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AVERAGE DAIL.Y UNIT POWER LEVEL-Docket No. 50-311 Unit Name Salem # 2 Date . Feb. 10,1985 | |||
' Completed by J.'P. Ronafalvy Telephone 609-935-6000 4 Extension 4455 Month January-1985 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 I | |||
7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 i 13 0 29 0 14 0 30 0 15 0 31 0 16 0 Pg. 8,1-7 R1 t | |||
8502150570 850131 PDR ADOCK 05000311 R PDR | |||
;,.,--,y e . , . - - | |||
-, -- , ,,-- -- , , . - + , - | |||
m - | |||
, ,, . - , , . ~ . - . . | |||
OPERATING DATA REPORT Docket No'. 50-311~ | |||
Date Feb. 10,1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status | |||
: 1. Unit Name Salem No. 2 Notes | |||
: 2. Reporting Period January 1985- | |||
: 3. ' Licensed Thermal Power (MWt) 3411 | |||
: 4. Nameplate Rating (Gross MWe) 1170* | |||
5.. Design Electrical Rating (Net MWe)' 1115 | |||
: 6. Maximum Dependable Capacity (Gross MWe)1149 | |||
: 7. Maximum Dependable Capacity (Net MWe) 1106 | |||
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason | |||
* Previous value reported was the turbine rating,- | |||
not the generator rating as required. | |||
: 9. Pcwer Level to Which Restricted, if any (Net MWe) N/A | |||
: 10. Reasons for Restrictions, if any N/A i | |||
This Month Year to Date Cumulative | |||
: 11. Hours in Reporting Period 744 744 28969 | |||
: 12. No. of Hrs. Reactor was Critical 0 0 15094.6 i 13. Reactor Reserve Shutdown Mrs. O. 0 3533.6 l 14. Hours Generator On-Line 0 0 14612.1 l 15. Unit Reserve Shutdown Hours 0 0 0 | |||
: 16. Gross Thermal Energy Generated (MWH) 0 0 43727036 | |||
: 17. Gross Elec. Energy Generated (MWH) 0 0 14277650 l 18. Net Elec. Energy Generated (MWH) (2419) (2419) 13515417 | |||
: 19. Unit Service Factor 0 0 50.4 | |||
: 20. Unit Availability Factor 0 0 50.4 | |||
: 21. Unit Capacity Factor (using MDC Net) 0 0 42.2 | |||
: 22. Unit Capacity Factor | |||
{ (using DER Net) 0 0 41.8 | |||
: 23. Unit Forced Outage Rate 100 100 38.2 | |||
: 24. Shutdowns scheduled over next 6 months (type, date_and duration of each) i N/A | |||
: 25. If shutdown at end of Report Period, Estimated'Date of Startup: | |||
j 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 l | |||
:l UNIT SHUTDOWN AND POWER REDUCTIONS Docknt No. 50 -311 REPORT MONTH January 1985 Unit Name Salem No.2 | |||
! Date Feb. 10,1985 Completed by J.P. Ronafalvy Telephone. 609-935-6000 Extension '4455 Method of Duration Shutting License Cause;and-Corrective | |||
] Down Event System Component Action to i No. Date Type Hours Reason j 1 2 Reacto r Report Code 4 Code 5 Prevent Recurrence-1 Misc. Major 85-010 1-01 S 312.0 B 4 - HC HTEXCH Condenser Overhaul-Major. | |||
85-010 1-01 S 312.0 A 4 - HA TURBIN Turbine Overhaul Generator-85-010 1-01 F 312.0 A 4 - HA GENERA Major Overhaul Nuclear 85-010 1-01 S 312.0 C 4 - | |||
RC FUELXX Normal Refueling Other 85-012 1 F 432.0 A 4 - | |||
HA GENERA Generator Problems | |||
) 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 l' F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as-i S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source | |||
; C-Refueling 3-Automatic-Scram. tion of Data s | |||
.! D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training.& Licensing Exam Previous Outage for Licensee. | |||
l F-Administrative 5-Load Reduction Event Report | |||
~ | |||
G-Operational' Error-explain 9-Other (LER) File ' | |||
H-Other-explain (NUREG 0161) 1 1 | |||
l | |||
MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH JANUARY 1985 UNIT NAME: Salem 2 DATE: February 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/935-6000 X4455 | |||
* DC R NO . PRINCIPLE SYSTEM SUBJECT 2EC-1963 Service Water Position No. 24 Service Water Motor (Allis Chalmers) has failed and is being replaced with a spare (GE) - motor. | |||
