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                      . AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name   Salem # 2 Date     Jan. 10,1985 Completed by   J. P. Ronafalvy                           Telephone 609-935-6000 Extension   4455 Month     December 1984 Day Average Daily Power Level               Day Average Daily Power Level (MWe-NET)                                 (MWe-NET) 1         0                                 17         0 2         0                                 18         0 3         0                                 19         0 4         0                                 20         0 5         0                                 21         0 6         0                                 22         0 7         0                                 23         0 8         0                                 24         0
AVERAGE DAILY UNIT POWER LEVEL Docket No.
: 9.         0                                 25         0 10         0                                 26         0 11         0                                 27         0 12..       0                                 28         0 13         0                                 29         0 14         0                                 30         0 15         0                                 31         0 16         0
50-311 Unit Name Salem # 2 Date Jan. 10,1985 Completed by J.
  .Pg. 8,1-7 R1 8501170247 841231 PDR ADOCK-05000311 R               PDR III
P.
Ronafalvy Telephone 609-935-6000 Extension 4455 Month December 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9.
0 25 0
10 0
26 0
11 0
27 0
12..
0 28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
.Pg. 8,1-7 R1 8501170247 841231 PDR ADOCK-05000311 R
PDR III


OPERATING DATA REPORT Docket No. 50-311 Date Jan. 10,1985 Telephone   935-6000 Completed by   J. P. Ronafalvy                   Extension   4455 Operating Status
OPERATING DATA REPORT Docket No. 50-311 Date Jan. 10,1985 Telephone 935-6000 Completed by J.
: 1. Unit Name                       Salem No. 2   Notes
P.
: 2. Reporting Period               December 1984
Ronafalvy Extension 4455 Operating Status 1.
: 3. Licensed Thermal Power (MWt)             3411
Unit Name Salem No. 2 Notes 2.
: 4. Nameplate Rating (Gross MWe)             1162
Reporting Period December 1984 3.
: 5. Design Electrical Rating (Net MWe)       1115
Licensed Thermal Power (MWt) 3411 4.
: 6. Maximum Dependable Capacity (Gross MWe)1149                                 i
Nameplate Rating (Gross MWe) 1162 5.
: 7. Maximum Dependable Capacity (Net MWe) 1106
Design Electrical Rating (Net MWe) 1115 6.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A
Maximum Dependable Capacity (Gross MWe)1149 i
: 9. Power Level to Which Restricted, if any (Net MWe)         N/A
7.
: 10. Reasons for Restrictions, if any                 N/A This Month Year to Date     Cumulative
Maximum Dependable Capacity (Net MWe) 1106 8.
: 11. Hours in Reporting Period             744         8784             28225
If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A 9.
: 12. No. of Hrs. Reactor was Critical       0         3386.0           15094.6
Power Level to Which Restricted, if any (Net MWe)
: 13. Reactor Reserve Shutdown Hrs.           0         1442.9             3533.6
N/A
: 14. Hours Generator On-Line                 0         3194.8           14612.1
: 10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
: 15. Unit Reserve Shutdown Hours             0             0                 0
: 11. Hours in Reporting Period 744 8784 28225
: 16. Gross Thermal Energy Generated (M103)                         0       10255964       43727036
: 12. No. of Hrs. Reactor was Critical 0
: 17. Gross Elec. Energy Generated (MWH)                         0         3409360       14277650
3386.0 15094.6
: 18. Net Elec. Energy Generated (MWH)     (2965)       3200588       13517836
: 13. Reactor Reserve Shutdown Hrs.
: 19. Unit Service Factor                     0             36.4             51.8
0 1442.9 3533.6
: 20. Unit Availability Factor               0             36.4             51.8
: 14. Hours Generator On-Line 0
: 21. Unit Capacity Factor (using MDC Net)                   0             32.9             43.3
3194.8 14612.1
: 22. Unit Capacity Factor (using DER Net)                   0             32.7             43.0
: 15. Unit Reserve Shutdown Hours 0
: 23. Unit Forced Outage Rate                 0             56.6             37.1
0 0
: 16. Gross Thermal Energy Generated (M103) 0 10255964 43727036
: 17. Gross Elec. Energy Generated (MWH) 0 3409360 14277650
: 18. Net Elec. Energy Generated (MWH)
(2965) 3200588 13517836
: 19. Unit Service Factor 0
36.4 51.8
: 20. Unit Availability Factor 0
36.4 51.8
: 21. Unit Capacity Factor (using MDC Net) 0 32.9 43.3
: 22. Unit Capacity Factor (using DER Net) 0 32.7 43.0
: 23. Unit Forced Outage Rate 0
56.6 37.1
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
: 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:
4-1-85
4-1-85
: 26. Units in Test Status (Prior to Commercial Operation) :
: 26. Units in Test Status (Prior to Commercial Operation) :
Forecast       Achieved Initial Criticality     6/30/80       8/2/80 Initial Electricity     9/1/80         6/3/81 Commercial Operation     9/24/80       10/13/81 8-1-7.R2
Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81 8-1-7.R2


