ML20135F709

Monthly Operating Rept for Aug 1985

ML20135F709
Person / Time
Site:	Salem
Issue date:	08/31/1985
From:	Ronafalvy J, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8509170364
Download: ML20135F709 (13)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 DateSeptember 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month August 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1097 17 1078 2~ 1075 18 1087 3 1088 19 1085 4 1057 20 1090 5 1062 21 1085 6 1089 22 1090 7 1114 23 1094 8 601 24 1098 9 0 25 1084 10 25 26 1097 11 811 27 133 12 1015 28 0 13 1080 29 391 14 1084 30 1074 15 1089 31 1091 16 1087 Pg. 8.1-7 R1 8509170364 850831 PDR e

R ADOCK 05000311 /

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OPERATING DATA REPORT Docket No. 50-311 Date September 10,1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period August 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)ll49

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) N7A

10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5831 34056

12. No. of Hrs. Reactor was Critical 648.3 2869.7 17964.3

13. Reactor Reserve Shutdown li r s . 0 0 3533.6

14. Hours Generator On-Line 636.6 2595.8 17207.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2128176 8100056 51827092

17. Gross Elec. Energy Generated (MWH) 702010 2669990 __

16947640

18. Net Elec. Energy Generated (MWH) 669179 2502739_ 16020575

19. Unit Service Factor ~

85.6 44.5 50.5

20. Unit Availability Factor 85.6 44.5 50.5

21. Unit Capacity Factor t (using MDC Net) 81.3 38.8 42.5

22. Unit Capacity Factor (using DER Net) 80.7 38.5 42.2

23. Unit Forced Outage Rate 14.4 52.7 40.1

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:

N/A

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved Initial Criticality 6/30/80 872/80 ~

Initial Electricity 9/1/80 673781 Commercial Operation 9/24/80 10/13/81 8-1-7.R2 i . - - _ - . _ - _ - _ -_ __.

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UNIT SHUTDOWN AND POWER REDUCTIONS Dockat No. 50-311 .

REPORT MONTH August 1985 Unit Name Salem No.2 Date Sep tember 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 1 2 Rea cto r Report Code 4 Code 5 Prevent Recurrence i Nuclear Other Control Rod 85-184 8-08 F 56.0 A 3 -

RB CRDRVE Drive Problems Nuclear Serivce Water Heat 85-206 8-27 F 51.4 A 1 -

WA HTEXCH Exchangers l

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! 1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 i F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as i S: Scheduled .B-Maintenance or Test 2-Manual Scram. for Prepara- Source I C-Refueling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee i F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) l i

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MAJOR PLANT MODIFICATIONS DOCKET NO. : 50-311 REPORT MONTH AUGUST 1985 UNIT NAME: Salem 2 DATE: September 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

• DC R NO . PRINCIPLE SYSTEM SUBJECT 2EC-1595 NPDES Thermal Relocate circ. water inlet Monitoring System and outlet temperature monitors from their present location at the condenser inlet and outlet waterboxes at the circ. water intake structure for measuring inlet ambient river water temperature and to the six outlet pipes for measuring combined plant discharge temperature.

2EC-1980 Steam Generator Feed Install suppression diodes Pumps across D.C. relays, delete BF65 valve limit switch pump trip and provide first out alarm for local pump trip pushbutton.

2EC-1995 Main Steam Install one inch, Sch. 40 vent lines between downstream of valves MS903 and MS904 and the existing atmospheric exhaust piping in the Auxiliary Feedwater Pump Turbine Room.

2EC-2026 Fire Protection-Doors Addition of two fire rated doors. These doors are located in the Aux Building and Mechanical / Electrical Penetration Areas. Both doors will be rated for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (Class A). Door #88 is to be removed and opening sealed.

Stairway will also be removed.

Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH AUGUST 1985 UNIT NAME: Salem 2 DATE: September 10, 1985 COMPLETED BY: J. Ronatalvy TELEPHONE: 609/339-4455

• DC R NO. 10CFR 50.59 SAFETY EVALUATION 2EC-1595 This DCP involves moving the location of the circulating water system temperature monitors and as such does not involve a change to the FSAR or the Tech. Specs. No unreviewed safety or environmental questions are involved.