* Design Change Request l | |||
- MAJOR. PLANT MODIFICATIONS -DOCKET NO.: ~50-311 | |||
- REPORT MONTH JANUARY'1985 | |||
, UNIT NAME: Salem 2 DATE: February 10, 1985 | |||
. COMPLETED ~BY: .J. Ronafalvy TELEPHONE: 609/339-4455 DCR NO. 10CFR 50.59 . SAFETY EVALUATION , | |||
2EC-1963- ' This change involves the replacement of an existing qualified motor with another qualified motor (dif ferent - | |||
manufacturer) . The differences between the two motors do 4 not compromise reliability and availability features. No | |||
- unreviewed safety cn: environmental questions ai *nvolved. | |||
* Design' Change Request 9 | |||
i s | |||
,0 | |||
) | |||
o--- - . v . -- , ,- | |||
s 1 | |||
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 | |||
( | |||
WO'NO DEPT . UNIT EQUIPMENT IDENTIFICATION 12-07-078-3 4 | |||
SMD 2 VALVE 24SW228 | |||
, FAILURE DESCRIPTION: VALVE STEM IS BENT.. | |||
CORRECTIVE ACTION: REPLACED VALVE-85-01-08-013-6 | |||
{ SMD 2 FUEL HANDLING BUILDING CRANE , | |||
', FAILURE DESCRIPTION:' EXCESSIVE BRIDGE AND TROLLEY MOTION AND-THE CONTROL | |||
. CIRCUIT FOR.THE BRIDGE IS OPERATING.IN FAST SPEED- | |||
! EWTN THOUGH SPEED SELECTOR IS ON SLOW SPEED.- - | |||
CORRECTIVE ACTION: ADJUSTED TROLLEY AND BRIDGE BRAKES;' CHANGED FUSE IN' BRIDGE SLOW SPEED RECT. CIRCUIT 1 | |||
009900429-1 i SMD 2 FUEL HANDLING BUILDING CRANE i FAILURE DESCRIPTION: CORRECT PROBLEM WITH CRANE. | |||
: l. CORRECTIVE! ACTION: CORRECTED THE MECHANICAL-INTERLOCK WHICH WAS HANGING UP 84-10-16-027-7 SMD 2 NO. :22 CHILLER CONDENSER t- FAILURE DESCRIPTION: POSSIBLE TUBE LEAK CORRECTIVE ACTION: . REPLACED TUBE NO. R4-4 i | |||
8 | |||
SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-12-07-074-7 SMD- 2 VALVE 21SW243 FAILURE DESCRIPTION: IMPROPER THREAD ENGAGEMENT ON ALL NUTS WHICH FASTEN THE VALVE FLANGES TO THE SERVICE WATER PIPING CORRECTIVE ACTION:- ' REPLACED STUD BOLTS 009901451-3 SIC 2 2R19A FAILURE DESCRIPTION: CHECK SOURCES WILL NOT ACTIVATE CORRECTIVE ACTION: REBUILT BACKPLANE 009900420-8 SMD 2 FUEL TRANSFER CART . | |||
FAILURE DESCRIPTION: PULL CABLE IS PREVENTING CART FROM REPOSITIONING' PROPERLY CORRECTIVE ACTION: REPAIRED PULL CABLE AS PER DR #MD-84-3371 84-09-29-017-1 SMD 2 10 BREAKER 21-3-11S FAILURE DESCRIPTION: BREAKER TRIPS WHEN BEZEL IS PLACED IN ' SLOT AND HAS ALL'SIX BUTTONS IN PLACE CORRECTIVE ACTION: . -REPLACED BREAKER RC 21-3-11 S AS PER DCR 1ED-10 0A | |||
& FQ WOMD039048 | |||
c- | |||
* 4 | |||
. SALEM GENERATING STATION MONTHLY: OPERATING' | |||
==SUMMARY== | |||
- UNIT NO. 2 j' . JANUARY 1985 , | |||
SALEM UNIT NO.'2 | |||
~ | |||
The period began with 'the second ' refueling / turbine outage in progress. | |||
Total man-rem exposure for[ work performed this outage.is significantlyf less'than the projected exposure. This is attributed to excellent-communication-among all concerned. parties.- Main' Generator replacement-work, continues. Turbine work'is continuing. All-lower and upper innerfcylinders have'been removed for reblading and the machining of sealing areas isiin progress. . Electrical and-mechanical modifications are' continuing for adaptation;of the General-Electric Generator. The rotor for the' Main i Generator. arrived on' site. Installation'of the three LP rotors has been initiated.- A successful Generator Bump Test (vibration type test),was accomplished upon completion of bracing and. | |||
reinforcement. 'The Reactor Vessel Flange. surface was polished | |||
, underwater. This is the first time this type work was performed | |||
: l. underwater. Extensive dose savings was realized by this effort. Fuel | |||
