ML18094B301

Monthly Operating Rept for Jan 1990 for Salem Unit 1.W/

ML18094B301
Person / Time
Site:	Salem
Issue date:	01/31/1990
From:	Miller L, Orticelle A, White P Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9002220668
Download: ML18094B301 (9)

Text

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• Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 12, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of January 1990 are being sent to you.

RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours, L. K. Miller General Manager -

Salem Operations cc:

Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People J

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I 95-21 89 (11 M) 12-84

AVERAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Month JANUARY 1990 Day Average Daily Power Level (MWe-NET) 1 1105 2

1107 3

1107 4

1109 5

1108 6

1115 7

1078 8

1115 9

1113 10 1122 11 1095 12 1127 13 1092 14 1003 15 1097 16 1111 P. 8.1-7 Rl Day Docket No.

~5~0_-=2~7=2~~~~~

Unit Name Salem # 1 Date

~0=2_-=1~0_-~9~0~~~~-

Telephone 609-935-6000

• Extension 4722

-'-=-=~~~~~~-

Average Daily Power Level (MWe-NET) 17 1110 18 1110 19 1020 20 1110 21 1109 22 1110 23 1110 24 1101 25 1101 26 1113 27 1121 28 665 29 1051 30 504 31 1080

OPERATING DATA REPORT Docket No.50-272

~~~~~~~~~-

Completed by Art Orticelle Operating Status Date: 2-10-90 Telephone:

_9_3_5_-_6_0_0_0~~~~

Extension: 4722

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1.

Unit Name Salem No. 1 Notes

2.

Reporting Period January 1990

3.

Licensed Thermal Power (MWt}

3411

4.

Nameplate R~ting (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~-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 744 744 110377

12. No. of Hrs. Reactor was Critical 744 744 71652.6

13. Reactor Reserve Shutdown Hrs.

o.

0 0

14. Hours Generator On-Line 744 744 69439.8

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH}

2454900 2454900 217555826

17. Gross Elec. Energy Generated (MWH}

817690 817690 72279050

18. Net Elec. Energy Generated (MWH}

792443 792443 68804153

19. Unit Service Factor 100 100 62.9

20. Unit Availability Factor 100 100 62.9

21. Unit Capacity Factor (using MDC Net) 96.3 96.3 56.4

22. Unit Capacity Factor (using DER Net}

95.5 95.5 55.9

23. Unit Forced Outage Rate 0

0 21.3

24. Shutdowns scheduled over next 6 months (type, date and duration of each}

NONE

25. If shutdown at end of Report Period, Estimated Date of Startup:

N/A 8-1-7.R2

Completed by No.

Date 0005 01-14-90 0004 01-14-90 0008 01-19-90 0010 01-28-90 0011 01-30-90 1

F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH JANUARY 1990 Unit Name Salem No.l Art Orticelle Method of Duration Shutting Type Hours Reason Down 1

2 Reactor F

5.0 B

5 F

4.5 B

5 F

2.3 B

5 F

6.6 A

5 F

11.7 A

5 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction License Event Report E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain Date 02-10-90 Telephone 609-935-6000 Extension 4722 System Component Code 4 Code 5 HF PUMP XX HF PUMP XX HF PUMP XX HB VAL VEX IB xxxxxx 3 Method 1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther Cause and Corrective Action to Prevent Recurrence 13A&B CIRC. WATER PUMP 13A&B CIRC. WATER PUMP 13A&B CIRC. WATER PUMP TURB. BEARING TRIP TEST MECHANISM DIAPRH. LEAK lA SEC AUTO TEST FAULT 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source

SAFETY RELATED MAINTENANCE MONTH: -

JANUARY 1990 DOCKET NO:

UNIT NAME:

50-272 SALEM 1 WO NO UNIT 890517079 1

900116116 1

900118134 1

900122063 1

900123145 1

DATE:

COMPLETED BY:

TELEPHONE:

FEBRUARY 10, 1990 P. WHITE (609) 339-4455 EQUIPMENT IDENTIFICATION AUX. FEED SPRINKLERS FAILURE DESCRIPTION:

SPRINKLER HEADS IN AUX. FEEDWATER PUMP AREA TOO LOW/RAISE HEADS 1LI501 FAILURE DESCRIPTION:

LOCATE GROUND ON SHIELD FOR 1LI501 SIGNAL WIRE 1RA10153 PLANT VENT RAD. MONITOR FAILURE DESCRIPTION:

PLANT VENT MONITOR SPIKING/

INVESTIGATE 1RA10155 1R41C RAD. MONITOR FAILURE DESCRIPTION:

1R41C RAD. MONITOR INOPERABLE/

TROUBLESHOOT AND CORRECT 1N43A POWER RANGE CHANNEL FAILURE DESCRIPTION:

CHANNEL CALIBRATION FOUND OUT OF SPEC./RECALIBRATE CHANNEL

MAJOR PLANT MODIFICATION~

MONTH: -

JANUARY 1990

• DCR PRINCIPAL SYSTEM lSC-01608 RHR Controls lSC-02018 Service Water

• Design Change Request DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-272 SALEM 1 FEBRUARY 10, 1990 P. WHITE (609) 339-4455 DESCRIPTION This design change separated the damper controls for the RHR Room Coolers.

This design change replaced the existing Service Water supply and return piping for No. 11 Component Cooling Heat Exchanger.

MAJOR PLANT MODIFICATIONS MONTH: -

JANUARY 1990 DOCKET NO:

UNIT NAME:

50-272 SALEM 1

• DCR lSC-01608 lSC-02018 DATE:

COMPLETED BY:

TELEPHONE:

SAFETY EVALUATION 10 CFR 50.59 FEBRUARY 10, 1990 P. WHITE (609) 339-4455 This design change separated the damper controls for the RHR Room Coolers.

The damper controls for the room coolers were relocated to allow separation as per the criteria of Appendix "R".

There was no change to any plant process or discharge or to the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

This design change replaced the existing Service Water supply and return piping for No. 11 Component Cooling Heat Exchanger.

The replacement piping is made of 6% Moly stainless steel for improved erosion and corrosion resistance in the service water environment.

There was no change to any plant process or discharge or to the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

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• DCR -

Design Change Request

SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 1 JANUARY 1990 The Unit began the period operating at 100% power and, with the exception of brief load reductions for waterbox cleaning and stop gate installation, continued to operate at essentially full power until January 28, 1990.

On January 28, 1990, power was reduced to 18% to repair a ruptured diaphragm on a main turbine trip device.

The repairs were completed and the Unit was restored to full power later the same day.

On January 29, 1990, power was reduced to 30% for a brief period to comply with Technical Specification requirements during investigation and repair of a malfunction in the lA SEC.

The Unit was restored to full power on January 30, 1990, and continued to operate at full power throughout the remainder of the period.

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SAFETY RELATED MAINTENANCE DOCKET NO:

MONTH: -

JANUARY 1990 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

MONTH DECEMBER 1989

1.

Refueling information has changed from last month:

YES NO x

2.

Scheduled date for next refueling:

October 6, 1990 50-272 SALEM 1 FEBRUARY 10, 1990 P. WHITE (609) 339-4455

3.

Scheduled date for restart following refueling:

November 19, 1990

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?:

September 1990

5.

Scheduled date(s) for submitting proposed licensing action:

N/A

6.

Important licensing considerations associated with refueling:

7.

Number of Fuel Assemblies:

a.

Incore 193

b.

In Spent Fuel Storage 540

8.

Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170

9.

Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

September 2001 8-l-7.R4