2EC-1980 This modification does not alter the function of a safety related system required for safe shutdown nor does it compromise a safety related system. No unreviewed safety or environmental questions are involved.

2 EC-19 95 This DCP does not create any new safety hazards. It improves the Auxiliary Feedwater Pump Turbine performance and reliability by eliminating the need of throttling the warm-up (drain valves) to minimize the amount of steam entering the pump's room. No unreviewed safety or environmental questions are involved.

2 EC-20 26 The new fire doors are not safety related. Their presence will not impact the operation of existing safety related equipment nor will they reduce the margin of safety related equipment as outlined in the Tech. Specs. Since the fire doors are relatively passive and " inert", a failure of the doors will not result in any damage or influence the operation of safety related equipment. The new fire doors will reduce the risk of fire damage to safety related equipment. No unreviewed safety or environmental questions are involved.

• Design Change Request

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099159503 SMD 2 22 CC PUMP FAILURE DESCRIPTION: SMALL CHROMATE LEAK ON DISCHARGE FLANGE.

CORRECTIVE ACTION: REPLACED GASKET ON BOTH SIDES OF SPACER 1/32".

0099165252 SIC 2 #21 STM GEN PRESS I FAILURE DESCRIPTION: COMPARATOR IS TRIPPING AND RESETTING AT ABOUT THE SAME VALUE.

CORRECTIVE ACTION: REPLACED C2 AND C3 IN PC514A/B. FOUND 105 MVAC ON OUTPUT OF 2PQ514SN. MD189 REMOVED FROM SERVICE INSTALLED SN166. COMPLETED FUNCTIONAL 2PD-2.6.030.

0099165422 SIC 2 RX TRIP BKR A FAILURE DESCRIPTION: INVESTIGATE CAUSE OF RX TRIP BKR " A" OPENING DURING SSPS TRAIN B TESTING.

- CORRECTIVE ACTION: MEASURED THE RESISTANCE OF SUPERVISORY COIL ON TRIP BKR A AND READ 7700 OHM, TRIP BKR B AT 7700 OHM REMOVED DUST COVER TO INSPECT LINKAGE. HAD TRIP BKR A AND B PASS B CLOSED DID CYCLED TRIP B 11 TIMES TO DUPLICATE. NO PROBLEMS.

0099176998 SIC 2 2PS 3 FAILURE DESCRIPTION: VALVE WON'T OPEN IN AUTO OR MANUAL.

CORRECTIVE ACTION: INSTALLED NEW AIR SUPPLY REGULATOR. REGULATOR SET TO 90 PSI.

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.i SALEM UNIT 2 f

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099178664 SMD 2 21 CFCU FAILURE DESCRIPTION: UNABLE TO ACKNOWLEDGE START OR STOP IN LOW SPEED.

CORRECTIVE ACTION: REPLACED RELAY 527-1/3 WITH A NEW ONE. RAN IN LOW SPEED AND ALL INDICATION IS SAT.

8409060507 SIC 2 #2 FIRE PP VENT DAMPERS FAILURE DESCRIPTION: DAMPER DOES NOT AUTO CLOSE WHEN FIRE PUMP IS TAKEN OUT OF SERVICE.

I CORRECTIVE ACTION: FOUND ACTUATOR MOTOR RUNNING, LIMIT SWITCH STUCK j IN ON POSITION. FIXED LIMIT SWITCH AND ADJUSTED DAMPERS AND. ACTUATOR. RETURNED TO SERVICE. NOW l

WORKING FINE.

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8507060340 SMD 2 2B DIESEL GEN FAILURE DESCRIPTION: GENERATOR FIELD GROUND ALARM CAME IN WHILE RUNNING DIESEL LOADED PER SP (O) 4.8.1.1.2 WOULD NOT RESET.

CORRECTIVE ACTION: FOUND PROBLEM TO BE WITH 64G RELAY. RELAY DEPT.

ADJUSTED RELAY. RAN DIESEL. ALARM NOW OPERATING

, PROPERLY.