. inspection and loading commenced and was completed. The' Reactor Vessel ~ Head was set in place. System . outages - (CVCS, RHR,. and SJ) ~ were initiated'and completed.. 2B Battery cell replacement and 2B Vital Bus outage.were initiated and completed. 2A Battery selected cell replacement was initiated and completed. MSR work continues. : Type C leak rate testing lof Containment Isolation Valves in is progress.- -21 i Component Cooling Heat Exchanger (CCHX) retubing was completed. | |||
Approximately 1600 tubes'were replaced. | |||
i t | |||
i l | |||
~ | |||
L | |||
4 z-_. m .. 4 4 -a 4 7$ | |||
' REFUELING INFORMATION DOCKET'NO.: 50-311 | |||
; COMPLETED BY: J. Ronafalvy ' UNIT NAME:: -Salem 2 DATE: February 10, 1985 | |||
, TELEPHONE:- 609/935-6000 j EXTENSION: -4455 . | |||
i . Month' January 1985 i i 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 | |||
:4. A) Will Technical. Specification changes or other license amendments be required? | |||
l YES ,X* NO - | |||
- B)' _Has'the reload fuel design been reviewed by the Station | |||
[ Operating Review Committee? | |||
f ' YES X NO j If no, when is-it scheduled? N/A j 5. Scheduled date (s) for submitting proposed licensing action: | |||
! N/A | |||
; 6. Important licensing considerations associated with refueling: " | |||
! NONE i | |||
: 7. Number of Fuel Assemblies: | |||
4 A) Incore 193 B) In Spent Fuel Storage 140 | |||
: 8. Present licensed spent fuel storage capacity: 1170 | |||
; Future spent-fuel storage capacity: '1170 | |||
: 9. Date of last refueling that can be discharged to spent. fuel pool assuming the present licensed capacity: March 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. | |||
i | |||
. _ - _ - . _ . _ _ _ _ . _ _ _. . . _ _ ____._ . . _ - . _ _ . . _ _ _ . . - , . . - . . . _ _ . . . _ _ . . a- | |||
O PSEG Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station | |||
. February 10', 1985 | |||
; -- Director, _ Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555- | |||
,1 | |||
==Dear Sir:== | |||
MONTHLY' OPERATING REPORT I | |||
SALEM NO._2 DOCKET NO. 50-311 4 | |||
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 January 1985 are being sent to you. | |||
Average Daily Unit Power Level-Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification-Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, s | |||
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- gj t | |||
I I | |||
The Energy People 95-2189 (20M) 11-81 | |||
._. , __ . ., , , , . . _ . ,-}} |
Latest revision as of 17:31, 18 May 2020
ML20106J285 | |
Person / Time | |
---|---|
Site: | Salem |
Issue date: | 01/31/1985 |
From: | Ronafalvy J, Zupko J Public Service Enterprise Group |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
References | |
NUDOCS 8502150570 | |
Download: ML20106J285 (10) | |
Text
~
AVERAGE DAIL.Y UNIT POWER LEVEL-Docket No. 50-311 Unit Name Salem # 2 Date . Feb. 10,1985
' Completed by J.'P. Ronafalvy Telephone 609-935-6000 4 Extension 4455 Month January-1985 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 I
7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 i 13 0 29 0 14 0 30 0 15 0 31 0 16 0 Pg. 8,1-7 R1 t
8502150570 850131 PDR ADOCK 05000311 R PDR
- ,.,--,y e . , . - -
-, -- , ,,-- -- , , . - + , -
m -
, ,, . - , , . ~ . - . .
OPERATING DATA REPORT Docket No'. 50-311~
Date Feb. 10,1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status
- 1. Unit Name Salem No. 2 Notes
- 2. Reporting Period January 1985-
- 3. ' Licensed Thermal Power (MWt) 3411
- 4. Nameplate Rating (Gross MWe) 1170*
5.. Design Electrical Rating (Net MWe)' 1115
- 6. Maximum Dependable Capacity (Gross MWe)1149
- 7. Maximum Dependable Capacity (Net MWe) 1106
- 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason
- Previous value reported was the turbine rating,-
not the generator rating as required.
