ML20203A298

Monthly Operating Rept for June 1986

ML20203A298
Person / Time
Site:	Salem
Issue date:	06/30/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8607170209
Download: ML20203A298 (13)

Text

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name Salem # 1 Date July 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month June 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 667 17 821 2

1037 18 910 3

1074 19 946 4

1079 20 955 5

1102 21 967 6

680 22 1001 7

124 23 1000 8

917 24 812 9

973 25 637 10 978 26 635 11 961 27 778 12 645 28 999 13 0

29 1008 14 263 30 1014 15 975 16 963 P.

8.1-7 R1 8607170209 860630 PDR ADOCK 05000272 R

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OPERATING DATA REPORT Docket No.50-27 2 Date July 10, 1986 Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status 1.

Unit Name Salem No. 1 Notes 2.

Reporting Period June 1986 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 Upgraded Output to equal Unit #2 l

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 720 4343 78912

12. No. of Hrs. Reactor was Critical 675.7 3146.3 47331.7

13. Reactor Reserve Shutdown Hrs.

0 0

3088.4

14. Hours Generator On-Line 650.8 2996.1 45500.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (PHiH) 1897517 9323199 139807228 137909711

17. Gross Elec. Energy Generated (MWH) 629300 3082940 46378950

18. Net Elec. Energy Generated (;MWH) 598942 2934975 44040467

19. Unit Service Factor 90.4 69.0 57.7

20. Unit Availability Factor 90.4 69.0 57.7

21. Unit Capacity Factor (using MDC Net) 75.2 61.1 50.5

22. Unit Capacity Factor (using DER Net) 74.6 60.6 50.1

23. Unit Forced Outage Rate 8.6 7.3 27.6

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

)

r UNIT onUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH JUNE 1986 Unit Name Salem No.1 Date July 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 3

2 Reactor Report Code 4 Code 5 Prevent Recurrence 478 0531 S

33.5 A

5 CH PUMPXX Feedwater Pump Station Service Transformer Station ED TRANSF Power Auxiliary 492 0606 F

25.8 A

3 Other High Pressure 496 0607 F

0.6 A

5 HA VALVEX Turbine Problems Feedwater Pump Drive 506 0612 F

15.8 A

3 HH TURBIN Steam Turbine Station Service Transformer Station ED TRANSF Power Auxiliary 508 0613 F

7.6-A 4

Other Nuclear Reactor Problems 510 0613 F

20.0 A

3 RA VESSEL Miscellaneous Other Feedwater 512 0614 F

3.0 A

5 CH PUMPXX Pump Problems Other Feedwater 532 0624 F

12.3 A

5 CH PUMPXX Pump Problems Other Feedwater 534 0625 F

31.0 A

4 CH PUMPXX Pump Problems Other Switchyard Equipment Steel EG HANGER Guy Wires Buses 536 0626 F

26.5 A

4 Other Switchyard Equipment Steel EG HANGER Guy Wires Buses 538 0627 F

3.0 A

4 1

2 Reason 3 Method 4 Exhibit G S 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 5-Load Reduction Event Report F-Administrative 9-Other (LER). File G-Operational Error-explain H-Other-explain (NUREG 0161) q

}

1 i

MAJOR PLANT MODIFICATIONS DOCKET NO. :

50-272 REPORT MONTH June 1986 UNIT NAME:

Salem 1 DATE:

Ju ly 10, 1986 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DCR NO.

PRINCIPAL SYSTEM SUBJECT 1ED-0218 Service Water System To permanently locate, setup and provide testing procedure for Clampitrom transducers for determining flows to permit the surveillance of the service water pumps as required by the applicable ASME Section XI code, in-service inspection, in accordance with the Technical Specification.

1EC-0764A Control Room Modify CAACS & EACS Systems to comply with requirements of Controls DM-S-12, PAR 5.4 (page 2).

1EC-1945 VS-Containment Fan Installation of Spring Coil Units assembly in the backdraft damper mechanism of the containment fan coil units Nos. 11, 12, 13, 14, and 15.

DCR - Design Change Request i

MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH June 1986

• DCR NO.

PRINCIPLE SYSTEM SUBJECT ISC-1272 Aux Feedwater System The No. 13 Auxiliary feedwater pump trip valve IMS52 presently does not provide indication in the control room when it is reset and latched.

