ML20099E475

Monthly Operating Rept for Oct 1984

ML20099E475
Person / Time
Site:	Salem
Issue date:	10/31/1984
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8411210326
Download: ML20099E475 (12)

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, JAVERAGE DAILY 1 UNIT. POWER LEVEL'- ,

Docket No.- 50-311 J

Unit.Name Salem # 2 Date -Nov. 10,1984 Completedtby. J.'P. Ronafalvy Telephone 609-935-6000

. Extension '4455 Month October 1984 Day Average Daily Power Level Day Average Daily Power: Level (MWe-KET) (MWe-NET) 11' 966 17 -0 2 1105 18 0 3 1102 19' O 4 588 20 0:

5 0 21 0-6 0 ~ 22 0 7 0 23 'O 8 0 24 0-4 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 8411210326 841031 '

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. OPERATING DATA REPORT Docket No. 50-311 Date Nov. 10,1984 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period October 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

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 745 7320 26761

12. No. of Hrs. Reactor was Critical 81.2 3386.0 15094.6

13. Reactor Reserve Shutdown Hrs. 0 1442.9 3533.6

14. Hours Generator On-Line 81.2 3194.8 14612.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (Mim) 276166 10255964 43727036

17. Gross Elec. Energy Generated (MWH) 94330 3409360 14277650

18. Net Elec. Energy Generated (MWH) 84749 3206994 13524242

19. Unit Service Factor 10.9 43.6 54.6

20. Unit Availability Factor 10.9 43.6 54.6

21. Unit Capacity Factor (using MDC Net) 10.3 39.6 45.7

22. Unit Capacity Factor (using DER Net) 10.2 39.3 45.3

23. Unit Forced Outage Rate 89.1 56.4 36.9

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:

4-85

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 Page 3 of 12

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E UNIT SHUTDOWN AND FOWER REDUCTIONS Docket No. 50-311 REPORT MONTH October 1984 Unit Name Salem No.2 .

1 Date Nov. 10,1984 J.P. Ronafalvy Telephone 609-935-6000 g Completed by 4455-Extension 7 Method of Duration Shutting License Cause and Corrective E Action to No. Date Type Hours Reason Down Event System Component Reactor Report- Code 4 Code 5 Prevent Recurrence L 1 2 HA GENERA Stator Windings84-300 10-04 F 663.7 A 3 -

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r 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 A-Equipment Failure-explain 1-Manual Instructions Salem as i F: Forced 2-Manual Scram. for Prepara- Source S: Scheduled B-Maintenance or Test

' C-Refueling 3-Automatic Scram. tion of Data

" D-Regulatory Restriction 4-Continuation of Entry Sh6ets y E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report P

G-Operational Error-explain 9-Other lLER) File H-Other-explain (NUREG 0161) 5

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. u 1 l MAJOR PLANT MODIFICATIONS DOCKET NO.: 450-311 REPORT MONTH OCTOBER'1984 UNIT NAME: Salem 2 I' ATE: November 10, 1984 C OMPLETE) BY: J. Ronafalvy TELEPHONE: 609/935-6000 X4455-

• DCR NO. PRINCIPLE SYSTEM SUBJECT

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2SC-1332 Chilled Water Install'an additional suction gattge no greater than 40 PSI for-21 and 22 Chilled Water

~ Pumps.

• Design Change Request

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MAJOR PLANT MODIFICATIONS- . DOCKET NO.: 50-311 REPORT MONTH OCTOBER 1984 UNIT.NAME: Salem 2 DATE: November 10, 1984-COMPLETED BY: J. Ronafalvy

-TELEPHONE:- 609/339-4455 DCR NO. -10CFR 50.59 SAFETY EVALUATION

2SC-1332' This change takes into account the ASME. Section' XI recommendations for the gauges to be no.more-- than four (4) times the reference value. No unreviewed safety or environmental questions are involved.

• ' Design Change Request t

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PSE&G SALEM GENERATING STATION ..

J SAFETY RELATED WORK ORDER LOG .

