ML20210B729

Monthly Operating Rept for Aug 1986

ML20210B729
Person / Time
Site:	Salem
Issue date:	08/31/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8609180156
Download: ML20210B729 (16)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name Salem # 1

.Date September 10,19.86 Completed by Pell White Telephone 609-935-6J00 Extension 4451 Month August 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1111 17 1101 2

1088 18 997 3

1086 19 1108 4

1080 20 1106 5

261 21 1115 6

1 22 1115 7

0 23 1115 8

0 24 1115 9

0 25 1093 10 0

26 1095 11 7

27 1106 12 640 28 1104 13 1092 29 1086 14 1096 30 1046 15 1107 31 1057 16 1091 P. 8.1-7 R1 8609180156 860831 PDR ADOCK 05000272 R

PDR 1_

OPERATING DATA REPORT-Docket No.50-272 Date September 10,1986 Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status 1.

Unit Name Salem No. 1 Notes 2.

Reporting Period August 1986 3.

Licensed Thermal Power (MWt) 3411 4.

Nameplate Rating (Gross MWe) 1170 5.

Design Electrical Rating (Net MWe) 1115 6.

Maximum Dependable capacityCGross 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 744 5831 80400

12. No. of Hrs. Reactor was Critical 600.1 4341.8 48527.2

13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 590.7 4175.8 46680.6

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1963392 13184429 143668458

17. Gross Elec. Energy Generated (MWH) 651510 4367480 47663490

18. Not Elec. Energy Generated (MWH) 623055 4161717 45267209-

19. Unit Service Factor 79.4 71.6 58.1

20. Unit Availability Factor 79.4 71.6 58.1

21. Unit Capacity Factor (using MDC Net) 75.7 64.5 50.9

32. Unit Capacity Factor (using DER Net) 75.1 64.0 50.5

23. Unit Forced Outage Rate 20.6 11.5 27.4

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 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Dockot No.50-272 REPORT MONTH AUGUST 1986 Unit N;m2 5 Ad t m No.1 Date September 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No.

Date Type Hours Reason Down Event System Component Action to 1

2 Reactor Report Code 4 Code 5 Prevent Recurrence 616 0805 F

22.1 A

3 CH PUMPXX Feedwater Pump 618 0806 F

3.8 A

4 CH PUMPXX Feedwater Pump 620 0806 F

.5 A

4 CH PUMPXX Feedwater Pump Plant Mod Strictly for Compliance With New or changed 622 0806 F

131.1 D

1 ZZ CKTBRK Reg Rea 624 0811 F

16.5 A

5 CH PUMPXX Feedwater Pump Feedwater Pump 644 0818 F

.7 A

5 CH PUMPXX Local Controls 1

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

for Prepara-Source 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 F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH AUGUST 1986 UNIT NAME:

Salem 1 DATE:

September 10, 1986 COMPLETED BY:

L. Miller TELEPHONE:

609/339-4497

• DCR NO.

PRINCIPAL SYSTEM SUBJECT 1EC-0692 Fire Protection Install automatic halon 1301 total flooding fire protection system in the Relay Room to maintain 7% halon concentration for 20 minutes.

1EC-1375 Steam Generator Feed Install motor operators on all

&' Condensate four BF 22'stop check valves.

1EC-1710 VS - Control &

Modify the existing control Relay Rooms circuit on each EACS fan by adding a stop feature. Also, add amber low flow indicating light to the CMC switch for fan failure.

1EC-1872 VS - Containment Fan Replacement of' Butyl expansion Coil Units joints at ECU discharge end for Containment Fan Coil Unit

1. 's 11, 12, 13, 14 and 15 with expansion joints made of EPDM material.

• DCR - Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH AUGUST 1986 UNIT NAME:

Salem 1 DATE:

September 10, 1986 COMPLETED BY:

L.

Miller TELEPHONE:

609/339-4497

• DCR SAFETY EVALUATION'10 CFR 50.59 1EC-0692 The installation of the automatic Halon 1301 Fire Protection System in the Relay Room is in compliance with ansNRC request.