Please provide indication on the controls bezel to indicate when the trip valve is reset and latched.

1SC-1573 Feedwater Heater Improve the steam sealing Bypass and LE capability of ll-14BF19 valves by using a Chesterton seal-using Belleville washers.

Possible Labyrinth Packing gland.

]

L r

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH June 1986 UNIT NAME:

Salem 1 DATE:

July 10, 1986 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 4

1ED-0218 This is a non-safety related design change.

It will not affect the operation of any safety function.

No plant process or discharge is affected by this design change.

No unreviewed safety or environmental questions are involved.

1EC-07 64 A This design change adds the Control Room corridor onto the Emergency Air Conditioning System to insure that occupancy requirements are met during j

an accident condition.

No plant process or discharge is affected by this design change.

No r.1 reviewed safety or environmental questions are involved.

1EC-1945 The presently installed. dampers in the Fan Coil Unit system are sluggish in closing after the fan is turned off.

The purpose of the dampers.is to prevent back flow through the non-operating fan.

The new spring assembly (outside the airflow) will i

provide the necessary initial momentum-to the counter weights thereby assisting in closing the dampers positively.

The spring assembly will not prevent opening the dampers for fan operation.

Failure of the spring will not jeopardize the operation of the backdraft damper.

This change will not af fect any presently. performed safety analysis nor does it create any new hazards.

No plant process or discharge is affected by this design change.

No unreviewed safety or environmental questions are involved.

1SC-1272 This design change' enhances the operators Control Room indication for the.#13 Auxiliary Feedwater Pump status.

It does not alter any automatic control system or adversely affect the capability s

i to se fely shut down -the Unit.

No plant process 1

or discharge is affected by this design change.

4 No unreviewed safety or environmental questions are involved..

j

• Design Change Request i

I

UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - June 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 ISC-15 73 The packing improvement modification on the BF-19 valves will not affect the operability of the valves.

The modification will minimize the potential for valve stem packing leaks thereby increasing the reliability of the valves.

After packing, the valves were tested to verify performance parameters as per Technical Specification 4.6.3.1.1.

The SAR and the Technical Specification bases are not affected by this modification.

The packing has a manufacturer's certification to meet nuclear grade J

requirements for nuclear power plants.

The modifications will not change any plant process or discharge and will not affect the existing plant i

impact.

No unreviewed. safety or environmental questions are involved.

• Design Change Request i

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

8606120464 1

12 AUX FEED PUMP i

FAILURE DESCRIPTION:

THE 12 AUX FEED PUMP FAILED TO START.

i INDICATION WAS A FLASHING STOP LIGHT.

125V BREAKER WAS CYCLED AND THE PUMP STARTED.

CORRECTIVE ACTION:

REPLACED 4.KV BKR S/N 0244A-6260-006, WITH SERIAL 0224A-6269-010.

BREAKER HAD A LOOSE FITTING CAM ON THE BREAKER CLOSING DRIVE SHAFT.

8606061590 1

-ATMOS. RELIEF FAILURE DESCRIPTION:

11MS10 WOULD NOT OPEN IN AUTO OR MANUAL.

CORRECTIVE ACTION:

BLEWDOWN PILOT AND VERIFIED OPERATION LOCALLY FROM i

CONTROL ROOM.

8606030074 1

POWER RANGE CHANNEL 1 7

FAILURE DESCRIPTION:

POWER RANGE CH 1 HAS INDICATED-A HIGH GAMMA FLUX CONDITION ON RP4 AND OHA.

[

CORRECTIVE ACTION:

FOUND MEMORY CARD A-707 BAD IN DEMULTIPLEXOR CABINET IN41 CHANNEL OPERTING SAT.

REPLACED CARD i

A-707 WITH NEW CARD.

i i

1

- - - + -

. _- _ - = - -

. _ _ = -

i SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION

. 8605271698 1

12MS10 i

FAILURE DESCRIPTION:

12MS10 IS LEAKING BY.

l CORRECTIVE ACTION:

CHECKED CALIBRATION OF E/P.

FOUND OUT OF CAL.

ADJUSTED TO SPEC.

VERIFIED VALVE FULLY CLOSED.

