ML20106J285

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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

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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

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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

] 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

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G-Operational' Error-explain 9-Other (LER) File '

H-Other-explain (NUREG 0161) 1 1

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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

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2

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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

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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

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. SALEM GENERATING STATION MONTHLY: OPERATING'

SUMMARY

- UNIT NO. 2 j' . JANUARY 1985 ,

SALEM UNIT NO.'2

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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.

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' 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.

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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-

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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

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The Energy People 95-2189 (20M) 11-81

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