ML20199D021

Monthly Operating Rept for May 1986

ML20199D021
Person / Time
Site:	Salem
Issue date:	05/31/1986
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8606180476
Download: ML20199D021 (13)

Text

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O OPERATING DATA REPORT Docket No.50-272 Date June 10, 1986 Telephone 935-6000 Completed by Pell White Extension 4451

' Operating Status 1.

Unit Name Salem No. 1 Notes 2.

. Reporting Period

'May 1986 3.

Licensed Thermal Power. (MWt) 3338 4.

Nameplate Rating (Gross MWe).

1776 5.

Design Electrical Rating (Net MWe) 1090 6.

Maximum Dependable Capacity (Gross MWe)TTll 7.

Maximum Dependable Capacity (Net MWe) T377 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report,.Give Reason-N/A 9.

Power Level Lto 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 3623 78192

12. No. of Hrs. Reactor was Critical 636.6 2470.6 46656.0

13. Reactor Reserve Shutdown Hrs.

0 0

3088.4

14. Hours Generator On-Line 582.1 2345.3 44850.1

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1774258 7425682 137909711

17. Gross Elec. Energy Generated (MWH) 580780 2453640 45749650

18. Net Elec. Energy Generated (MWH) 550390 2336033 43441525

19. Unit Service Factor 78.2 64.7 57.4

20. Unit Availability Factor 78.2 64.7 57.4

21. Unit Capacity Factor (using MDC Net) 68.6 59.8 51.5

22. Unit Capacity Factor (using DER Net) 67.9 59.2 51.0

23. Unit Forced Outage Rate 3.0 6.9 27.8

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 8606100476 860531 PDR ADOCK 0D000272 R

PDR t

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AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name

-Salem # 1 Date June 10,1986 Completed by Pe11' White Telephone 609-935-6000 Extension 4451 Month May 1986 Day-Average Daily Power Level.

Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 0

17 1092 2

0-18 967 3

0 19 1096 4

0 20 1080 5

0 21 1085 6

52 22 1068 7

160 23~

1066 8

520 24 1030 9

831 25 1101 10 975 26 1099 11 1029 27 1095 12 844 28 1100 13 116 29 1097 14 702 30 1044 15 1083 31 710 16 1100 P. 8.1-7 R1 L-

F'

' Docket, No.50-272 '

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1986 Unit-Name:S91em No.1 Dato Jun7 10,1986-Telephone 609-935-6000 Completed by Pell' White Extension 4451 Method of Cause and Corrective Duration Shutting License Action to No.

-Date Type Hours Reason Down Event System Component

_ Prevent Recurrence 1

2 Reactor Report Code 4 Code 5 ZZ ZZZZZ Turbine Overspeed 388 0507

-F 1.6 B

1 Trip test HA' TURBIN Rotor Shaft Turbine LP 390 0507 F

4.1 B

4 Reactor Performance 392 0509 F

3.4 B

5 ZZ ZZZZZ Testing Reactor Performance ZZ ZZZZZ Testing 394 0509 F

6.0 B

5 CH PUMPXX Feedwater Pump 408 0512 F

18.2 A

3 Moisture Separator 410 0514 F

5.7 A

5 HB HTEXCH Reheater CH PUMPXX Feedwater Pump 418 0518 F

1.4 A

5 Other Nuclear 474 0530 S

0.1 A

5 RA VESSEL Reactor Problems Misc.

476 0531 S

7.5 A

5 CH PUMPXX Feedwater Pump 478 0531 S

10.5 A

5 CH PUMPXX Feedwater Pump 3 Method 4 Exhibit G 5 Exhibit 1 1

2 Reason 1-Manual

-Instructions Salem as F: Forced A-Equipment Failure-explain 2-Manual Scram.

for Prepara-Source S: Scheduled B-Maintenance or Test 3-Automatic Scram. tion of Data C-Refueling 4-Continuation of Entry Sheets D-Regulatory Restriction E-Operator Training & Licensing Exam Previous Outage for Licensee 5-Load Reduction Event Report F-Administrative G-Operational Error-explain 9-Other (LER) File (NUREG 0161)

-H-Other-explain

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH MAY 1986 UNIT-NAME:

Salem 1 DATE:

June 10, 1986 COMPLETED BY:

J.

Ronafalvy TELEPHONE:

609/339-4455

• DCR NO.

PRINCIPAL-SYSTEM SUBJECT 1EC-1477 Solenoid Valves Replace internals of solenoid valves SV0519, SV0397, SV0399, SV0401, SV0506, SV0518, SV0519, SV0520, SV0521, SV0910, SV0911, SV0912, SV0913, SV0914, SV0915, SV1077, SV1079, SV1081, SV1083, SV1384, and SV1385 with resilient seated valve internals.