UNIT SHUTDOWN AND POWER REDUCTIONS         Docket No. 50-311 REPORT MONTH-December 1984-                 Unit Name- Salem No.2         '
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH-December 1984-Unit Name-Salem No.2 Date Jan. 10,1985 Completed by J.P.
Date       Jan. 10,1985 Completed by       J.P. Ronafalvy                                                   Telephone   609-935-6000 Extension   4455 Method of Duration           Shutting License                         Cause and Corrective Action to No.       Date     Type     Hours   Reason   Down     Event   System   Component 1                 2     Reactor   Report Code 4     Code 5       Prevent Recurrence Generator Major Overhaul HA     GENERA 84-302     11-03     F       744       A         4         -                                                .
Ronafalvy Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No.
Major Turbine TURBIN     Overhaul 84-302     11-03'     S       744       A         4         -        HA Misc. Major           -
Date Type Hours Reason Down Event System Component Action to 1
.84-302     11-03     S       744       B         4         -        HC    HTEXCH      Condenser Overhaul 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-Other             (LER) File H-Other-explain           ,
2 Reactor Report Code 4 Code 5 Prevent Recurrence Generator Major HA GENERA Overhaul 84-302 11-03 F
(NUREG 0161)
744 A
4 Major Turbine HA TURBIN Overhaul 84-302 11-03' S
744 A
4 Misc. Major HC HTEXCH Condenser Overhaul
.84-302 11-03 S
744 B
4 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-Other (LER) File H-Other-explain (NUREG 0161)


MAJOR PLANT MODIFICATIONS                 DOCKET NO.:   50-311 REPORT MONTH DECEMBER 1984                 UNIT NAME:   Salem 2 DATE: January 10, 1984 COMPLETED BY:   J. Ronafalvy TELEPHONE:   609/935-6000 X4455
MAJOR PLANT MODIFICATIONS DOCKET NO.:
            *DCR NO.           PRINCIPLE SYSTEM                 SUBJECT 2EC-1566       Chilled Water           Install a 10 psig relief valve at the chilled water expansion tank.
50-311 REPORT MONTH DECEMBER 1984 UNIT NAME:
2EC-1733       Waste Disposal-Liquid   Replace existing impeller, coupling set and motor on No.
Salem 2 DATE:
January 10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/935-6000 X4455
*DCR NO.
PRINCIPLE SYSTEM SUBJECT 2EC-1566 Chilled Water Install a 10 psig relief valve at the chilled water expansion tank.
2EC-1733 Waste Disposal-Liquid Replace existing impeller, coupling set and motor on No.
2 Waste Evaporator Feed Pump with upgraded components.
2 Waste Evaporator Feed Pump with upgraded components.
2EC-1944       Cables and 28VDC         Replace existing 2C #14 cable (2BDE7A-ET) with a new cable so that the original. cable manufactured by AIW, can be tested for E.Q. Replaced cable should be qualified cable.
2EC-1944 Cables and 28VDC Replace existing 2C #14 cable (2BDE7A-ET) with a new cable so that the original. cable manufactured by AIW, can be tested for E.Q.
2EC-1957       Pressurizer System       Modify control circuit to 2PR6 and 2PR7 valves.
Replaced cable should be qualified cable.
2EC-1963       Service Water           Position No. 24 Service Water Motor (Allis Chalmers) has failed and is being replaced with a spare (GE) motor.
2EC-1957 Pressurizer System Modify control circuit to 2PR6 and 2PR7 valves.
2EC-1998       Steam Generator Feed     Provide inspection openings Pumps                   on both north and south side o f the No. 22 Steam Generator feed baseplate.
2EC-1963 Service Water Position No. 24 Service Water Motor (Allis Chalmers) has failed and is being replaced with a spare (GE) motor.
            -2SC-0483       Chilled Water           Change shaft sleeve material
2EC-1998 Steam Generator Feed Provide inspection openings Pumps on both north and south side o f the No. 22 Steam Generator feed baseplate.
(#22 Chiller.cond.     from stainless steel- (316) to Recirc Pump only)       monel.
-2SC-0483 Chilled Water Change shaft sleeve material
2FC-1162       24 RCP Motor             Replace #24 RCP motor rotor resistance rings with new-improved design.
(#22 Chiller.cond.
* Design Change Request
from stainless steel- (316) to Recirc Pump only) monel.
2FC-1162 24 RCP Motor Replace #24 RCP motor rotor resistance rings with new-improved design.
Design Change Request