I 8507260420 SMD 2 HEAT TRACE CONTROLLER HC-2121 FAILURE-DESCRIPTION: HC-2121, HEAT TRACE CONTROLLER FOR THE BORIC ACID FILTER DRAIN IS CONTROLLING LOW.

t CORRECTIVE ACTION: ' INPUT TO HC2121A+B CONTROLLERS IS ONLY 78 DEGREES FROM TC. BOTH CONTROLLERS ARE PICKED UP AND SENDING l

- POWER TO THE HEAT TRACE. SPLICED BOTH TRACES - SAT.

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8508060033 SIC 2 24 RC LOOP FLOW FAILURE DESCRIPTION: ALL CHANNELS READ APPROX. 98% LOW SPEC IS 97.9%.

CORRECTIVE ACTION: INSTALLED EQUIPMENT FOR STATEPOINT DATA. 8-6-85 REMOVED EQUIPMENT. 8-9-85 NEW LOW LIMIT VALUES 1 HAVE BEEN DETERMINED BY RX ENG. GROUPS. NO WORK PERFORMED.

8508060041 SIC 2 22 RC LOOP FLOW FAILURE DESCRIPTION: THE LOOP FLOWS ON 2 OF 3 CHANNELS ARE INDICATING 98%

LOW SPEC. IS 97.9%.

CORRECTIVE ACTION: NEW LOW LIMIT VALUES DETERMINED BY RX ENGINEERING.

NO WORK PERFORMED.

8508080042 SIC 2 CONDENSER VAC INDICATION FAILURE DESCRIPTION: CONDENSER VACUUM RECORDERS DO NOT AGREE WITH

> BACKPRESSURE INDICATION. DIFFERENCE APPROX. . 4" .6".

CORRECTIVE ACTION: CHECKED CAL. ON VACUUM RECORDER AND ALSO BACKPRESSURE INDICATORS. RECORDER REQUIRED CLEANING AND LUBRICATION. BOTH DEVICES WERE IN SPEC.

8508081472 SIC 2 21MS10 FAILURE DESCRIPTION: 21MS10 NO SET POINT RESPONSE.

[ CORRECTIVE ACTION: REPLACED SERVO SETPOINT STATION 2HC-5168. REMOVED S/N 107 AND INSTALLED S/N 102. CALIBRATED PER PAGE 22 OF CH CAL PROCEDURE 2PD-2.1.118.

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SALEM UNIT 2 -

WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8508081502' SIC 2 23 MS10 FAILURE DESCRIPTION: 23MS10 - UNABLE TO CHANGE SET POINT, CLOSE PUSH BUTTON STUCK IN THE RELEASE POSITION.

CORRECTIVE ACTION: FREED STUCK CLOSED PUSH BUTTON. PERFORMED APPLICABLE PORTIONS OF CHANNEL CA

L. PROCEDURE

TO VERIFY CAL OF CONTROLLER 2PC-536C.

8508100248 SMD 2 22MS167 FAILURE DESCRIPTION: WHEN THE OPEN PUSH BUTTON WAS HIT THE MS16 7 BY PASS DID NOT GO CLOSED. THE 22MS 167 DID GO OPEN BUT TOOK LONGER THAN NORMAL.

CORRECTIVE ACTION: REPLACED OPENING SOLENOID COIL.

8508120010 SIC 2 SHUTDOWN ROD ISB3 FAILURE DESCRIPTION: SHUTDOWN ROD ISB3 IRPI IS READING 14 STEPS LOWER THAN BANK DEMAND POSITION.

CORRECTIVE ACTION: FOUND INDICATOR TO BE PROBLEM BY SWAPPING INDICATORS.

DID CAL. CK. OF INDICATOR GN BINDER. FOUND SIGNAL MODULE OUT-OF-SPEC. CALIBRATED MODULE AND CHANNEL.

RETURNED TO SERVICE. i i

SALEM UNIT 2 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8508140711 SIC 2 22 S/G LEVEL FAILURE DESCRIPTION: THE LEVEL IS SLOWLY INCREASING IN AUTO. FOR NO OBVIOUS REASON.

CORRECTIVE ACTION: REPLACED ISOLATOR S/N 473 2LM-505B WITH ISOLATOR S/N 00382. TIGHTENED LOOSE WIRE ON I/V BLOCK LC-500C A/R CAUSING ERRATIC RESPONSE OF ORIGINAL ISOLATOR.

