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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

Monthly Operating Rept for Jan 1985
ML20106J285
Person / Time
Site: Salem PSEG icon.png
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

  • 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

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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

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