ML18093A733

Monthly Operating Rept for Feb 1988

ML18093A733
Person / Time
Site:	Salem
Issue date:	02/29/1988
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8803210435
Download: ML18093A733 (10)

Text

1-\\VERAGE DAILY UNIT POWER LEVEL Completed by Pell White Docket No.

Unit Name Date Telephone Extension Month FEBRUARY 1988 Day Average Daily Power (MWe-NET) 1 688 2

1095 3

1123 4

1082 5

10 99 6

1088 7

1103 8

1090 9

1101 10 1087 11 1111 12 1098 13 10 99 14 478 15 906 16 1068 Pg. 8.1-7 Rl 8803210435 880229 PDR ADOCK 05000311

• R DCD Level Day Average Daily (MWe-NET}

17 1085 18 1101 19 1083 20 1082 21 1092 22 1084 23 1105 24 1102 25 1077 26 1095 27 1095 28 1098 29 10 98 50-311 Salem # 2 March 10, 1988 609-935-6000 4451 Power Level

e OPERATING DATA REPORT Completed by Pell White Operating Status Docket No.

Date Telephone Extension 50-311 March 10,1988 935-6000 4451

1.

2.

3.

4.

5.

6.

7.

8.

Unit Name Salem No. 2 Notes Reporting Period February 1988 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) 1170 Design Electrical Rating (Net MWe) 1115 Maximum Dependable Capacity(Gross MWe)ll49 Maximum Dependable Capacity (Net MWe) 1106 If Changes Occur in Capacity Ratings (items 3 through 7)

Report, Give Reason since Last N/A

9.

Power Level to Which Restricted, if any (Net MWe)

N/A

~~~~~~~~~~~~

10. Reasons for Restrictions, if any N/A

~~~~~~~~~~~~~~~~~~~~~

11. Hours in Reporting Period

12. No. of Hrs. Reactor was Critical

13. Reactor Reserve Shutdown Hrs.

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Elec. Energy Generated (MWH)

18. Net Elec. Energy Generated (MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (using MDC Net)

22. Unit Capacity Factor This Month 696 69 6 0

696 0

2298118 762980 732279

--100--

100 95.1 Year to Date 1440 1440 0

1436.3 0

4788944 1594060 1530929 99.7 99.7 96.1 Cumulative 55945 33802.9 0

32718.1 0

50439465 33223530 31550307 58.5 58.5

51. 0 (using DER Net) 94.4 95.3 50.6

23. Unit Forced Outage Rate 0

0.26 30.1

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 8-1-7.R2

Completed by No.

Date 0020 1-31-88 0021 2-1-88 0031 2-14-88 0032 2-14-88 1

F: Forced S: Scheduled UNIT SHU TD OWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH FEBRUARY 1988 Unit Name Salem No.2 Pell White Method of Duration Shutting License Type Hours Reason Down Event 1

2 Reactor ReE ort F

7. 3 A

5 F

6. 4 A

5 F

1. 0 H

5 F

16. 2 H

5 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain Date March 10,1988 Telephone 609-935-6000 Extension 4451 System Component Code 4 Code 5 CH INSTRU CH INSTRU WE FILTER HC HT EX CH 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 STEAM GENERATOR FEED PUMP LOCAL CONTROLS STEAM GENERATOR FEED PUMP LOCAL CONTROLS CIRCULATING WATER INTAKE PROBLEM HIGH CONDENSER BACK PRESSURE 4

Exhibit G 5

Exhibit Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Salem as A Source

WO NO 870724034 870922108 871221169 871228120 880115161 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2

2A DIESEL PRELUBE FAILURE DESCRIPTION:

2A DIESEL PRELUBE PIPING LEAKS.

REWORK PIPING.

2 21 SW STRAINER FAILURE DESCRIPTION:

21 SERVICE WATER STRAINER HAS A. BROKEN SHEAR KEY.

TROUBLESHOOT AND CORRECT.

2 22 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:

22 WASTE GAS COMPRESSOR IS SEIZED.

OPEN AND INSPECT.

2 21 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:

21 WASTE GAS COMPRESSOR TRIPS WHEN ENERGIZED.

TROUBLESHOOT AND REWORK.

2 2Rl3C FAILURE DESCRIPTION:

2Rl3C/ 22 & 23 CFCU RADIATION MONITOR.

MONITOR IS FAILED.