8605270063 1

BAST LEVEL INDICATORS FAILURE DESCRIPTION:

WHEN N2 BANK WAS CUT IN, COMBINED LEVELS JUMPED AND SETTLED OUT 15% ABOVE WHAT THEY WERE.

PLEASE DETERMINE IF CORRECT LEVELS ARE INDICATED.

4 CORRECTIVE ACTION:

CUT TRANSMITTERS OUT OF SERVICE, EQUALIZED AND BLEWOUT BUBBLER LINES, SET REGULATORS (FLOW)

EQUAL AND CUT TRANSMITTERS BACK IN SERVICE.

TRANSMITTERS / INDICATORS ARE SHOWING CORRECT LEVEL.

8605200910 1

PRESSURIZER CONTROL HEATER PHASE "A" FAILURE DESCRIPTION:

PHASE "A"

INDICATES MUCH LOWER THAN.THE OTHER PHASES ALL THE BREAKERS ARE NOT TRIPPED.

CORRECTIVE ACTION:

FOUND BAD WIRE CONNECTION ON TIME PROPORTIONAL HEATER CONTROL BOARD FOR PHASE "A"

ECL.

1 l

i I

1 4

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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8602280866 1

RMS 1R3 FAILURE DESCRIPTION:

1R3 FAILED CORRECTIVE ACTION:

CLEANED, REPAIRED, AND TIGHTENED BLUE RIBBON CONNECTORS.

INSTALLED A NEW DETECTOR.

VERIFIED a

FIELD CABLE OPERABLE.

J l

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 JUNE 1986 SALEM NO. 1 The Unit began the period operating at full power.

On 6/06/86 at 1448 r

hours, the Unit tripped on Generator Protection due to an internal fault in the No. 1 Auxiliary Power Transformer.. On 6/07/86 at 1637 t

hours,-the Unit was synchronized and brought to 90% power.

With No. 1 Auxiliary Power Transformer unavailable, Unit power will be maintained 1

2 at the reduced level (90%) due to cable rating limitations between i

Nos. 11 & 12 Station Power Transformers and their respective group busses.

On 6/12/86 at 1611 hours0.0186 days <br />0.448 hours <br />0.00266 weeks <br />6.129855e-4 months <br />, the Unit tripped on No. 13 Steam Generator (S/G) Steam Flow Feed Flow Mismatch due to the loss of #11-l Steam Generator Feed Pump.

The pump tripped when the inlet valve to the "C" train of the low pressure feedwater heaters closed due to a false high level signal caused by 15C feedwater heater level 4

controller.

The Unit was synchronized on 6/13/86 at 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />.

At t

l 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br />, the same day, the Turbine tripped followed by a Reactor

{

Trip with the Unit at 15% power.

This trip was caused by air entrained in the Main Turbine Lube Oil System which had entered the j

system when the Lube Oil Coolers were changed over.

The Unit was synchronized on 6/14/86 at 1144 hours0.0132 days <br />0.318 hours <br />0.00189 weeks <br />4.35292e-4 months <br /> and returned to 90% power.

On 6/16/86 at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />, Unit power was reduced to 70% in support of the repair of a packing leak on #12 Heater Drain Pump.

The Unit was returned to 90% power on 6/19/86 at 0949 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />.

On 6/24/86 at 1134 I

hours, Unit power was reduced to 60% in support of the repair of a leak on #12 Steam Generator Feed Pump turbine drain header.

The Unit was returned to 90% power on 6/27/86 at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> where it remained for the rest of the period.

A decision has been made to do a complete rewind of the No. 1 Auxiliary Power Transformer.

The transformer should be returned to service by 12/1/86.

4 1

a n-

REFUELING INFORMATION DOCKET NO. :

50-272 COMPLETED BY :

J.

Ronafalvy UNIT NAMB:

Salem 1 DATE:

July 10, 1986 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month June 1986 1.

Refueling information has changed from last month:

YES X

NO 2.

Scheduled date for next refueling:

September 12, 1987 4

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 Fuel Assemblies:

A)

Incore 19 3 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'PSEG Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 10, 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 June 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,

J. M.

upko, Jr.

General Manager - Salem Operations JR:sl cc:

Dr. Thomas E. Murley Regional Administrator USNRP 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 zc2.y The Energy People

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