This modification enhances.the plant protection against fire.

Additionally, installation of this system does not increase or change any plant emissions.

Therefore, no unreviewed safety or environmental questions are involved.

1EC-1375 Limitorque motor operators ensure positive closure of the BF22 stop check valves to preclude release or radioactivity to the environment because of seat leakage.

The electric operators are not required to be automatically activated during a unit trip or a containment isolation signal.

They are also not required or designed to close against normal feedwater flow.

In any given situation when the BF22 valves need positive closure, the operators can be activated from the control room.

Necessary alarms and indicators to display valve position and motor availability are provided.

The modifications enhance compliance to General Design Criteria 57 and do not create any unreviewed safety questions or reduce the margin of safety or alter previous analysis.

This modification does not alter any plant process or discharge.

No l

unreviewed safety or environmental questions are involved.

I 1EC-1710 The modifications provide stop and alarm features I

to two independent channels.

The function of having one of two fans availabic remains unchanged.

This modification, as required by the Technical Specifications, ensures the 1/4" wc differential pressure in the control room with respect to the outside.

No unreviewed safety or environmental questions are involved.

• Design Change Request i

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i UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - AUGUST 1986 i

• DCR SAFETY EVALUATION 10 CFR 50.59 lEC-1872 The replacement joint is made of elastomer vulcanized to two plies of corrosion resistant knit wire to form a tough, honogeneous wall joint and is better qualified to withstand the

-environmental conditons inside the contadrment after an accident.

Loss, in the sense of a hole or tear in any one of the expansion joints will not impair the containment cooling cepability j

since only three out of five containment fan coil units are required to mitigate the consequences of' a design basis accident.

Use of the new expansion i

joints does not affect any presently performed j

safety analysis or create any new safety hazards.

This modification does not change any plant i

process or discharge or affect the existing plant impact.

No unroviewed safety or environmental l

questions are involved, i

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• Design Change Request t

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 0099180839 1

N2 ACCUM FILL VALVE 12 ACCUM FAILURE DESCRIPTION:

VALVE WILL'NOT STROKE'OPEN.

PLEASE REPAIR.

CORRECTIVE ACTION:

CLEANED AND RETIGHTENED LEAD WIRES.

CYCLED VALVE VERIFIED LIMITS WITH CONTROL ROOM.

0099181606 1

1. 13 CHARGING PUMP FAILURE DESCRIPTION:

PUMP IS LEAKING THRU PACKING WITH PUMP I/S RCS LEAKAGE WAS 97 GPM WITH PUMP O/S AND ISOLATED LEAK RATE WAS 32 GPM PLEASE REPAIR.

CORRECTIVE ACTION:

REPLACED PLUNGER AND REPACKED #2 CYLINDER.

0099182271 1

11 AFP BREAKER FAILURE DESCRIPTION:

11 AF PP BREAKER DID NOT DISCHARGE WHEN IT WAS PE: ACTED.

PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION:.

ADJUSTED DISCH BRACKET, BREAKER DISCHARGED WHEN RACKET DOWN.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8606160172 1

13 CHARGING PUMP FAILURE DESCRIPTION:

CHARGING PUMP SEAL TANK IS OVERFLOWING DUE TO SEAL LEAKAGE IN EXCESS OF 1 GPM.

PLEASE REPAIR.

CORRECTIVE ACTION:

REPLACED 2 PLUNGERS, PACKING, THROAT BUSHINGS, GLAND FOLLOWER, PRIMARY FOLLOWER.

REUSED ALL SPRINGS AND SECONDARY GLAND O-RINGS.

8606270261 1

1CC264 3/4" GLOBE FAILURE DESCRIPTION:

PACKING LEAK.

REPACK WITH CHESTERTON PACKING.

DRAWING 205231 SHEET 2 (D 5).

CORRECTIVE ACTION:

REPACKED VALVE WITH CHESTERTON PACKING AND TORQUED TO 5 FT LBS PER PROCEDURE MP7.8, REPLACED PACKING GLAND STUDS.