- 9. Pcwer Level to Which Restricted, if any (Net MWe) N/A
- 10. Reasons for Restrictions, if any N/A i
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 744 28969
- 12. No. of Hrs. Reactor was Critical 0 0 15094.6 i 13. Reactor Reserve Shutdown Mrs. O. 0 3533.6 l 14. Hours Generator On-Line 0 0 14612.1 l 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0 43727036
- 17. Gross Elec. Energy Generated (MWH) 0 0 14277650 l 18. Net Elec. Energy Generated (MWH) (2419) (2419) 13515417
- 19. Unit Service Factor 0 0 50.4
- 20. Unit Availability Factor 0 0 50.4
- 21. Unit Capacity Factor (using MDC Net) 0 0 42.2
- 22. Unit Capacity Factor
{ (using DER Net) 0 0 41.8
- 23. Unit Forced Outage Rate 100 100 38.2
- 24. Shutdowns scheduled over next 6 months (type, date_and duration of each) i N/A
- 25. If shutdown at end of Report Period, Estimated'Date of Startup:
j 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 l
- l UNIT SHUTDOWN AND POWER REDUCTIONS Docknt No. 50 -311 REPORT MONTH January 1985 Unit Name Salem No.2
! Date Feb. 10,1985 Completed by J.P. Ronafalvy Telephone. 609-935-6000 Extension '4455 Method of Duration Shutting License Cause;and-Corrective
] Down Event System Component Action to i No. Date Type Hours Reason j 1 2 Reacto r Report Code 4 Code 5 Prevent Recurrence-1 Misc. Major 85-010 1-01 S 312.0 B 4 - HC HTEXCH Condenser Overhaul-Major.85-010 1-01 S 312.0 A 4 - HA TURBIN Turbine Overhaul Generator-85-010 1-01 F 312.0 A 4 - HA GENERA Major Overhaul Nuclear 85-010 1-01 S 312.0 C 4 -
RC FUELXX Normal Refueling Other 85-012 1 F 432.0 A 4 -
HA GENERA Generator Problems
) 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 l' F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as-i S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source
- C-Refueling 3-Automatic-Scram. tion of Data s
.! D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training.& Licensing Exam Previous Outage for Licensee.
l F-Administrative 5-Load Reduction Event Report
~
G-Operational' Error-explain 9-Other (LER) File '
H-Other-explain (NUREG 0161) 1 1
l
MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH JANUARY 1985 UNIT NAME: Salem 2 DATE: February 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/935-6000 X4455
- DC R NO . PRINCIPLE SYSTEM SUBJECT 2EC-1963 Service Water Position No. 24 Service Water Motor (Allis Chalmers) has failed and is being replaced with a spare (GE) - motor.
- Design Change Request l
- MAJOR. PLANT MODIFICATIONS -DOCKET NO.: ~50-311
- REPORT MONTH JANUARY'1985
, UNIT NAME: Salem 2 DATE: February 10, 1985
. COMPLETED ~BY: .J. Ronafalvy TELEPHONE: 609/339-4455 DCR NO. 10CFR 50.59 . SAFETY EVALUATION ,
2EC-1963- ' This change involves the replacement of an existing qualified motor with another qualified motor (dif ferent -
manufacturer) . The differences between the two motors do 4 not compromise reliability and availability features. No
- unreviewed safety cn: environmental questions ai *nvolved.
- Design' Change Request 9
i s
,0
)
o--- - . v . -- , ,-
s 1
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2
(
WO'NO DEPT . UNIT EQUIPMENT IDENTIFICATION 12-07-078-3 4
SMD 2 VALVE 24SW228
, FAILURE DESCRIPTION: VALVE STEM IS BENT..
CORRECTIVE ACTION: REPLACED VALVE-85-01-08-013-6
{ SMD 2 FUEL HANDLING BUILDING CRANE ,
', FAILURE DESCRIPTION:' EXCESSIVE BRIDGE AND TROLLEY MOTION AND-THE CONTROL
. CIRCUIT FOR.THE BRIDGE IS OPERATING.IN FAST SPEED-
! EWTN THOUGH SPEED SELECTOR IS ON SLOW SPEED.- -
CORRECTIVE ACTION: ADJUSTED TROLLEY AND BRIDGE BRAKES;' CHANGED FUSE IN' BRIDGE SLOW SPEED RECT. CIRCUIT 1
009900429-1 i SMD 2 FUEL HANDLING BUILDING CRANE i FAILURE DESCRIPTION: CORRECT PROBLEM WITH CRANE.
