ML18093A791

Monthly Operating Rept for Mar 1988

ML18093A791
Person / Time
Site:	Salem
Issue date:	03/31/1988
From:	Ronafalvy J, White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8804190044
Download: ML18093A791 (10)

Text

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I AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Docket No.

Unit Name Date Telephone Extension Month MARCH 1988 Day Average Daily Power Level Day Average Daily (MWe-NET)

(M.We-NET) 1 1100 17 1071 2

1098 18 1084 3

1104 19 1097 4

1125 20 1097 5

997 21 1089 6

1093 22 1089 7

1109 23 1084 8

1089 24 1104 9

1101 25 1123 10 1090 26 1027 11 1089 27 1092 12 1083 28 1097 13 1105 29 1103 14 1084 30 1091 15 1098 31 1096 16 1124 Pg. 8.1-7 Rl

,----:--.--~------- -.

• . 88041 90044 8E:o::::31

. ** PDR :* ***

• ADOCI< 05000:311

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. DCD 50-311 Salem # 2 April 10, 1988 609-935-6000 4451 Power Level

I I

~

e OPERATING DATA REPORT Completed by Pell White Operating Status Docket No. 50-311 Date Telephone Extension

~~~~~~~~

April 10,1988 935-6000 4451 1

• 2.

3

• 4.

5

• 6.

7

• 8

• Unit Name Salem No. 2 Notes Reporting Period March 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) 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 2184 56689

12. No. of Hrs. Reactor was Critical 744 2184 35986.9

13. Reactor Reserve Shutdown Hrs.

0 0

0

14. Hours Generator On-Line 744 2180.3 33462.1

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2532218 7321162 52971683

17. Gross Elec. Energy Generated (MWH) 845860 2439920 34069390

18. Net Elec. Energy Generated (MWH) 811935 2342864 32362242

19. Unit Service Factor 100 99.8 59.0

20. Unit Availability Factor 100 99.8 59.0

21. Unit Capacity Factor (using MDC Net) 98.7 97.0 51.6

22. Unit Capacity Factor (using DER Net) 97.9 96.2 51.2

23. Unit Forced Outage Rate 0

0.17 29.6

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-l-7.R2

Completed by No.

Date NONE 1

F: Forced S: Scheduled PNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1988 Docket No. 50-311 Unit Name Date Telephone Extension Salem No.2-Pell White Type 1

Duration Hours Reason 2

Method of Shutting Down Reactor License Event Report 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Adm inist rat ive G-Operational Error-explain H-Other-explain System Code 4 3 Method 1-Manual Component Code 5 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther April 10, 1988 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence 4

Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit Salem as Sou re e

WO NO UNIT 870515050 2

870827085 2

870909072 2

870912029 2

880211069 2

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 EQUIPMENT IDENTIFICATION 22 CHILLER EXPANSION JOINT FAILURE DESCRIPTION:

REPLACE SUCTION EXPANSION JOINT ON #22 CHILLER 2SV263 SOL VLV FAILURE DESCRIPTION:

LEAKING AIR WITH VALVE IN CLOSED POSITION 21CV154 FAILURE DESCRIPTION:

REPLACE THE VALVE.

2SJ133 FAILURE DESCRIPTION:

REPLACE VALVE.

21CV16 2 FAILURE DESCRIPTION:

LEAKING DIAPHRAM/REPLACE.

e

WO NO 880216092 880307088 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2

/f2 2 BAT PUMP FAILURE DESCRIPTION:

MECHANICAL SEAL LEAKING.

REPAIR/REPLACE.

2 23 CHARGING PUMP FAILURE DESCRIPTION:

THE HORZINAL COVER NUMBER 2 CYLINDER ON 23 CHARGING PUMP LEAKS/REWORK.

2 22SW133 FAILURE DESCRIPTION:

NO/FLOW/DISASSEMABLE & INSPECT

MAJOR PLANT MODIFICATIONS REPORT MONTH MARCH 1988

• DCR NO.

2EC-2172A 2SM-00111 2SM-00131 PRINCIPAL SYSTEM Service Water Service Water Radiation Monitoring Design Change Request DOCKET NO.:

50-311 UNIT NAME:

Salem 2 DATE:

April 10,1988 COMPLETED BY:

J. Ronafalvy TELEPHONE: 609/339-4455 DESCRIPTION This Modification changed out all dissimilar metal welds within the Containment.

The change was made due to failures experienced in dissimilar metal weld joints.

The concern was that failure in these joints could cause forced outages by rendering Containment Fan Coil Units inoperable.

This design change replaced piping immediately downstream of valve 22SW122 with a removable spoolpiece which is internally coated with Belzona erosion/corrosion barrier.

The piping in this area is subject to severe cavitation, erosion, and corrosion damage due to turbulence created by the valve.

This design change raised Radiation Monitor 2R32A alarm and warning setpoints to accommodate an increase in background radiation levels above the Spent Fuel Pool.

e MAJOR PLANT MODIFICATIONS REPORT MONTH -

MARCH 1988

• DCR SAFETY EVALUATION 10 CFR 50.59 DOCKET NO: 50-272 UNIT NA.ME : -=s'"-a"""'l_e_m__,2,,__ __ _

DATE:

April 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455 2EC-2241 This design change has been accomplished within the requirements of Procedure GM8-EMP-028 Category IV.

The changes were stress analyzed to ensure Seismic I integrity of the Service Water System has been maintained.

The modifications affected by this DCR have no impact to analysis performed in the FSAR or to any bases to the Technical Specifications.

No potential was created for a new/accident malfunction or aggravating a previously analyzed one.

This modification did not involve a change to any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions were involved.

2SM-00111 This modification did not alter the original design criteria as outlined in PSE&G detail specification S-C-MPOO-MGS-0001.

This modicication did not involve a change to any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

2SM-00131 This design change does not alter the original design criteria of the 2R32A setpoints.

This modification did not involve a change to any plant process or discharge or affect 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 NO. 2 MARCH 1988 The Unit began the period operating at 100% power and continued to operate at full power throughout the entire period.

Steam Generator primary to secondary tube leaks were identified in Nos. 22 and 24 Steam Generators and were calculated at 4.6 and 3.5 gpd respectively.

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

J. Ronafalvy DATE:

April 10, 1988 TELEPHONE: 609/935-6000 EXTENSION ~4-4~5~5~~~~~~~-

Month MARCH 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-l-7.R4 193 224 1170 1170 March 2003 l

1"".. *'.

OPS~G Pub I ic Service Electric and Gas Company P.0. 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 April 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 March 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, J.~~f.*

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 8-1-7.R4 The Energy People

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