SALEM' UNIT 2, WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 942842 SIC COMMON R45'S FAILURE DESCRIPTION: CHANNEL INDICATORS FAIL;-PRINTERS INDICATE TRANSIENT.

ERRORS CORRECTIVE ACTION: RE-ENTERED FILE PARAMETERS FOR UNIT 1; REPLACED' LIMIT SWITCH AND Q8 ON CSM PL BOARD 2R4SB- _

0099128268 SIC 2 AIRLOCK SEAL FLOW INDICATOR (100' EL.)

FAILURE DESCRIPTION: IMPROPER FUNCTION DURING' SURVEILLANCE-TESTING CORRECTIVE ACTION: IMPROPER PLACEMENT OF BLOCKING TAG (CORRECTED) 0099098776 SIC 2 N-44

' FAILURE DESCRIPTION: N-44 SPIKES' PERIODICALLY CORRECTIVE ACTION: REPLACED GAIN POT. AND RESET DRAWER 009908397 SIC 2 EXCORE POWER RANGE CHANNELS FAILURE DESCRIPTION: DELTA'I CALIBRATION REQUIRED m

j CORRECTIVE ACTION: REPLACED MODULE 20M CAPACITORS o

,y 0099099187 SIC 2 CHANNEL 2R12B o.

m FAILURE DESCRIPTION: NO_ INDICATION.IN CONTROL ROOM-CORRECTIVE ACTION: LOCAL CONTROLLER' SEAT: RING ADJUSTED REPLACED THUMBWHEEL

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-SALEM UNIT 2' .

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION -

009902081

SIC 2 NO. 22 LOOP Tave INDICATOR FAILURE DESCRIPTION

ERRATIC READINGS CORRECTIVE ACTION: REPLACED AMP BOARD AND. MOTOR MOVEMENT 5AND f RECALIBRATED.

e 0099024713 SIC 2 2R12B i FAILURE DESCRIPTION: CHANNEL APPEARS FAILED CORRECTIVE ACTION: NEW PINS INSTALLED; SETPOINTS. ADJUSTED' 0099099217 SIC 2 OVERPOWER RECORDER CHANNEL N-43 FAILURE DESCRIPTION: CHANNEL CONTINUALLY. FAILS AT 120% POWER' CORRECTIVE ACTION: REPLACED-SERVO ASSEMBLY AND RECALIBRATED

! 84-08-24-001-3' SMD- 2 NO. 23 CHARGING PUMP FAILURE DESCRIPTION: CONSTANT OVERFLOW FROM THE SEAL WATER' TANK-CORRECTIVE ACTION: REPACKED #3 CYLINDER l.m 84-09-28-061-2 SMD 2 23 ACCUMULATOR PRESSURE ' ALARM i j-a FAILURE DESCRIPTION: ALARM IS SOUNDING WITH-SATISFACTORY PRESSURE; co S CORRECTIVE ACTION: REPLACED CARAST 2 IN RACK 111 AND 112-t

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. SALEM. UNIT 2 - <

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JWO NO - DEPT UNIT EQUIPMENT IDENTIFICATION

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0099100002 SIC 2 22 S/G PRESSURE CHANNEL II FAILURE DESCRIPTION: READING LOWER THAN OTHER CHANNELS CORRECTIVE ACTION: RECALIBRATED.PRESSURELINDICATORS FOR-CHANNELS 1, 2, AND 3 84-09-14-021-7 SIC 2 21 S/G STEAM FLOW CHANNEL I FAILURE DESCRIPTION: SPIKE OCCURS SOMETIMES CAUSING THE FEED' REG.iVALVE TO GO FULL OPEN REPLACED RELAY FX512A- '

CORRECTIVE ACTION: -

84-09-13-021-1 ~

. SIC 2 24 LOOP Tave FAILURE DESCRIPTION: READING LOW.

CORRECTIVE ACTION: REPLACED RELAY TX412AB-IN RACK-'126- .