8508161565 SIC 2 ISB2 IRPI FAILURE DESCRIPTION: IRPI 12 STEPS BELOW GROUP COUNTER.

CORRECTIVE ACTION: FOUND SIGNAL MODULE AND INDICATOR OUT OF SPEC.

CALIBRATED BOTH IAW 2PD 8.1.003. ALL SAT.

8508202001 SIC 2 2VC8, 2VC12 FAILURE DESCRIPTION: THE VALVES HAD TO BE ASSISTED TO OPEN BY MANUALLY MAKING UP THE OPEN LIMIT SWITCHES.

CORRECTIVE ACTION: VERIFIED STEM TRAVEL ON BOTH VALVES WAS 1/2 INCH.

ADJUSTED LIMIT SWITCHES, VERIFIED OPERATION.

8508240236 SIC 2 VCT H2 PRESSURE REGULATOR FAILURE DESCRIPTION: STILL DOESN'T WORK. VALVED IN TO ADD H2 TO VCT, VALVED IT BACK OUT WITH PRESSURE 44# INCREASING.

l SETPOINT SHOULD BE 30# PER OP II-3.3.10 STEP 5.1.12A.

CORRECTIVE ACTION: RESET REGULATOR TO A SETPOINT OF 35 PSI.

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 AUGUST 1985 SALEM UNIT NO. 2 The Unit began the period operating at full power. On 8/1/85 the Unit was reduced in power to 92% for a brief period due to low level in the Refueling Water Storage Tank. On 8/08/85 at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br /> a Turbine Trip / Reactor Trip occurred due to a loose lead which caused reactor trip breaker "A" to open during functional testing of reactor trip breaker "B". Unit startup was initiated at 1334 hours0.0154 days <br />0.371 hours <br />0.00221 weeks <br />5.07587e-4 months <br /> on 8/10/85. At 213 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> the Unit was brought on line and returned to full power.

On 8/27/85 at 0312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />, a Unit shutdown was commenced due to inoperability of both Component Cooling Heat Exchangers (CCHX) . No.

21CCHX was out for required maintenance and #22CCHX service water flow had been reduced below design due to a valve (22SW356) problem.

Startup was delayed until 8/28/85 as a result of the need to reset the Main Steam safety valve 22MS14. On 8/29/85 at 0806 hours0.00933 days <br />0.224 hours <br />0.00133 weeks <br />3.06683e-4 months <br />, the Unit was brought on line and brought to full power where it remained for the rest of the period.

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REFUELING INFORMATION DOCK ET NO . : 50-311 COMPLETED BY: J. Ronafalvy UNIT NAME: Salem 2 DATE: September 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month August 1985

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: September 6, 1986

3. Scheduled date for restart following refueling: November 16, 1986

4. A) Will Technical Specification changes or other license amendments be required?

YES NO Not determined to date B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? August 1986

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

August 1986 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 19 3 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 tuel pool assuming the present licensed capacity: March 2003 8-1-7.R4

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Public Smico Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station September 10, 1985 i Director,' Office of Inspection and Enforcement  ;

j U.S. Nuclear Regulatory Commission washington, DC 20555 i

Dear Sir:

! t MONTHLY OPERATING REPORT SALEM NO. 2 ,

DOCKET NO. 50-311 I

In compliance with Section 6.9, Reporting Requirements for the Salem

Technical Specifications,-10 copies of the following monthly operating j reports for the month of August 1985 are being sent to you.

Average Daily Unit Power Level -

' Operating Data Report Unit Shutdowns and Power Reductions 1

Major Plant Modification i

Safety Related Work Orders Operating Summary Refueling Information L l Sincerely yours, i

tA p >-1) , -

J. M. Zupko, Jr.

General Manager -

j Salem Operations JR:sbh

} cc: Dr. Thomas E.. Murley i Regional Administrator USNRC l Region I l 631 Park Avenue l King of Prussia, PA 19406 1

! Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission

Washington, DC 20555 4

Enclosure

8-1-7.R4 h I The Energy People mumnuu m J

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