WO NO 880126090 880208145 UNIT EQUIPMENT IDENTIFICATION 2

FHB SUPPLY FAN INLET DAMPER SALEM UNIT 2 FAILURE DESCRIPTION:

FHB SUPPLY FAN INLET DAMPER, AIR LINE BROKEN, REP~IR.

2 22 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:

22 WASTE GAS COMPRESSOR TRIPS, TROUBLESHOOT, REWORK AS NECESSARY.

MAJOR PLANT MODIFICATIONS REPORT MONTH FEBRUARY 1988

• DCR NO.

2EC-2172A 2SC-0916 PRINCIPAL SYSTEM Hot Shutdown Panel Indications RHR Sump Design Change Request DOCKET NO.:

50-311 UNIT NAME:

Salem 2 DATE:

March 10,1988 COMPLETED BY:

J. Ronafalvy TELEPHONE: 609/339-4455 SUBJECT This design change modified the existing Gamma-Metrics as follows:

1.

Added a power transfer switch at the Hot Shutdown Panel to provide 2C 115 VAC vital instrument power to "C" channel to meet Reg.

Guide 1.97 criteria and provide 2 ASOS instrument power to 11 C" channel to meet Appendix "R" criteria.

2.

Shutdown monitors which alarm for a boron dilution accident were relocated from the NI rack to the 2RP1 panel for better Control Room Operator accessibility.

3.

Added a signal buffer to provide a spare channel for the Westinghouse Audio Count Rate Network.

This design change replaced the RHR sump pumps with improved portable submersible trash pumps.

e MAJOR PLANT MODIFICATIONS REPORT MONTH -

FEBRUARY 1988

• DCR SAFETY EVALUATION 10 CFR 50.59 e

DOCKET NO: 50-272 UNIT NAME:

~S~a~l~e-m~~2~~~~

DATE:

March 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455 2EC-2172A This design change affected a functional change to a safety related system and involved an electrical safety to non-safety related interface.

This modification did not introduce or increase the possibility of adverse physical impact to any safety related equipment because all new equipment and mountings are seismically installed.

This design change did not introduce and new failure modes as a result of electrical interaction of interfaces.

Electrical isolation and separation has been maintained.

This design change does not alter any plant process or discharge and did not affect the existing environmental impact.

No unreviewed safety or environmental questions are involved.

2SC-0916 The probability of occurrence of an accident previously evaluated in the SAR is not increased.

Thee is no increased possibility of an accident of a different type then previously evaluated in the SAR and the margin of safety is not reduced for any Technical Specification.

There is no potential for adverse impact to any safety related equipment.

This design change does not affect any plant process or discharge and did not affect the existing environmental impact.

No unreviewed safety or environmental questions are involved.

DCR -

Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT NO. 2 FEBRUARY 1988 The Unit began the period with power held at 50% due to Steam Generator Feed Pump speed control problems.

The speed control problems were resolved and on February 1, 1988, power was increased to 100%.

The Unit continued to operate at essentially 100% power until early February 14, 1988, when power was reduced to 20% due to ice and grass fouling of the circulating water travelling screens.

Power was increased to 49% later that morning and held at that level 1due to rod control misalignment problems.

The repairs were completed and the power escalation was resumed that evening.

On February 15, 1988, the power escalation was held at 78% for circulating water box cleaning.

The water box cleaning was completed and power was increased to 100%

that same day.

The Unit continued to operate at essentially 100%

power for the remainder of the period.

REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY:

J. Ronafalvy DATE:

March 10, 1988 TELEPHONE: 609/935-6000 EXTENSION __,4~4~5~5=-~~~~~~-

Month FEBRUARY 1988

1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

September 3, 1988

3.

Scheduled date for restart following refueling: November 2,1988

4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO 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, 1988

5.

Scheduled date(s) for submitting proposed licensing action:

August 1988 if required

6.

Important licensing considerations associated with refueling:

7.

8.

9.

NONE Number of Fuel Assemblies:

A)

Inc ore B)

In Spent Fuel Storage Present licensed spent fuel storage capacity:

Future spent fuel storage capacity:

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

8-1-7.R4 193 224 1170 1170 March 2003

}'

~* 0 PS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sir~

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 March 11, 1988 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of February 1988 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours,

/?::1::!:2 General Manager -

Salem Operations RH:sl cc:

Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 I

The Energo/ People 95-2189 (11 M) 12-84