REPAIRED BONNET GASKET.

8607101056 1

11CCHX SW CONTROL VALVE FAILURE DESCRIPTION:

IN AUTO VALVE CONTINUALLY CYCLES OPEN AND CLOSED.

CORRECTIVE ACTION:

VALVE WAS REMOVED AND ACTUATOR REMOVED FOR MAINTENANCE WORK 86-07-29-048-7.

VALVE WAS STROKED USING CONTROLLER AND CHECKED SATISFACTORY.

VERIFIED CONTROLLER STABLE AND VALVE ACTION SIGNAL NOT CYCLING.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8608050552 1

P-4's & BREAKERS FAILURE DESCRIPTION:

PLEASE PERFORM 11C-18.1.006 AND IIC-18.1.007 WITHIN TWENTY FOUR HOURS OF UNITS l's STARTUP.

CORRECTIVE ACTION:

PERFORMED IIC-18.1.006 AND IIC-18.1.007 ON REACTOR TRIP BREAKERS AND BYPASS BREAKERS.

EVERYTHING SATISFACTORY.

8608080443 1

RX TRIP BREAKER &

TURBINE TRIP SOLENOID FAILURE DESCRIPTION:

VERIFY RX TRIP BREAKER AND TURBINE TRIP SOLENOID ACTUATION TIMES FROM 11 S/G LO FLOW COINCIDENT WITH LO LEVEL RX TRIP.

(TO SATISFY AD-16).

CORRECTIVE ACTION:

VERIFIED TIMES.

REACTOR MAIN TRIP BREAKER B TRIP 5 CYCLES.

REACTOR MAIN TRIP BREAKER A TRIP 6 CYCLES.

TURBINE REMOTE EMERG TRIP 7 CYCLES.

8608080672 1

LEAK TEST VALVE ROOM COVERS FAILURE DESCRIPTION:

LEAK RATE TEST THE 11SJ44 AND THE 12SJ44 VALVES ROOM COVERS IN ACCORDANCE WITH PROCEDUP.E M9-ILP-CT-3.

THESE LEAK RATES ARE DUE TO THE LIMITORQUE OPERATOR E.Q.

INSPECTIONS. (12SJ44)

CORRECTIVE ACTION:

PERFORMED A LEAR RATE TEST ON 11 AND 12SJ44 VALVE ROOM COVERS WITH AN ACCEPTABLE LEAKAGE AS FOLLOWS:

11SJ44 - 7.0 SCCM LEAKAGE 12SJ44 - 1.5 SCCM LEAKAGE

i SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 0099182327 1

BREAKER 12BSD FAILURE DESCRIPTION:

4KV BREAKER FOR 1B VITAL BUS INFEED 1,

12BSD, INADVERTENTLY OPENED.

PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION:

CHECKED CONTROL CIRCUIT AND ALL MULTI TRIPS, FOUND NO PROBLEM AT THIS TIME, VISUAL INSPECTION OF

)

WIRES PERFORMED.

1 l

8310300216 1

LIQUID WASTE FAILURE DESCRIPTION:

REPLACE THE EXISTING RHR SUMP PUMPS (CHEM PUMP)

WITH PORTABLE SUBMERSIBLE TYPE TRASH PUMPS,

)

MODIFY THE EXISTING MO'UNTING PLATES AND INSTALL l

FLEXIBLE STAINLESS STEEL PIPING TD ALLOW FOR I

i REMOVAL AND CLEANING.

I f

CORRECTIVE ACTION:

REPLACED PUMPS, PLATES, SUPPORTS AND RELATED PIPING PER DCR REQUIRED.

J 8605150149 1

11 CONT. SPRAY ROOM COOLER FAILURE DESCRIPTION:

INSPECT FOR ACCUMULATION OF SILT AND CORROSION /

PITTING AT THE WATER BOX AND FLANGED AREA PER FIELD DIRECTIVE S-1-M600-MFD-0350.

