ML20106J285

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Monthly Operating Rept for Jan 1985
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 Extension 4455 4

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

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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 i

No.

Date Type Hours Reason Down Event System Component Action to j

1 2

Reacto r Report Code 4 Code 5 Prevent Recurrence-Misc. Major 1

HC HTEXCH Condenser Overhaul-85-010 1-01 S

312.0 B

4 Major.

HA TURBIN Turbine Overhaul 85-010 1-01 S

312.0 A

4 Generator-HA GENERA Major Overhaul 85-010 1-01 F

312.0 A

4 Nuclear RC FUELXX Normal Refueling 85-010 1-01 S

312.0 C

4 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 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

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 not compromise reliability and availability features.

No 4

- unreviewed safety cn: environmental questions ai

  • nvolved.

Design' Change Request 9

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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 SMD 2

VALVE 24SW228 4

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 SMD 2

FUEL HANDLING BUILDING CRANE i

i FAILURE DESCRIPTION:

CORRECT PROBLEM WITH CRANE.

CORRECTIVE! ACTION:

CORRECTED THE MECHANICAL-INTERLOCK WHICH WAS l.

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-

. SALEM GENERATING STATION 4

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 Generator. arrived on' site.

Installation'of the i

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.

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4

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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:

A)

Incore 193 4

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-

Dear Sir:

,1 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

.. _.,-