MAJOR PLANT MODIFICATIONS                                                 DOCKET NO.: 50-311 REPORT MONTH DECEMBER 1984                                                   UNIT NAME: Salem 2 DATE: January 10, 1984 COMPLETED BY:                                                                         J. Ronafalvy TELEPHONE:                                                               609/339-4455 DCR NO.                   10CFR 50.59                                     SAFETY EVALUATION 2EC-1566             This change does not jeopardize the pressure retaining boundary nor does it impact the operation / basic design of the Chilled Water System. No unreviewed safety or environmental questions are involved.
MAJOR PLANT MODIFICATIONS DOCKET NO.:
2EC-1733             This change to upgrade the Waste Evaporator Feed Pump capacity is consistent with the manufacturers rating tor maximum working pressure of the pump and design rating of the Liquid Waste Disposal System piping. No unreviewed safety or environmental questions are involved.
50-311 REPORT MONTH DECEMBER 1984 UNIT NAME: Salem 2 DATE:
2EC-1944             This change involves no potential for failures or malfunctions. No unreviewed safety or environmental questions are involved.
January 10, 1984 COMPLETED BY:
2EC-1957             This change involves enhancement of the valve operation and is in accordance with the manufacturers recommendation for valve movement. No unreviewed safety or environmental questions are involved.
J.
2EC-1963             This change involves hookup of non-safety related thermocouples.to the new motor. No unreviewed safety or environmental questions are involved.
Ronafalvy TELEPHONE:
2EC-1998             The modification to the baseplate of No. 22 Steam Generator Feed Pump does not affect any presently performed safety analysis nor does it create any new hazards. The basis for the Technical Specifications remains unchanged. No unreviewed safety or environmental questions are involved.
609/339-4455 DCR NO.
2SC-0483             The new shaft sleeves are designed to the same requirements as per the original pump design. The material change from stainless steel to monel does not affect'any presently' performed safety analysis nor does it create any new hazards. The basis for the Technical Specifications remains unchanged. No unreviewed safety or environmental questions are involved.
10CFR 50.59 SAFETY EVALUATION 2EC-1566 This change does not jeopardize the pressure retaining boundary nor does it impact the operation / basic design of the Chilled Water System.
2SC-1162             Implementation of this DCR does not add, delete, or alter any safety related equipment.                           No unreviewed                                                                                 safety or environmental questions are involved.
No unreviewed safety or environmental questions are involved.
* Design Change Request a
2EC-1733 This change to upgrade the Waste Evaporator Feed Pump capacity is consistent with the manufacturers rating tor maximum working pressure of the pump and design rating of the Liquid Waste Disposal System piping.
No unreviewed safety or environmental questions are involved.
2EC-1944 This change involves no potential for failures or malfunctions.
No unreviewed safety or environmental questions are involved.
2EC-1957 This change involves enhancement of the valve operation and is in accordance with the manufacturers recommendation for valve movement.
No unreviewed safety or environmental questions are involved.
2EC-1963 This change involves hookup of non-safety related thermocouples.to the new motor.
No unreviewed safety or environmental questions are involved.
2EC-1998 The modification to the baseplate of No. 22 Steam Generator Feed Pump does not affect any presently performed safety analysis nor does it create any new hazards.
The basis for the Technical Specifications remains unchanged.
No unreviewed safety or environmental questions are involved.
2SC-0483 The new shaft sleeves are designed to the same requirements as per the original pump design.
The material change from stainless steel to monel does not affect'any presently' performed safety analysis nor does it create any new hazards.
The basis for the Technical Specifications remains unchanged.
No unreviewed safety or environmental questions are involved.
2SC-1162 Implementation of this DCR does not add, delete, or alter any safety related equipment.
No unreviewed safety or environmental questions are involved.
Design Change Request a


PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO   DEPT   UNIT   EQUIPMENT IDENTIFICATION ~
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION ~
0099121204 SMD     2   VALVE 21SW22 FAILURE DESCRIPTION:   VALVE WILL NOT OPERATE MANUALLY CORRECTIVE. ACTION:   REPLACED BEVEL GEAR AND HANDWHEEL MECHANISM 84-12-19-009-2 SMD     2. NO.~22 BAT PUMP FAILURE DESCRIPTION: PUMP DOES NOT PUMP CORRECTIVE ACTION:   REPLACED DIAPHRAGM ON 21CV156 0099124696 SMD     2 . VALVE 22RH19 FAILURE DESCRIPTION: VALVE WILL NOT OPEN CORRECTIVE ACTION:   REPLACED OPERATE / RESET COIL ON CONTROL CIRCUIT 84-12-40-085-9 SMD. 2   2A VITAL BUS INVERTOR FAILURE DESCRIPTION: NO TRANSFER TO NORMAL FEED CORRECTIVE ACTION:   REPLACED K1, K2, AND K4 RELAY AND TIGHTENED LOOSE WIRE ON TP2-5 0099120861                       _
0099121204 SMD 2
        -SMD       2 W BE OIL COOLER FAILURE DESCRIPTION:   SERVICE WATER LEAK, CRACK ON WELD ON BELL CORRECTIVE ACTION:     CLEANED AND' REPAIRED WELD
VALVE 21SW22 FAILURE DESCRIPTION:
VALVE WILL NOT OPERATE MANUALLY CORRECTIVE. ACTION:
REPLACED BEVEL GEAR AND HANDWHEEL MECHANISM 84-12-19-009-2 SMD 2.
NO.~22 BAT PUMP FAILURE DESCRIPTION:
PUMP DOES NOT PUMP CORRECTIVE ACTION:
REPLACED DIAPHRAGM ON 21CV156 0099124696 SMD 2
. VALVE 22RH19 FAILURE DESCRIPTION:
VALVE WILL NOT OPEN CORRECTIVE ACTION:
REPLACED OPERATE / RESET COIL ON CONTROL CIRCUIT 84-12-40-085-9 SMD.
2 2A VITAL BUS INVERTOR FAILURE DESCRIPTION:
NO TRANSFER TO NORMAL FEED CORRECTIVE ACTION:
REPLACED K1, K2, AND K4 RELAY AND TIGHTENED LOOSE WIRE ON TP2-5 0099120861
-SMD 2
W BE OIL COOLER FAILURE DESCRIPTION:
SERVICE WATER LEAK, CRACK ON WELD ON BELL CORRECTIVE ACTION:
CLEANED AND' REPAIRED WELD


