ML18094B395

Monthly Operating Rept for Mar 1990 for Salem 2

ML18094B395
Person / Time
Site:	Salem
Issue date:	03/31/1990
From:	Miller L, Orticelle A, White P Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9004170004
Download: ML18094B395 (9)

Text

,.:.

Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 March 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 95-2189 (11 M) 12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No.

=5=0_-=3=1=1~~~~~-

Unit Name Salem # 2 Date

=0~4_-~0~9_-~9~0~~~~-

Completed by Art Orticelle Telephone 609-339-2122 Month MARCH 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1100 17 1091 2

1097 18 1088 3

1054 19 1096 4

1094 20 1053 5

1112 21 933 6

1087 22 1096 7

1110 23 1086 8

1111 24 1073 9

1111 25 1039 10 1084 26 1088 11 1083 27 1094 12 1104 28 1088 13 1110 29 1088 14 1085 30 874 15 1098 31 0

16 1115 Pg. 8.1-7 Rl

OPERATING DATA REPORT Docket No:

50-311 Date:

04-09-90 Completed by:

Art Orticelle Telephone:

609-339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period March 1 1990

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 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 2160 74209

12. No. of Hrs. Reactor was Critical 723.1 1993.8 47999.7

13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 720.3 1974.1 46519.3

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2418187.2 6555801.6 95607541

17. Gross Elec. Energy Generated (MWH) 825190 2237880 48284932

18. Net Elec. Energy Generated (MWH) 792656 2145829 45945735

19. Unit Service Factor 96.8 91.4 62.7

20. Unit Availability Factor 96.8 91.4 62.7

21. Unit Capacity Factor (using MDC Net) 96.3 89.8 56.0

22. Unit Capacity Factor (using DER Net) 95.6 89.1 55.5

23. Unit Forced Outage Rate 0

7.6 25.4

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

REFUELING OUTAGE, START 3-31-90 1 DURATION 55 DAYS.

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

5-24-90 8-1-7.R2

NO.

DATE 0037 03/03/90 0043 03/20/90 0047 03/25/90 0050 03/31/90 1

F: Forced S: Scheduled DURATION TYPE i (HOORS)

REASON 2 F

1.0 A

F 7.1 H

F 3.4 H

s 23.7 c

UNIT SHUTOOWN AND POWER REDUCTIONS REPORT IDNTH MARCH, 1990 MEI'HOD OF SHU'ITING I.JCENSE OOWN EVENT SYITTEM REACTOR REPORI' #

CODE 4 5

AD 5

EB 5

EB 1

RC mMPONENT CODE 5 xxxxxx TRAN SF TRAN SF FUELXX OOCKEI' NO.: 50-311.

UNIT NAME:

Salem #2 DATE: 04-09-90 CDMPLEI'ED BY: Art Orticelle-TELEPHONE:

339-2122 CAUSE AND CORRECTIVE ACTION

'ID PREVENT REaJRRENCE

1. 1 BEARING IITGH TEMP.

SOLAR FLARES SOLAR FLARES REFUEL1NG

~

2 3

4 5

Reason:

A-F.quiµnent Failure (Explain)

B-Maintenance or Test C-Refueling D--Regulatory Restriction E-()perator Training & License Examination F-Administrative G--Operational Error (Explain)

H--Other (Explain)

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-COntinuation of Previous outage 5-l.oad Reduction 9--0ther Exhibit G - Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report (LER.) File (NUREG--0161)

SAFETY RELATED MAINTENANCE MONTH; -

MARCH 1990 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 WO NO UNIT 910819004 2

920205002 2

890807107 2

900305132 2

900309084 2

900309120 2

DATE:

COMPLETED BY:

TELEPHONE:

APRIL 10, 1990 P. WHITE (609) 339-4455 EQUIPMENT IDENTIFICATION 12WG10 FAILURE DESCRIPTION:

REPLACE DIAPHRAGM 12SW66 FAILURE DESCRIPTION:

REPLACE DIAPHRAGM AUX. FD. STORAGE TANK FAILURE DESCRIPTION:

AFWST LEVEL INDICATION FAILED -

TROUBLESHOOT AND REPAIR 22MS10/22 FAILURE DESCRIPTION:

MAIN STEAM ATMOSPHERIC RELIEF LEAKING PAST SEAT -

INVESTIGATE 2NR45 POWER RANGE RECORDER FAILURE DESCRIPTION:

POWER RANGE RECORDER READS LOW -

INVESTIGATE 2SW213 FAILURE DESCRIPTION:

CHARGING PUMP ROOM COOLER VALVE DID NOT OPEN -

TROUBLESHOOT

~AJOR PLANT MODIFICATIONS MONTH: -

MARCH 1990

• DCR 2SM-00091 2SM-00093 PRINCIPAL SYSTEM Post Accident Sampling Sys.

Steam Generator DCR -

Design Change Request DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 APRIL 10, 1990 P. WHITE (609) 339-4455 DESCRIPTION This design change replaced the instrument air regulating valves which supply the solenoid valves which actuate the Post Accident Sampling System (PASS) containment isolation valves.

This design change rerouted the Steam Gen~rator Feed Pump (SGFP) separator suction piping to a location lower in the reservoir.

]

I_

I I

I

' MAJOR PLANT MODIFICATIONS DOCKET NO:

50-311 SALEM 2 MONTH: -

MARCH 1990 UNIT NAME:

• DCR 2SM-00091 2SM-00093 DATE:

COMPLETED BY:

TELEPHONE:

SAFETY EVALUATION 10 CFR 50.59 APRIL 10, 1990 P. WHITE

{609) 339-4455 This design change replaced the instrument air regulating valves which supply the solenoid valves which actuate the Post Accident Sampling System (PASS) containment isolation valves.

The replacement valves are designed to better withstand the environmental conditions postulated for an accident.

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 rerouted the Steam Generator Feed Pump (SGFP) separator suction piping to a location lower in the reservoir to help reduce sludge buildup.

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.

DCR -

Design Change Request

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 MARCH 1990 The Unit began the period operating at 100% power and continued to operate at essentially full power until March 30, 1990, when it was shutdown for a refueling outage.

During the period, there were several minor load reductions in response to solar magnetic disturbance alerts.

REFUELING INFORMATION DOCKET NO:

MONTH: -

MARCH 1990 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

MONTH DECEMBER 1989

1.

Refueling information has changed from last month:

YES x

NO

2.

Scheduled date for next refueling:

March 31, 1990

3.

Scheduled date for restart following refueling:

50-311 SALEM 2 APRIL 10, 1990 P. WHITE (609) 339-4455 May 24, 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?:

April 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 316

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:

March 2003 8-1-7.R4