ML18094B342

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Monthly Operating Rept for Feb 1990 for Salem,Unit 2.W/
ML18094B342
Person / Time
Site: Salem 
Issue date: 02/28/1990
From: Miller L, Orticelle A
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003200173
Download: ML18094B342 (9)
v • d • e


Text

.,.

OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 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 February 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

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~DR ADOCK 05000311 R

PDC 95-2189 (11 M) 12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No.

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

Unit Name Salem # 2 Date

~0~3_-~0~9_-~9~0~~~~-

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

(MWe-NET) 1 967 17 1075 2

942 18 1112 3

1014 19 1094 4

1068 20 1109 5

1112 21 1083 6

1100 22 1115 7

1109 23 1085 8

1117 24 1110 9

1109 25 1100 10 1109 26 1078 11 1093 27 1111 12 1055 28 1091 13 1097 29 14 1092 30 15 1100 31 16 1100 Pg. 8.1-7 Rl I L__ __

OPERATING DATA REPORT Docket No:

50-311 Date:

03-09-90 Completed by:

Art Orticelle Telephone:

609-339-2122 Operating Status

1.

Unit Name Salem No. 2 Notes

2.

Reporting Period February 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 ( i terns 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 672 1416 73465
12. No. of Hrs. Reactor was Critical 672 1270.8 47276.6
13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 672 1253.8 45799
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated

{MWH) 2262746.4 4137614.4 93189353.8

17. Gross Elec. Energy Generated (MWH) 775490 1412690 47459742
18. Net Elec. Energy Generated (MWH) 746365 1353173 45153079
19. Unit Service Factor 100 88.5 62.3
20. Unit Availability Factor 100 88.5 62.3
21. Unit Capacity Factor (using MDC Net) 100.4 86.4 55.6
22. Unit Capacity Factor

{using DER Net) 99.6 85.7 55.1

23. Unit Forced Outage Rate 0

11.5 25.7

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

REFUELING OUTAGE, START 3-31-90, SCHEDULED TO LAST 55 DAYS.

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

N/A 8-1-7.R2

NO.

DATE 0023 01/31/90 0026 02/02/90 1

F: Forced S: Scheduled I

DURATION

'IYPE 1 (HOORS)

REASON z F

7.2 H

F 3.9 A

UNIT SHUTOOWN AND POWER REDUCTIONS REPORT IDNTH FEBRUARY 1990 METIIOD OF SHUTTING LICENSE DOWN EVENT SYSTEM REACTOR REPORT ff OODE" 5

HF 5

HF a>>iPONENT OODE 5 xxxxxx Filter OOCKEl' NO.: 50-311 UNIT NAME:

Salem #2 DATE: 03-09-90 CDMPIEI'ED BY: Art Orticelle TELEPHONE:

339-2122 CAUSE AND OORRECTIVE ACTION

'IO PREVENT RIDJRRENCE Circ. Water Diff. Temp.

12 B Trav. Screen 2

3 4

5 Reason:

A-F.quipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E--Operator Training & License Examination F-Adrrd.nistrative G-Operational Error (Explain)

H-other (Explain)

Method:

1-Manual 2-Manual Scram 3-Autanatic Scram 4-COntinuation of Previous outage 5-1.oad Reduction 9-other Exhibit G - Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report CLER) File (NUREXJ-0161)

SAFETY RELATED MAINTENANCE MONTH: -

FEBRUARY 1990 DOCKET NO:

UNIT NAME:

50-311 SALEM 2 DATE:

COMPLETED BY:

TELEPHONE:

MARCH 10, 1990 P. WHITE (609) 339-4455 WO NO UNIT EQUIPMENT IDENTIFICATION

~--------------------------------------------------------------------

880825121 2

CHEM. ADD. TANK FAILURE DESCRIPTION:

PERFORM ISI 10 YR. HYDRO TEST 890914177 2

AUX. FD. PUMPS FAILURE DESCRIPTION:

PERFORM ISI 10 YR. HYDRO TEST 890914184 2

900126086 2

900215145 2

AUX. FD. STORAGE TANK FAILURE DESCRIPTION:

PERFORM ISI 10 YR. HYDRO TEST

  1. 2 BORIC ACID BATCH TANK FAILURE DESCRIPTION:

PERFORM ISI 10 YR. HYDRO TEST 2XD5517 AUX. BLDG. VENT BEZEL FAILURE DESCRIPTION:

EMERGENCY AREA EXH. BEZEL -

INVESTIGATE

~---------------------

900305035 2

  1. 21 CHARGING PUMP FAILURE DESCRIPTION:

FLUSH CUNO FILTER

MAJOR PLANT MODIFICATIONS MONTH: -

FEBRUARY 1990

Design Change Request DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

50-311 SALEM 2 MARCH 10, 1990 P. WHITE (609) 339-4455 DESCRIPTION This design change eliminated the RTD bypass piping along with manifolds and associated valves to install an alternate method of obtaining reactor coolant loop measurements.

MAJOR PLANT MODIFICATIONS MONTH: -

FEBRUARY 1990 DOCKET NO:

UNIT NAME:

50-311 SALEM 2

COMPLETED BY:

TELEPHONE:

SAFETY EVALUATION 10 CFR 50.59 MARCH 10, 1990 P. WHITE (609) 339-4455 This design change eliminated the RTD bypass piping along with manifolds and associated valves to install an alternate method of obtaining reactor coolant loop measurements.

Elimination of the bypass piping results in a reduction in maintenance, radiation exposure and outage time.

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

r=

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

UNIT 2 FEBRUARY 1990 SALEM UNIT NO. 2 The Unit began the period operating at reduced power for condenser waterbox cleaning.

The Unit was restored to full power on February 4, 1990, and continued to operate at essentially full power for the remainder of the period.

SAFETY RELATED MAINTENANCE MONTH: -

FEBRUARY 1990 MONTH DECEMBER 1989 DOCKET NO:

UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

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 MARCH 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 308

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

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