CORRECTIVE ACTION:

OPENED AND INSPECTED AND CLOSED BACK UP.

SYSTEM WILL BE MADE UP TO DETERMINE WHAT IS NECESSARY TO CLEAN SYSTEM UP, REMOVED COOLER IIEAD FOR INSPECTION, REINSTALLED AFTER INSPECTION.

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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8607310712 1

ILT528 CH FUNCTION FAILURE DESCRIPTION:

REACTOR PROT SYSTEM.

PERFORM CHANNEL FUNCTION TEST ON LOOP ILT528.

CORRECTIVE ACTION:

PERFORMED CHANNEL FUNCTION TEST IIC-2.6.044 FOUND 1BS528B TRIPPING OUT OF TECH SPEC.

REPLACED C2 AND C3 VERIFIED TIRP SETPONT AS PER IIC-2.2.044 PAGE 16 COMPLETED FUNCTION.

8008011646 2

13 S/G A.F.

FLOW INDIC.

FAILURE DESCRIPTION:

INDICATION OF AUX. FEED FLOW TO 13 S/G IS BOUNCING.

PLEASE INVESTICATE AND REPAIR.

CORRECTIVE ACTION:

FOUND CCNTROL CONSOLE INDICATOR FA-5753IB OSCILLATING.

CONTROL OPERATOR RAM #11 AUX FEED PUMP AND TOOK OUT OF SERVICE INDICATION ON FA-5753IB WENT TO ZERO AND STOPPED OSCILLATING.

l 8603050412 1

STEAM DUMPS FAILURE DESCRIPTION:

PLEASE INVESTIGATE STEAM DUMP SYSTEM FOR POSSIBLE PROBLEMS OBSERVED DURING TRIP OF 8/5/86.

l CORRECTIVE ACTION:

AFTER ANALYZING TRIP OPERATOR FEEL,S THAT STEAM DUMP OPERATION WAS SATISFACTORY.

AS PER A.

ORTICELLE.

NO WOFK PERFORMED.

1 i

SALLM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 860809G325 1

LEAK RATE TEST ICV 69 FAILURE DESCRIPTION:

LEAK RATE TEST VALVE 1CV69 IN ACCORDANCE WITH PROCEDURE M9-ILP-CT-3.

THIS VALVE IS BEING LEAK RATE TESTED, BECAUSE A NEW TORQUE SWITCH WAS INSTALLED.

CORRECTIVE ACTION:

ABORTED TEST, BOUNDRY DID NOT HOLD.

AN INCIDENT WILL BE WRITTEN TO DECLARE THE 1CV69 VALVE INOPERABLE 8608130335 1

REACTOR VESSEL LEVEL FAILURE DESCRIPTION:

REMOTE DISPLAY IN CONTAINMENT ROOM INTERMITTENTLY FAILS TO COMMUNICATE WITH THE MICROPROCESSOR, REQUIRING RESET AND OR POWER RESET.

REWORK AS NECESSARY.

CORRECTIVE ACTION:

FOUND POWER SUPPLY PS1 ON CARD A10 FAILED.

8608150760 1

EXHAUST FAN FAILURE DESCRIPTION:

WHEN STARTED, CONTROL ROOM DOES NOT GET RED START LIGHT ON CMC SWITCH AND GREEN STOP LIGHT FLICKERS.

PLEASE REPAIR.

CORRECTIVE ACTION:

REPLACED 6X RELAY THAT WAS BURNED TO A CRISP, STILL NO INDICATION, PROBLEM IS IN THE DAMPER SWITCHES, REPLACED SOLENOID COIL.

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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8608181819 1

CFCU DISCHARGE FAILURE DESCRIPTION:

THE INDICATION FOR R13A IS TOO LOW.- PLEASE INVESTIGATE AND REPAIR.

