ML18094A519

Monthly Operating Rept for May 1989 for Salem Unit 2. W/890612 Ltr

ML18094A519
Person / Time
Site:	Salem
Issue date:	05/31/1989
From:	Miller L, White P Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8906210019
Download: ML18094A519 (10)

Text

• o es1<<1*

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station June 12, 1989 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 Specification, the original copy of the monthly operating reports for the month of May 1989 are being sent to you.

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

It~

L. K. Miller 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

_r-e-906210019 890531 PDR ADOCK 05000311 R PNU The Energy People 95-2189 (5M) 12-88

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name *~s~a~l-e_m_,,.#-=2~~~~

Date 6-08-89

-=-=-=--=-=-=--=-=-=-=~---

Completed by Art Orticelle Telephone 609-935-6000 Extension 4451

~-=---------------

Month MAY 1989 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1104 17 1084 2 1086 18 1068 3 10 88 19 1031 4 1097 20 1057 5 1086 21 1078 6 1094 22 1076 7 97 6 23 1086 8 1074 24 1106 9 1056 25 1074 10 1004 26 1067 11 1035 27 77 4 12 996 28 0 13 10 87 29 0 14 1020 30 0 1~ 1014 31 0 16 1075 Pg. 8.1-7 Rl

OPERATING DATA REPORT Docket No. 50-311 Date 6-0~8--~8~9 _ _ __

Telephone 935-6000 Completed by Pell White Extension 4451 Operating Status

1. Unit Name Salem No. 2 Notes

2. Reporting Period May 1989

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 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 3623 66912

12. No. of Hrs. Reactor was Critical 66 2. 1 30 77. 6 41433.4

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 648.32 2922.05 40044.6:.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2170394.4 9521035.2 74186132.2

17. Gross Elec. Energy Generated (MWH) 710440 3117055 41001355

18. Net Elec. Energy Generated 1MWH) 700535 3048728 39024033

19. Unit Service Factor 87.1 80.7 59.8

20. Unit Availability Factor 87.1 80.7 59.8

21. Unit Capacity Factor (using MDC Net) 85.1 76.1 52.7

22. Unit Capacity Factor (using DER Net) 84.4 75.5 52.3

23. Unit Forced Outage Rate 12.9 19.3 27.9

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

NONE

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

Unit returned back to service on June 1, 1989 at 0341.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH MAY 1989 Unit Name Salem No.2 Date 6-08-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Rep art Code 4 Code 5 Prevent Recurrence CONDENSER TUBE 0120 05-09-89 F 0 A 5 HF HT EX CH WATER BOX CLEANING CONDENSER TUBE 0125 05-12-89 F 0 A 5 HF HTEXCH WATER BOX CLEANING 0148 05-28-89 F 85.68 A 1 CH VAL VEX BF19 PROBLEM MODIFICATION e 1 2 Reason 3 -Method 4 Exhibit G 5 Exhibi-F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram. for Prepara- Source C-Ref ue ling 3-Automatic Scram. tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-0ther (LER) File H-Other-explain (NUREG 0161) l

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 890501256 2 2FI513 FAILURE DESCRIPTION: 21 S/G STM FLW/LOW INDICATION/REWORK.

890503086 2 22SW53 FAILURE DESCRIPTION: VLV BODY CORRODED, REPAIR.

880712157 2 24 INNER PEN AREA EXHAUST FAN FAILURE DESCRIPTION: REPLACE PER 2SM-00672.

890528085 2 21-24BF19 FWTR ISO FAILURE DESCRIPTION: SOV MOD/INCORP. DCP 2SC2025.

890529061 2 21 BF40 VALVE FAILURE DESCRIPTION: REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

890529062 2 22 BF40 VALVE FAILURE DESCRIPTION: REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 890529064 2 23 BF40 VALVE FAILURE DESCRIPTION: REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

890529065 2 24 BF40 VALVE FAILURE DESCRIPTION: REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

• MAJOR PLANT MODIF. .TIONS DOCKET.: 50-311 REPORT MONTH MAY 1989 UNIT NAME: Salem 2 DATE: June 10, 1989 COMPLETED BY: P. White TELEPHONE: 609/339-4455

• DCR NO. PRINCIPAL SYSTEM DESCRIPTION 2EC-02193 Reactor This design change deleted the Protection direct Reactor Trip following a turbine trip below 50%

2SC-01186 4KV Group Bus This design change upgraded the undervoltage protection of the 4KV Group Busses, 2E, 2F, 2G, 2H, to prevent the uncontrolled restart of connected equipment upon power restoration to a deenergized 4KV Group Bus.

2SM-0607 Transformers This design change provided for the installation of a microprocessor based on line transformer gas monitoring system.

• Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO~ 50-272 REPORT.MONTH MAY 1989 UNIT NAME: Salem 2 DATE: June 10, 19 89 COMPLETED BY: P. White TELEPHONE: (609)339-4455

• DCR SAFETY EVALUATJON 10 CFR 50.59 2EC-02193 This design change deleted the direct Reactor Trip tallowing a turbine trip below 50% power. 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.

2SC-01186 This design change upgraded the undervoltage protection of the 4KV Group Busses, 2E, 2F, 2G, 2H, to prevent the uncontrolled restart of connected equipment upon power restoration to a deenergized 4KV Group Bus. This modification enhances reliability by minimizing the possibility of damage to the reactor Coolant Pump Motors or breakers. 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.

2SM-0607 This design change provided for the installation of a microprocessor based on line transformer gas monitoring system. Installation of the equipment provides continuous monitoring of the level of combustible gas in transformer oil, allowing early detection of developing problems, thus increasing the safety and reliability of the equipment. 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 GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 2 MAY 1989 SALEM UNIT NO. 2 The Unit began the period operating at full power, and, with the exception of some minor load reductions for condenser waterbox cleaning and maintenance of delta T limits, continued to operate at essentially full power until May 27, 1988. On May 27, 1989, power was reduced due to the failure of No. 22W Intercept Valve during a turbine valve test. The Unit was removed trom service on May 28, 1989, to comply with Technical specification requirements, due to problems identified with the testing of the Unit 2 main feedwater regulating valves. The problems were corrected and the valves tested satistactorily on May 29, 1989. The Unit ended the period with startup in progress.

y REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: P. White DATE: June 10, 1989 TELEPHONE: 609/935-6000 EXTENSION 4455 Month MAY 1989

1. Refueling information has changed from last month:

YES X NO

2. Scheduled date for next refueling: March 3 0 , 19 9 0

3. Scheduled date for restart following refueling: May 15, 1990

4. A) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMIN_E_D__

T_O-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? February 1990

5. Scheduled date(s) for submitting proposed licensing action:

January 1990

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Inc ore 193 B) In Spent Fuel Storage 224

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170

9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: March 2003 8-1-7.R4