                            . . _ . .    - _ _ _ - - .-      .        .        -~     _ _ .            - _
-~
SALEM UNIT 2 WO NO '   DEPT     UNIT         EQUIPMENT IDENTIFICATION 84-11-06-001-2 SMD   2           2VC1 FAILURE DESCRIPTION: EXPANSION BOOT UPSTREAM OF VALVE HAS A RIP-IN-IT a
SALEM UNIT 2 WO NO '
CORRECTIVE ACTION:     REPLACED RUBBER EXPANSION JOINT                   .
DEPT UNIT EQUIPMENT IDENTIFICATION 84-11-06-001-2 SMD 2
84-11-17-011-0                                                                                             -
2VC1 FAILURE DESCRIPTION:
;                  SMD   2           2A EMERGENCY DIESEL
EXPANSION BOOT UPSTREAM OF VALVE HAS A RIP-IN-IT a
!                                      FAILURE DESCRIPTION:   THE LUBE OIL HEATER HAS FAILED AND CAUGHT ON FIRE I
CORRECTIVE ACTION:
CORRECTIVE ACTION:     LUBE OIL HEATER ELEMENT REPLACED; INSTALLED NEW LUBE OIL FLOW DEVICE
REPLACED RUBBER EXPANSION JOINT 84-11-17-011-0 SMD 2
2A EMERGENCY DIESEL FAILURE DESCRIPTION:
THE LUBE OIL HEATER HAS FAILED AND CAUGHT ON FIRE I
CORRECTIVE ACTION:
LUBE OIL HEATER ELEMENT REPLACED; INSTALLED NEW LUBE OIL FLOW DEVICE
]
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SALEM GENERATING STATION MONTHLY OPERATING  
SALEM GENERATING STATION MONTHLY OPERATING  
Line 104: Line 203:
  - UNIT NO. 2 DECEMBER 1984 The period began with the second refueling / turbine outage in progress.
  - UNIT NO. 2 DECEMBER 1984 The period began with the second refueling / turbine outage in progress.
Mode 6 (first Reactor Head stud detensioned) was entered on 12/14/84.
Mode 6 (first Reactor Head stud detensioned) was entered on 12/14/84.
Main Generator replacement work continues. The General Electric Generator was set in place two (2) days ahead of schedule. Turbine work is continuing. All lower and upper inner cylinders have been removed for reblading and the machining of sealing areas is in progress. Steam Generator eddy current work was completed. All secondary work on the Steam Generators was completed. No. 24 Steam Generator tube leak repair was completed. Reactor disassembly work was completed. All new fuel has been received and is in storage.
Main Generator replacement work continues.
The General Electric Generator was set in place two (2) days ahead of schedule.
Turbine work is continuing.
All lower and upper inner cylinders have been removed for reblading and the machining of sealing areas is in progress.
Steam Generator eddy current work was completed.
All secondary work on the Steam Generators was completed.
No. 24 Steam Generator tube leak repair was completed.
Reactor disassembly work was completed.
All new fuel has been received and is in storage.
Core unloading commenced on 12/22/84 and was completed on 12/30/84.
Core unloading commenced on 12/22/84 and was completed on 12/30/84.
Nos. 21 and 23 Reactor Coolant Pump (RCP) seal replacement has been completed. Type C leak rate testing of Containment Isolation Valves is in progress. No. 21 Service Water Header outage and No. 2A Vital Bus outage activities were completed. 2B Battery and 2C Battery cell replacement was initiated and completed. No. 21 Component Cooling Heat Exchanger tube inspections have been complete. A significant number of tube wall thinning was found. Selected retubing of No. 21 Component Cooling Heat Exchanger tubes was started. Approximately 1600 tubes will be replaced. MSR work waa started and is continuing.
Nos. 21 and 23 Reactor Coolant Pump (RCP) seal replacement has been completed.
Type C leak rate testing of Containment Isolation Valves is in progress.
No. 21 Service Water Header outage and No. 2A Vital Bus outage activities were completed.
2B Battery and 2C Battery cell replacement was initiated and completed.
No. 21 Component Cooling Heat Exchanger tube inspections have been complete.
A significant number of tube wall thinning was found.
Selected retubing of No. 21 Component Cooling Heat Exchanger tubes was started.
Approximately 1600 tubes will be replaced.
MSR work waa started and is continuing.