IEC-1770 Fire Protection Wrap "B" diesel control cable System tray 1A217 Between tray 1A258 and 1A218 with ES195, one hour rated fire barrier material.

1EC-1874A Service Water Revise the 8" SW emergency System supply line to the Auxiliary Feedwater system (AFS) from No.

12 SW nuclear header; revise the 4" SW supply line to the room and oil coolers from No. 12 SW nuclear header; line or replace the stainless steel SW supply and return piping to No. 12 Component Cooling Heat Exchanger (CCHX) ; add break flanges in the SW supply and return piping to No. 12 CCHX.

1EC-1904 Aux. Feedwater Relocate the (4) Aux. feedwater System flow transmitter square root extractors and power feed switches to the 84' switchgear room which is a benign environment area.

DCR - Design Change Request

MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH MAY 1986

• DCR NO.

PRINCIPLE SYSTEM SUBJECT ISC-1124 Containment Spray-Provide a hard pipe for System containment spray cavity fill line.

Pipe should be same size as containment spray test line.

A flexible hose with quick disconnects can be used in the polar crane track area but should be minimized.

Also, designate a storage area for the pipe when not in use.

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• DCR - Design Change Request

-MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272 REPORT MONTH MAY 1986 UNIT NAME:

Salem 1 DATE:

June 10, 1986 COMPLETED BY:

J.

Ronatalvy TELEPHONE:

609/339-4455

• DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1477 No changes are being made (with this design change) which change the qualification, function or fit of any equipment.

No additional equipment is being installed.

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

No unreviewed safety or environmental questions are involved.

1EC-1770 This design change wraps the "B" Diesel Control Cable Tray with one hour fire rated barrier material.

No functional changes are involved.

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

No unreviewed safety or environmental questions are involved.

1EC-1874A The Service Water replacement piping will prevent the buildup of marine growth on the pipe wall and will prevent corrosion thereby ensuring the integrity of the system.

The emergency supply to the Aux. Feedwater System and. the supply to the Room Coolers have been revised.

This modification will allow the Aux. Feedwater line to be isolated from the system thereby eliminiating the buildup of marine growth and silt in this line.

The supply line will subsequently operate more efficiently.

The addition of the brake flanges allows for future inspections to verify the integrity of the system.

These changes have no impact on the safe shutdown of the plant.

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

No unreviewed safety or environmental questions are involved.

1EC-1904 This change meets all the design requirements (e.g., seismic I).

The function of the equipment has not been modified.

This change meets NUREG 0737 requiremetns.

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

No unreviewed safety or environmental questions are involved.

Design Change Request

UNIT 1 MAJOR PLANT MODIFICATIONS (continued)

REPORT MONTH - MAY 1986

• DCR SAFETY EVALUATION 10 CFR 50.59 ISC-ll24

.This temporary hard pipe will only be utilized during Modes 5 and 6.

Prior to the Unit being placed back on line, the piping will be dismantled and placed in-Seismic I supported tiedown structures inside the Containment for storage.

This temporary hard pipe will not cause an accident or malfunction not previously mentioned / analyzed in the FSAR. 'The installation will not increase the probability of the occurrence of an accident.

The hard pipe replaces an existing hose and will not thrash around hazardously as did the hose.

No plant process or discharge is affected this design change.

No unreviewed safety or environmental questions are involved.

l

• Design Change Request

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 1

WO NO UNIT EQUIPMENT IDENTIFICATION 0099194583 1

100 ELEVATION AIR LOCK FAILURE DESCRIPTION:

INTERLOCKS ON 100 ELEVATION AIR LOCK BROKEN SUCH THAT INNER DOOR CANNOT BE OPENED.

CORRECTIVE ACTION:

REPLACED CAM FOLLOWERS 8604290559 1

CHANNEL C & D HI ALARM FOR 14 ACCUMULATOR HI LEVEL ALARM DID NOT OPERATE WHILE FILLING IT ABOVE FAILURE DESCRIPTION:

THE HI ALARM SETPOINT ON EITHER BEZEL CHANNEL.

CORRECTIVE ACTION:

COMPARATOR 1LC-934D/H OUTPUT f1 TRIPS IN SPEC.

COMPARATOR ILC-935 IN OUTPUT #1 TRIPS IN SPEC.

REPLACED REFLASH CORDS.

