ML18093A908

Monthly Operating Rept for May 1988 for Salem Unit 2.W/

ML18093A908
Person / Time
Site:	Salem
Issue date:	05/31/1988
From:	White P, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8806230104
Download: ML18093A908 (11)

Text

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

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

(MWe-NET) 1 1106 17 1076 2

1102 18 1083 3

1102 19 1094 4

1106 20 1090 5

1129 21 1079 6

1073 22 1098 7

1108 23 1093 8

1117 24 1088 9

10 82 25 1095 10 1105 26 1086 11 1081 27 1098 12 1081 28 1085 13 1093 29 10 90 14 0

30 1097 15 0

31 1130 16 424 Pg. 8.1-7 Rl 50-311 Salem # 2 June 10, 1988 609-935-6000 4451 Power Level

e OPERATING DATA REPORT Completed by Pell White Operating Status

1.

Unit Name Salem No. 2

2.

Reporting Period May 1988

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)ll49

7.

Maximum Dependable Capacity (Net MWe) 1106

8.

If Changes Occur in Capacity Ratings (items Report, Give Reason Docket No.

Date Telephone Extension Notes 3 through 50-311 June 10. 1988 935-6000 4451

7) 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 744 69 2. 2 0

686.8 0

2323214 777090 744708 92.3 92.3 90.5 Year to Date 3647 3565.5 0

35 31.1 0

11893632 3967560 3807148 96.8 96.8 94.4 Cumulative 58152 35928.4 0

34812.9 0

57544153 35597030 33826526 59.9 59.9 52.6 (using DER Net) 89.8 93.6 52.2

23. Unit Forced Outage Rate 7.7 3.2 28.9

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

Refueling Outage scheduled for 9-1-88 and lasting for aEproximately 52 da s.

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

N/A 8-l-7.R2

Completed by No.

Date 00 98 5-13-88 1

F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MAY 1988 Docket No.

Unit Name Date Telephone Extension 50-311 Salem No.2 Pell White Method of Duration Shutting Type Hours Reason Down 1

2 Reactor F

57.2 A

3 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing F-Administrative G-Operational Error-explain H-Other-explain License Event Re12ort Exam System Component Code 4 Code 5 RB CONROD 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 CONTROL ROD DRIVE PROBLEMS 4

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

\\

5 Exhibit Salem as Source

WO NO 870226084 870422010 871208174 871209164 871229155 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2

22 RHR PUMP FAILURE DESCRIPTION:

LEAKING FROM THE PUMP BASE.

REPLACE CASING.

2 2CV59 FAILURE DESCRIPTION:

STEM SEPARATED FROM DIAPHRAGM.

REPLACE BONNET.

2 2SWE51 FAILURE DESCRIPTION:

REPLACE EXPANSION JOINT.

2 2SWE48 FAILURE DESCRIPTION:

REPLACE EXPANSION JOINT.

2 23 AUX PUMP SPEED DEMAND FAILURE DESCRIPTION:

CLEAN/INSPECT/LUE

SAT.. EH HNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880203083 2

2SWE52 FAILURE DESCRIPTION:

NEEDS REPLACING/REPLACE.

880321121 2

25 SW PUMP FAILURE DESCRIPTION:

SEAL RING LEAKING/REPLACE RING.

88 0418146 2

2SW319 FAILURE DESCRIPTION:

LEAK IN WELD ON FLANGE/REPAIR.

880422150 2

MS3l'S STM DUMP FAILURE DESCRIPTION:

DUMP TO CONDS / WONT WORK IN AUTO / REWORK.

SALEH UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880428063 2

2CH55 FAILURE DESCRIPTION:

RADIOGRAPHY REVEALED VALVE OPEN.

INSPECT FOR ABNORMAL CONDITIONS.

REPAIR AS NECESSARY.

880505122 2

22AF53 FAILURE DESCRIPTION:

BONNET LEAK, REPLACE GASKET.

FAJOR PLANT MODIFICATIONS REPORT MONTH MAY 1988

• DCR NO.

PRINCIPAL SYSTEM 2EC-1692 Service Water 2SM-00122 Service Water 2SM-00347 RVLIS Design Change Request DOCKET NO.:

50-311 UNIT NAME:

Salem 2 DATE:

June 10,1988 COMPLETED BY:

TELEPHONE:

J. Ronafalvy 609/339-4455 DESCRIPTION This modification. replaced existing carbon steel piping with stainless steel piping in the discharge off the No. 22 Nuclear Header upstream and downstream of valve 22SW49.

This design change replaced Valve 21SW99.

As there were no 4" mission duo check valves available, this valve was replaced with a 4" Clow duo check valve.

This design change replaced cormnunication board A4 with a later revision board.

L e

e t:AJOR PLANT MODIFICATIONS REPORT MONTH -

MAY 1988 DOCKET NO: 50-272 UNIT NAME:

=s-a~l-em--~2------~

• DCR SAFETY EVALUATION 10 CFR 50.59 DATE:

June 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE: (609)339-4455 2EC-1692 This design change replaced highly eroded carbon steel piping with stainless steel piping.

The function of the system was not altered but its integrity was ensured.

This modifciation did,not alter any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

2SM-00122 This modification did not alter the original design of the system.

The duo check valve is no longer manufactured by TRW but is now made by Clow.

A review of the design specifications show that the new valve is identical in every way to the old one.

This modification did not alter any plant process or discharge or affect the environmental impact of the plant.

No unreviewed safety or environmental questions are involved.

ZSM-00347 The installation of the new components did not alter the operating characteristics or specif-ications of the system.

This modification did not alter 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 SUMJ;.:1ARY - UNIT NO. 2 MAY 1988 The Unit began the period operating at 100% power and continued to operate at full power until May 13, 1988, when a Reactor Trip occurred due to a Negative Flux Rate condition.

The results of testing performed to ascertain the cause of the trip have been inconclusive, but suggest a dropped rod.

The Unit was returned to full power on May 16, 1988, and continued to operate at that level for the remainder of the period.

The primary to secondary leak rate calculations for Nos.

22 and 24 Steam Generators continue to indicate less than five gallons per day per Steam Generator.

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

J. Ronafalvy DATE:

June 10, 1988 TELEPHONE: 609/935-6000 EXTENSION ---.--44~5~5=--~~~~~

Month MAY 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)

B)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE X

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 2008

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 June 14, 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 May 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 Surmnary Refueling Information Sincerely yours, J.~~~-

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 The Energy People 95-2189 (11 M) 1