REFUELING INFORMATION DOCKET NO.:   50-311 COMPLETED BY:     J. Ronafalvy             UNIT NAME: Salem 2 DATE: January 10, 1985 TELEPHONE:   609/935-6000 EXTENSION: 4455 Month     December 1984
REFUELING INFORMATION DOCKET NO.:
: 1. Refueling information has changed from last month:
50-311 COMPLETED BY:
YES     X         NO
J.
: 2. Scheduled date for next refueling:       October 4, 1984
Ronafalvy UNIT NAME:
: 3. Scheduled date for restart following refueling:     April 1, 1985
Salem 2 DATE:
: 4. A)   Will Technical Specification changes or other license amendments be required?
January 10, 1985 TELEPHONE:
YES X*         NO B)   Has the reload fuel design been reviewed by the Station Operating Review Committee?
609/935-6000 EXTENSION:
YES   X         NO If no, when is it scheduled?       N/A
4455 Month December 1984 1.
: 5. Scheduled date (s) for submitting proposed licensing action:
Refueling information has changed from last month:
N/A
YES X
: 6. Important licensing considerations associated with refueling:
NO 2.
NONE
Scheduled date for next refueling:
: 7. Number of Fuel Assemblies:
October 4, 1984 3.
A)   Incore                                                   0 B)   In Spent Fuel Storage                                 265
Scheduled date for restart following refueling:
: 8. Present licensed spent fuel storage capacity:             1170 Future spent fuel storage capacity:                       1170
April 1, 1985 4.
: 9. Date of last refueling that can be discharged to spent fuel pool as'suming the'present licensed. capacity:                                     March 2004 8-1-7.R4
A)
* A request for Technical Specification change that is required for Salem 2 Cycle 3 operation was transmitted to the NRC in our letter dated 10/15/84.
Will Technical Specification changes or other license amendments be required?
YES X*
NO B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES X
NO If no, when is it scheduled?
N/A 5.
Scheduled date (s) for submitting proposed licensing action:
N/A 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 0
B)
In Spent Fuel Storage 265 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 as'suming the'present licensed. capacity:
March 2004 8-1-7.R4 A request for Technical Specification change that is required for Salem 2 Cycle 3 operation was transmitted to the NRC in our letter dated 10/15/84.


  ~
~
~
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
O PSEG
~
Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555


==Dear Sir:==
==Dear Sir:==
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of December 1984 are being sent to you.
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of December 1984 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Wo rk Orders Operating Summary Refueling Information Sincerely yours,
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related W rk Orders o
                                                                    /? 1l y ,
Operating Summary Refueling Information Sincerely yours,
e,2   .
/? 1l y, e,2 J. M.
J. M. Zupko, Jr.
Zupko, Jr.
General Manager - Salem Operations JR:sbh cc:       Dr. Thomas E. Murley Regional Administrator USNRC Region I                                                                                           (
General Manager - Salem Operations JR:sbh cc:
631 Park Avenue King of Prussia, PA 19406 Director, Office of. Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosure 8-1-7.R4 The Energy People fr> 2189 (20M) 1181
Dr. Thomas E. Murley Regional Administrator USNRC Region I
_ _.                    __J}}
(
631 Park Avenue King of Prussia, PA 19406 Director, Office of. Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosure 8-1-7.R4 The Energy People fr> 2189 (20M) 1181 J}}

Latest revision as of 00:38, 13 December 2024

Monthly Operating Rept for Dec 1984
ML20112H619
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/31/1984
From: Ronafalvy J, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8501170247
Download: ML20112H619 (10)
v • d • e


Text

AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-311 Unit Name Salem # 2 Date Jan. 10,1985 Completed by J.

P.

Ronafalvy Telephone 609-935-6000 Extension 4455 Month December 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9.

0 25 0

10 0

26 0

11 0

27 0

12..

0 28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

.Pg. 8,1-7 R1 8501170247 841231 PDR ADOCK-05000311 R

PDR III

OPERATING DATA REPORT Docket No. 50-311 Date Jan. 10,1985 Telephone 935-6000 Completed by J.

P.

Ronafalvy Extension 4455 Operating Status 1.

Unit Name Salem No. 2 Notes 2.

Reporting Period December 1984 3.

Licensed Thermal Power (MWt) 3411 4.

Nameplate Rating (Gross MWe) 1162 5.

Design Electrical Rating (Net MWe) 1115 6.

Maximum Dependable Capacity (Gross MWe)1149 i

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 8784 28225
12. No. of Hrs. Reactor was Critical 0

3386.0 15094.6

13. Reactor Reserve Shutdown Hrs.

0 1442.9 3533.6

14. Hours Generator On-Line 0

3194.8 14612.1

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (M103) 0 10255964 43727036
17. Gross Elec. Energy Generated (MWH) 0 3409360 14277650
18. Net Elec. Energy Generated (MWH)

(2965) 3200588 13517836

19. Unit Service Factor 0

36.4 51.8

20. Unit Availability Factor 0

36.4 51.8

21. Unit Capacity Factor (using MDC Net) 0 32.9 43.3
22. Unit Capacity Factor (using DER Net) 0 32.7 43.0
23. Unit Forced Outage Rate 0

56.6 37.1

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:

4-1-85

26. Units in Test Status (Prior to Commercial Operation) :

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH-December 1984-Unit Name-Salem No.2 Date Jan. 10,1985 Completed by J.P.

