 29 1101 30 1090 31 50-272 Salem ff 1 July 10, 1988 609-935-6000 4451 Power Level

Completed by e

OPERATING DATA REPORT Pell White Operating Status Docket No.50-272 Date:

~J~u~l~y~l.,....,....u-,--.1~9~9~9...-~

Telephone: 935-6000 Extension: ~4~4-5~1~~~~~~~

1.

Unit Name Salem No. 1 Notes

2.

Reporting Period June 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 1 1. Hours in Reporting Period 720 4367 96456

12. No. of Hrs. Reactor was Critical 72 0 26 88. 3 60383.4
13. Reactor Reserve Shutdown Hrs.

0 u

0

14. Hours Generator On-Line 720 26 05. 2 58396.9 1 5
  • Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Gen era ted (MWH) 2445290.4 8751180.4 181020189.2 1 7. Gross Elec. Energy Generated (MWH) 818230 2938960 60133450 1 8. Net Elec. Energy Generated (MWH) 785534 2795692 57191901
19. Unit Service Factor 100 59.7 60.5
20. Unit Availability Factor 100 59.7 60.5
21. Unit Capacity Factor (using MDC Net)
98. 6 57.9 53.6
22. Unit Capacity Factor (using DER Net)
97. 8 57.4 53.2 2 3. Unit Forced Outage Rate 0

1.4 23.4

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 0106 6-26-88 1

F: Forced S: Scheduled Pell White Duration Type Hours 1

F 6.3 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1988 Method of Shutting Reason Down 2

Reactor A

5 License Event Rep art System Code 4 EA Docket No.50-272

~~~~~~~~-

Unit Name Date Telephone Extension Salem No.l July 10, 198'8 609-935-6000 44 51 Component Code 5 Cause and Corrective Action to Prevent Recurrence Hope Creek Power Feed to Circulators 2 Reason 3 Method 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source 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 1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther

MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1988

  • OCR NO.

PRINCIPAL SYSTEM lSM-0283 Fire Protection lSM-0350 Containment Spray lSM-0351 Boiler Feed

~ DCR - Design Change Request DOCKET NO.:

50-272 UNIT NAME:

  • -=s-a__,,l_e_m____,1:--------

DATE:

July 10, 1988 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 DESCRIPTION This modification replaced the automatic transfer switch for fire pump control.

This modification installed drain valves on the Contain-ment side of Valves 11 & 12 CS48 to allow draining of the valve bodies for leak rate testing.

This modification replaced the spools on Valves 12 & 14 BF19 due to the original counter-bore machining encroaching upon the minimum wall thickness.

MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1988 DOCKET NO.

50-272 UNIT NAME :

Sal_e_m_..,1,_--------

  • DCR lSM-0283 lSM-0350 lSM-0531 DATE:

July 10, 1988 COMPLETED BY:

J. Ronafalvy TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This modification does not change the design basis or normal operation of the fire pump automatic transfer switch.

The replacement switch is different due to the original being obsolete.

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.

The addition of drain valves to the downstream side of Valves 11 & 12 CS48 allow draining of the lines for Type "C" Testing.

System and component operations have not been affected.

This modifi-cation did not alter any plant process or dis-charge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

The replacement of the spools ensured the spools continue to meet the required wall thickness.

The replacement spools are made of a material with superior corrosion/erosion resistance to that of the original spools.

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

WO NO 880119077 880217114 880405132 880416083 880602092 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

RX BYPASS BKR-A FAILURE DESCRIPTION:

DOESN'T ALARM WHEN RACKED IN TROUBLESHOOT 1

RX TRIP BRK FAILURE DESCRIPTION:

"B"P250 INPUT CIRCUT/TROUBLESHOOT AND REWORK.

1 2CC19 6 FAILURE DESCRIPTION:

PACKING LEAK/REPACK/ A-255.

1 2C D/G PT VOLT ALARM FAILURE DESCRIPTION:

ALARMED DURING RUN / TROUBLESHOOT.

1 22 CHL WTR PUMP FAILURE DESCRIPTION:

BEARINGS RUNNING HOT/REPLACE BEARINGS.

e

WO NO 880609079 880609116 880610045 880622078 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1

22CV15 3 1

FAILURE DESCRIPTION:

BONNET LEAKING/ REPLACE BONNET.

21 DEBORATING DEMIN BED FAILURE DESCRIPTION:

21 DEBORATING DEMIN BED RESIN FOR eves TO BE SLUICED.

1 22 BAT PUMP FAILURE DESCRIPTION:

MECHANICAL SEAL LEAKING/ REWORK.

FAILED MECHANCIAL SEAL ON #22 BAT PUMP REPAIR/REPLACE.

1 2C VITAL INSTRUMENT INVERTER FAILURE DESCRIPTION:

FAILED / TROUBLESHOOT.

~.

SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT NO. 1 JUNE 1988 The Unit began the period operating at 100% power and continued to operate at full power until June 3, 1988, When power was briefly reduced to 85% for repairs to a feedwater heater.

The Unit was restored to full power on June 5, 1988, and continued to operate at full power until June 26, 1988, when load was briefly reduced to repair "hot spots" in the temporary 13KV power feed from Hope Creek to Salem.

On June 27, 1988, the Unit was restored to full power and continued to operate at that level for the remainder of the period.

PEFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

J. Ronafalvy UNIT NAME:

Salem 1 DATE:

July 10, 19 88 TELEPHONE:

609/935-6000 EXTENSION:

4497 Month JUNE 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:

7 0

8.
9.

NONE Number of Fuel Assemblies:

A)

Inc ore B)

In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent tuel storage capacity:

Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:

8-l-7.R4 193 464 11 70 1170 September 2001

CPS~G 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

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 July 13, 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 June 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. <l:: t:!f 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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