8605030275 1

til AUX. SUMP TANK PUMP FAILURE DESCRIPTION:

460V BREAKER WILL NOT TURN ON.

CORRECTIVE ACTION:

REPLACED DEFECTIVE BREAKER.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8605060808 1

llBF19 & llBF40 FAILURE DESCRIPTION:

llBF19 AND llBF40 ARE NOT CONTROLLING PROPERLY.

CORRECTIVE ACTION:

REPLACED CAPACITOR ON LLC-500A.

REPLACED lHC5001 WITH S/N 20144.

VERIFIED PROPER OPERATION.

8605060816 1

13BF19 & 13BF40 FAILURE. DESCRIPTION:

13BF19 AND 13BF40 ARE NOT CONROLLING PROPERLY..

CORRECTIVE ACTION:

REPLACED SUMMATOR 575 WITH 632'AT 1FM-530E.

VERIFIED PROPER OPERATION.

8605061189 1

LOW LOAD FEED REG VALVE (14BF40)

FAILURE DESCRIPTION:

VALVE WILL NOT CLOSE.

CORRECTIVE ACTION:

REPLACED BROKEN POSITIONER LINKAGE COUPLING AND VERIFIED PROPER STROKE OF VALVE.

i

SALEM UNIT 1 WO NO UNIT. EQUIPMENT IDENTIFICATION

^ 8605100125 1

13 S/G LEVEL CONTROL VALVE FAILURE DESCRIPTION:

VALVE HAS STEAM LEAK FROM A FURMANITE FITTING.

CORRECTIVE ACTION:

FURMANITE FITTING RETIGHTENED.

I 8dd5131021 1

PRT HI/LO ALARM FAILURE DESCRIPTION:

HIGH LEVEL ALARM INOPERABLE.

VERIFIED TRIP POII4TS AND ALARM CIRCUITRY GOOD VIA TIIE PROCESS RACKS.

CORRECTIVE ACTION:

REPLACED PC BOARD.

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 MAY 1986 SALEM NO. 1 The Unit began the period in Mode 3 (Hot Standby) with surveillances being performed in preparation for power operation (as the sixth refueling outage draws to a close).

On May 7, 1986 at 0839 hours0.00971 days <br />0.233 hours <br />0.00139 weeks <br />3.192395e-4 months <br />, the Unit was synchronized and power ascension to full power operations began.

On May 12, 1986 at 1954 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.43497e-4 months <br />, the Unit tripped on "#14 Steam Generator Feed Water Flow & Low Level" which was due to the loss of both Steam Generator Feed Pumps (SGFP's).

The loss of the SGFP's was due to a defective limit switch in the pump trip circuitry.

On May 13, 1986 at 1407 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.353635e-4 months <br />, the Unit was synchronized and power ascension was initiated.

During power ascension a steam leak on #11E Moisture Separator Reheater was repaired.

On May 17, 1986 at 2114 hours0.0245 days <br />0.587 hours <br />0.0035 weeks <br />8.04377e-4 months <br />, power was reduced to 68% in order to blowdown #11 SGFP suction strainer which had high differential pressure across it.

The Unit was returned to full power operation at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on May 18, 1986.

During the period from May 23, 1986 to May 25, 1986 minor load reductions were required due to high river grasses and debris causing Circulating

' Water System problems.

On May 30, 1986 at 2157 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.207385e-4 months <br />, the first of two load rejection tests was conducted. Unit load was reduced to 60%

(from 100%) at a rate of 10%/ minute.

The Unit was returned to 100%

power at 2206 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.39383e-4 months <br /> the same day.

On May 31, 1986 at 0558 hours0.00646 days <br />0.155 hours <br />9.22619e-4 weeks <br />2.12319e-4 months <br />, the second load rejection test was conducted.

Unit load was reduced to 56% at a rate of 200%/ minute.

At 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> the same day power ascension was initiated.

Power was held at 67% to replace the suction strainer on #11 Steam Generator Feed Pump -(SGFP).

On June 1, 1986 at 2258 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.59169e-4 months <br />, the Unit resumed power ascension to full power.

i

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REFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

J.

Ronafalvy UNIT NAME:

Salem 1 DATE:

June 10, 1986 J

TELEPHONE:

609/935-6000 EXTENSION:

4455 Month May 1986 1.

Refueling information has changed from last month:

YES X

NO 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 L

l 7.

Number of Fuel Assemblies:

A)

Incore 193 B)~

In Spent Fuel Storage 380 l

l 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

D PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June 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 May 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.

Zupko, Jr.

General Manager - Salem Operations JR:sl 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 T6 zy The Energy People j

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