Ronafalvy Telephone 609-935-6000 Extension 4455 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 Generator Major HA GENERA Overhaul 84-302 11-03 F

744 A

4 Major Turbine HA TURBIN Overhaul 84-302 11-03' S

744 A

4 Misc. Major HC HTEXCH Condenser Overhaul

.84-302 11-03 S

744 B

4 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-Other (LER) File H-Other-explain (NUREG 0161)

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 REPORT MONTH DECEMBER 1984 UNIT NAME:

Salem 2 DATE:

January 10, 1984 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/935-6000 X4455

  • DCR NO.

PRINCIPLE SYSTEM SUBJECT 2EC-1566 Chilled Water Install a 10 psig relief valve at the chilled water expansion tank.

2EC-1733 Waste Disposal-Liquid Replace existing impeller, coupling set and motor on No.

2 Waste Evaporator Feed Pump with upgraded components.

2EC-1944 Cables and 28VDC Replace existing 2C #14 cable (2BDE7A-ET) with a new cable so that the original. cable manufactured by AIW, can be tested for E.Q.

Replaced cable should be qualified cable.

2EC-1957 Pressurizer System Modify control circuit to 2PR6 and 2PR7 valves.

2EC-1963 Service Water Position No. 24 Service Water Motor (Allis Chalmers) has failed and is being replaced with a spare (GE) motor.

2EC-1998 Steam Generator Feed Provide inspection openings Pumps on both north and south side o f the No. 22 Steam Generator feed baseplate.

-2SC-0483 Chilled Water Change shaft sleeve material

(#22 Chiller.cond.

from stainless steel- (316) to Recirc Pump only) monel.

2FC-1162 24 RCP Motor Replace #24 RCP motor rotor resistance rings with new-improved design.

Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 REPORT MONTH DECEMBER 1984 UNIT NAME: Salem 2 DATE:

January 10, 1984 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455 DCR NO.

10CFR 50.59 SAFETY EVALUATION 2EC-1566 This change does not jeopardize the pressure retaining boundary nor does it impact the operation / basic design of the Chilled Water System.

No unreviewed safety or environmental questions are involved.

2EC-1733 This change to upgrade the Waste Evaporator Feed Pump capacity is consistent with the manufacturers rating tor maximum working pressure of the pump and design rating of the Liquid Waste Disposal System piping.

No unreviewed safety or environmental questions are involved.

2EC-1944 This change involves no potential for failures or malfunctions.

No unreviewed safety or environmental questions are involved.

2EC-1957 This change involves enhancement of the valve operation and is in accordance with the manufacturers recommendation for valve movement.

No unreviewed safety or environmental questions are involved.

2EC-1963 This change involves hookup of non-safety related thermocouples.to the new motor.

No unreviewed safety or environmental questions are involved.

2EC-1998 The modification to the baseplate of No. 22 Steam Generator Feed Pump does not affect any presently performed safety analysis nor does it create any new hazards.

The basis for the Technical Specifications remains unchanged.

No unreviewed safety or environmental questions are involved.

2SC-0483 The new shaft sleeves are designed to the same requirements as per the original pump design.

The material change from stainless steel to monel does not affect'any presently' performed safety analysis nor does it create any new hazards.

The basis for the Technical Specifications remains unchanged.

No unreviewed safety or environmental questions are involved.

2SC-1162 Implementation of this DCR does not add, delete, or alter any safety related equipment.

No unreviewed safety or environmental questions are involved.

Design Change Request a

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION ~

0099121204 SMD 2

VALVE 21SW22 FAILURE DESCRIPTION:

VALVE WILL NOT OPERATE MANUALLY CORRECTIVE. ACTION:

REPLACED BEVEL GEAR AND HANDWHEEL MECHANISM 84-12-19-009-2 SMD 2.