CORRECTIVE ACTION:

CHECK SOURCE WAS STUCK ON 1R13F CAUSING IT TO READ 3K WHEN THE % OF BACKGROUND IS SUBSTAINED FROM R13A IT CAUSED IT TO READ ZERO BECAUSE THREE CHANNELS DO NOT READ NEGATIVE.

8608221012 1

PENETRATION FAILURE DESCRIPTION:

THE ABOVE MENTIONED PENETRATION, LOCATED ON THE NORTH WALL IN THE BIT ROOM, IS NOT SEALED.

COULD YOU PLEASE INVESTIGATE'AND REPAIR.

ANY QUESTIONS CONTACT SITE PROTECTION AT EX 4017.

CORRECTIVE ACTION:

SEALED PENETRATION #1424C40003N, LOCATED IN SERVICE WATER PIPING ALLEY, WITH KAOWOOL AND SEMKIT., READY FOR INSPECTION BY SITE PROTECTION.

SALEM GENERATING STATION MONTIILY OPERATING

SUMMARY

- UNIT NO. 1 AUGUST 1986 SALEM NO. 1 The Unit began the period in Mode 3 (Hot Standby).

On July 28, 1986 at 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> Unit Startup commenced.

At 0649 hours0.00751 days <br />0.18 hours <br />0.00107 weeks <br />2.469445e-4 months <br /> (the same day) the Unit was synchronized and brought to full power operation.

On l-August 5, 1986 at 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br />, the Unit tripped on #12 Steam Generator (S/G) Low-Low Level due to #11 Steam Generator Feed Pump (SGFP) tripping on overspeed protection.

The pump experienced overspeed when I

a suppression diode in the Governor actuator controls failed.

On l

August 6, 1986 at 0421 hours0.00487 days <br />0.117 hours <br />6.960979e-4 weeks <br />1.601905e-4 months <br /> the Unit was synchronized.

At 0839 hours0.00971 days <br />0.233 hours <br />0.00139 weeks <br />3.192395e-4 months <br /> on August 6, 1986, the Unit tripped on #11 S/G Low Level in conjunction with Feed Flow / Steam Flow mismatch.

No. 12 SGFP had experienced a runback to minimum speed during troubleshooting of the previous days problem with No. 11 SGFP.

The runback was caused by j

personnel inadvertently " earth grounding" the circuit common in the feed pump controls.

Cooldown to Mode 5 commenced on August 6, 1986 at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> to nupport environmental qualification inspection / repair of Limitorque motor operated valves.

With completion of the investigation / repairs, the Unit was brought to Mode 4 at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on August 10, 1986. ~On August 11, 1986 at 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br /> the Unit was synchronized and brought to full power.

The Unit operated at 100%

power for.the remainder of the period, except for approximately eight (8) hours on August 18, 1986, when a load reduction to 60% was required to clear a plugged sensing line on No. 12 Steam Generator Feed Pump.

o REFUELING INFORMATION DOCKET NO.:

50-272

' COMPLETED BY:

L.K. Miller UNIT NAME:

Salem 1 DATE:

September 10, 1986 TELEPHONE:

609/935-6000 EXTENSION:

4497 Month August 1986 1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

September 12, 1987 3.

Scheduled date for restart following refueling: November 26, 1987 4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE X

B)

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X

If no, when is it scheduled?

August 1987 5.

Scheduled date(s) for submitting proposed licensing action:

August 1987 if required 6.

Important licensing considerations associated with refueling:

NONE

-=

7.

Number of Fucl Acccmblice:

A)

Incore 193 B)

In Spent Fuel Storage 380 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:

September 2001 8-1-7.R4

O PSIEG PubCc Service Elmtoc anrf Gm Company P O Box E Hancocks Bhdy!, Nev/ Jorsey 08038 Salem Generating Station September 11, 1986 Director, Office of Inspection and Enforcement U.S.

Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 August 1986 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, okJ J.

M.

,,upko, Jr.

General Manager - Salem Operations JR:al cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management U.S.

Nuclear Regulatory Commission Document Control Desk washington, DC 20555 Enclosures 8-1-7.R4 M

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