- l. CORRECTIVE! ACTION: CORRECTED THE MECHANICAL-INTERLOCK WHICH WAS HANGING UP 84-10-16-027-7 SMD 2 NO. :22 CHILLER CONDENSER t- FAILURE DESCRIPTION: POSSIBLE TUBE LEAK CORRECTIVE ACTION: . REPLACED TUBE NO. R4-4 i
8
SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-12-07-074-7 SMD- 2 VALVE 21SW243 FAILURE DESCRIPTION: IMPROPER THREAD ENGAGEMENT ON ALL NUTS WHICH FASTEN THE VALVE FLANGES TO THE SERVICE WATER PIPING CORRECTIVE ACTION:- ' REPLACED STUD BOLTS 009901451-3 SIC 2 2R19A FAILURE DESCRIPTION: CHECK SOURCES WILL NOT ACTIVATE CORRECTIVE ACTION: REBUILT BACKPLANE 009900420-8 SMD 2 FUEL TRANSFER CART .
FAILURE DESCRIPTION: PULL CABLE IS PREVENTING CART FROM REPOSITIONING' PROPERLY CORRECTIVE ACTION: REPAIRED PULL CABLE AS PER DR #MD-84-3371 84-09-29-017-1 SMD 2 10 BREAKER 21-3-11S FAILURE DESCRIPTION: BREAKER TRIPS WHEN BEZEL IS PLACED IN ' SLOT AND HAS ALL'SIX BUTTONS IN PLACE CORRECTIVE ACTION: . -REPLACED BREAKER RC 21-3-11 S AS PER DCR 1ED-10 0A
& FQ WOMD039048
c-
- 4
. SALEM GENERATING STATION MONTHLY: OPERATING'
SUMMARY
- UNIT NO. 2 j' . JANUARY 1985 ,
SALEM UNIT NO.'2
~
The period began with 'the second ' refueling / turbine outage in progress.
Total man-rem exposure for[ work performed this outage.is significantlyf less'than the projected exposure. This is attributed to excellent-communication-among all concerned. parties.- Main' Generator replacement-work, continues. Turbine work'is continuing. All-lower and upper innerfcylinders have'been removed for reblading and the machining of sealing areas isiin progress. . Electrical and-mechanical modifications are' continuing for adaptation;of the General-Electric Generator. The rotor for the' Main i Generator. arrived on' site. Installation'of the three LP rotors has been initiated.- A successful Generator Bump Test (vibration type test),was accomplished upon completion of bracing and.
reinforcement. 'The Reactor Vessel Flange. surface was polished
, underwater. This is the first time this type work was performed
- l. underwater. Extensive dose savings was realized by this effort. Fuel
. inspection and loading commenced and was completed. The' Reactor Vessel ~ Head was set in place. System . outages - (CVCS, RHR,. and SJ) ~ were initiated'and completed.. 2B Battery cell replacement and 2B Vital Bus outage.were initiated and completed. 2A Battery selected cell replacement was initiated and completed. MSR work continues. : Type C leak rate testing lof Containment Isolation Valves in is progress.- -21 i Component Cooling Heat Exchanger (CCHX) retubing was completed.
Approximately 1600 tubes'were replaced.
i t
i l
~
L
4 z-_. m .. 4 4 -a 4 7$
' REFUELING INFORMATION DOCKET'NO.: 50-311
- COMPLETED BY
- J. Ronafalvy ' UNIT NAME:: -Salem 2 DATE: February 10, 1985
, TELEPHONE:- 609/935-6000 j EXTENSION: -4455 .
i . Month' January 1985 i i 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
- 4. A) Will Technical. Specification changes or other license amendments be required?
l YES ,X* NO -
- B)' _Has'the reload fuel design been reviewed by the Station
[ Operating Review Committee?
f ' YES X NO j If no, when is-it scheduled? N/A j 5. Scheduled date (s) for submitting proposed licensing action:
! N/A
- 6. Important licensing considerations associated with refueling
- "
! NONE i
- 7. Number of Fuel Assemblies:
4 A) Incore 193 B) In Spent Fuel Storage 140
- 8. Present licensed spent fuel storage capacity: 1170
- Future spent-fuel storage capacity
- '1170
- 9. Date of last refueling that can be discharged to spent. fuel pool assuming the present licensed capacity: March 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.
i
. _ - _ - . _ . _ _ _ _ . _ _ _. . . _ _ ____._ . . _ - . _ _ . . _ _ _ . . - , . . - . . . _ _ . . . _ _ . . a-
O PSEG Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station
. February 10', 1985
- -- Director, _ Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555-
,1
Dear Sir:
MONTHLY' OPERATING REPORT I
SALEM NO._2 DOCKET NO. 50-311 4
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 January 1985 are being sent to you.
Average Daily Unit Power Level-Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification-Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, s
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- gj t
I I
The Energy People 95-2189 (20M) 11-81
._. , __ . ., , , , . . _ . ,-