NO.~22 BAT PUMP FAILURE DESCRIPTION:

PUMP DOES NOT PUMP CORRECTIVE ACTION:

REPLACED DIAPHRAGM ON 21CV156 0099124696 SMD 2

. VALVE 22RH19 FAILURE DESCRIPTION:

VALVE WILL NOT OPEN CORRECTIVE ACTION:

REPLACED OPERATE / RESET COIL ON CONTROL CIRCUIT 84-12-40-085-9 SMD.

2 2A VITAL BUS INVERTOR FAILURE DESCRIPTION:

NO TRANSFER TO NORMAL FEED CORRECTIVE ACTION:

REPLACED K1, K2, AND K4 RELAY AND TIGHTENED LOOSE WIRE ON TP2-5 0099120861

-SMD 2

W BE OIL COOLER FAILURE DESCRIPTION:

SERVICE WATER LEAK, CRACK ON WELD ON BELL CORRECTIVE ACTION:

CLEANED AND' REPAIRED WELD

-~

SALEM UNIT 2 WO NO '

DEPT UNIT EQUIPMENT IDENTIFICATION 84-11-06-001-2 SMD 2

2VC1 FAILURE DESCRIPTION:

EXPANSION BOOT UPSTREAM OF VALVE HAS A RIP-IN-IT a

CORRECTIVE ACTION:

REPLACED RUBBER EXPANSION JOINT 84-11-17-011-0 SMD 2

2A EMERGENCY DIESEL FAILURE DESCRIPTION:

THE LUBE OIL HEATER HAS FAILED AND CAUGHT ON FIRE I

CORRECTIVE ACTION:

LUBE OIL HEATER ELEMENT REPLACED; INSTALLED NEW LUBE OIL FLOW DEVICE

]

9 I

.I i

4 J

j i

4

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 DECEMBER 1984 The period began with the second refueling / turbine outage in progress.

Mode 6 (first Reactor Head stud detensioned) was entered on 12/14/84.

Main Generator replacement work continues.

The General Electric Generator was set in place two (2) days ahead of schedule.

Turbine work is continuing.

All lower and upper inner cylinders have been removed for reblading and the machining of sealing areas is in progress.

Steam Generator eddy current work was completed.

All secondary work on the Steam Generators was completed.

No. 24 Steam Generator tube leak repair was completed.

Reactor disassembly work was completed.

All new fuel has been received and is in storage.

Core unloading commenced on 12/22/84 and was completed on 12/30/84.

Nos. 21 and 23 Reactor Coolant Pump (RCP) seal replacement has been completed.

Type C leak rate testing of Containment Isolation Valves is in progress.

No. 21 Service Water Header outage and No. 2A Vital Bus outage activities were completed.

2B Battery and 2C Battery cell replacement was initiated and completed.

No. 21 Component Cooling Heat Exchanger tube inspections have been complete.

A significant number of tube wall thinning was found.

Selected retubing of No. 21 Component Cooling Heat Exchanger tubes was started.

Approximately 1600 tubes will be replaced.

MSR work waa started and is continuing.

REFUELING INFORMATION DOCKET NO.:

50-311 COMPLETED BY:

J.

Ronafalvy UNIT NAME:

Salem 2 DATE:

January 10, 1985 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month December 1984 1.

Refueling information has changed from last month:

YES X

NO 2.

Scheduled date for next refueling:

October 4, 1984 3.

Scheduled date for restart following refueling:

April 1, 1985 4.

A)

Will Technical Specification changes or other license amendments be required?

YES X*

NO B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES X

NO If no, when is it scheduled?

N/A 5.

Scheduled date (s) for submitting proposed licensing action:

N/A 6.

Important licensing considerations associated with refueling:

NONE 7.

Number of Fuel Assemblies:

A)

Incore 0

B)

In Spent Fuel Storage 265 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 as'suming the'present licensed. capacity:

March 2004 8-1-7.R4 A request for Technical Specification change that is required for Salem 2 Cycle 3 operation was transmitted to the NRC in our letter dated 10/15/84.

~

O PSEG

~

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of December 1984 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related W rk Orders o

Operating Summary Refueling Information Sincerely yours,

/? 1l y, e,2 J. M.

Zupko, Jr.

General Manager - Salem Operations JR:sbh cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I

(

631 Park Avenue King of Prussia, PA 19406 Director, Office of. Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosure 8-1-7.R4 The Energy People fr> 2189 (20M) 1181 J

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