84-09-12-079-1 "

SIC- 2 #22 FAN COIL LEAK DETECTOR

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FAILURE DESCRIPTION: 2LC731A/B OUT OF SPEC.

CORRECTIVE ACTION: REPLACED C2 AND C3; PERFORMED - 2IC-2'.10.'169.'

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-m j 84-05-30-592-1 ,

o SIC 2 NIS N-42 FAILURE' DESCRIPTION: CONTROL ROOM. INDICATION 6%'> IR'S g CORRECTIVE ACTION: REPLACED PCB;" INDICATOR RECALIBRATED-

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i EQUIPMENT IDENTIFICATION-WO NO DEPT UNIT 84-09-29-027 SMD- 2 26 SERVICE WATER PUMP PIPING ,

FAILURE DESCRIPTION: PIPE ELBOW HAS A LEAK-

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CORRECTIVE ACTION: REPLACED SPOOL' PIECE-l 009900264-7 ,

1 SMD 2 21 COMPONENT COOLING PUMP  :

FAILURE DESCRIPTION:- OUTBOARD SEAL LEAKING', n.

t CORRECTIVE ACTION

REBUILT OUTBOARD SEAL- 3 i

0099100614 u.

SMD 2 21 COMPONENT COOLING PUMP .

! FAILURE DESCRIPTION: INBOARD BEARING LEAKS OUT l

CORRECTIVE ACTION: REPL' ACED OUTBOARDLBEARING- -

0099099616 4 SMD 2 ' #11. SERVICE WATER PUMP STRAINER ^

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! FAILURE DESCRIPTION: PACKING LEAK

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CORRECTIVE' ACTION: REPACKED AND REPLACED PACKING GLAND- - ,-

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1 SALEM GENERATING STATION-MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 OCTOBER 1984 Unit No. 2 began the period operating at full power. It remained at full power until 10/04/84 when, at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, the Unit tripped as a result of generator differential relay protection actuation. Mode 5 was entered on 10/05/84 at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. Investigations to determine the extent of damage to the Generator were conducted. A high potential test was performed indicating distress in the Phase C windings in addition to the failed coil behind the header box in the Phase A winding. Due to the extent of damage to the Generator, it has been decided to replace'the generator with the General Electric Generator originally intended for Hope Creek Unit 2. This decision will result in an expected return to service for No. 2 Unit- on April 1, 1985. The Unit will be refueled during this outage.

Sixty-eight (68) new fuel assemblies will' arrive on site by 11/29/84.

The Component Cooling Water System has been dechromated and released for inspections and work. Jul outage on "C" Vital Bus is in progress.

The Reactor Coolant System has been depressurized. As a result of MSR inspections, work similar to that performed during'the last Unit 1 outage will be required. The No. 22 Service Water Header outage was commenced. On 10/23/84, the Annual Emergency Exercise was conducted testing the emergency preparedness capabilities of PSE&G and outside agencies.

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s REFUELING INFORMATION DOCKET.NO.: 50-311~

COMPLETED' BY:- J. Ronafalvy UNIT-NAME:- Salem 2 DATE: ' November 10,-1984

. TELEPHONE: J 609/935-6000

. EXTENSION : : 4455 Month -October 1984

.l. ~ . 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 re. fueling:'. Apri101, 1985-4.. A) Will Technical Specification changes or other license amendments be required?- .

YES- X *- NO B) Has the reload tuel_ design been reviewed by the Station'

. Operating Review Committee?

YES NO X*

If no, when is it scheduled? December 1984

5. Scheduled date (s) for. submitting proposed licensing action:

December 1984 (if additional submittal is required) *

6. Important licensing considerations associated with refueling:

NOME

7. Number of Fuel Assemblies:

A) Incore 193 B) In Spent Fuel Storage 72.

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. The actual reload analysis for Cycle 3 is in progress and if further Technical Specification changes are required,.they will ' '

be submitted in December-1984.

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j IF'!!ilBit i (l") l Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station gg4 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 October 1984 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 Intormation Sincerely yours, 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 f.h l

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The Energy People 16 21T)(20W 1181