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 K, 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 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 June 12, 1989 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 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 Sincerely

yours, L. K. Miller General Manager -Salem Operations 95-2189 (5M) 12-88 AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name 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 1014 31 0 16 1075 Pg. 8.1-7 Rl OPERATING DATA REPORT Completed by Pell White Operating Status Docket No. Date Telephone Extension 50-311

___ _ 935-6000 4451 1. 2. 3. 4. 5. 6. 7. 8. Unit Name Salem No. 2 Notes Reporting Period May 1989 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 since Last N/A If Changes Occur in Capacity Ratings (items 3 through 7) Report, Give Reason

9. Power Level to Which Restricted, if any (Net MWe) N/A

10. Reasons for Restrictions, if any N/A

11. 12. 13. Hours in Reporting Period No. of Hrs. Reactor was Critical 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 1MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 66 2. 1 0 648.32 0 2170394.4 710440 700535 87.1 87.1 85.1 Year to Date 3623 30 77. 6 0 2922.05 0 9521035.2 3117055 3048728 80.7 80.7 76.1 Cumulative 66912 41433.4 0 40044.6:.2 0 74186132.2 41001355 39024033 59.8 59.8 52.7 84.4 75.5 52.3 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 Completed by No. Date 0120 05-09-89 0125 05-12-89 0148 05-28-89 1 F: Forced S: Scheduled l UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH MAY 1989 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1 2 Reactor Rep art F 0 A 5 F 0 A 5 F 85.68 A 1 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Ref ue ling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain Unit Name Salem No.2 Date 6-08-89 Telephone 609-935-6000 Extension 4451 System Component Code 4 Code 5 HF HT EX CH HF HTEXCH CH VAL VEX 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 CONDENSER TUBE WATER BOX CLEANING CONDENSER TUBE WATER BOX CLEANING BF19 PROBLEM e MODIFICATION 4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Salem as Source WO NO 890501256 890503086 880712157 890528085 890529061 890529062 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2 2FI513 FAILURE DESCRIPTION:

21 S/G STM FLW/LOW INDICATION/REWORK.

2 22SW53 FAILURE DESCRIPTION:

VLV BODY CORRODED, REPAIR. 2 24 INNER PEN AREA EXHAUST FAN FAILURE DESCRIPTION:

REPLACE PER 2SM-00672.

2 21-24BF19 FWTR ISO FAILURE DESCRIPTION:

SOV MOD/INCORP.

DCP 2SC2025. 2 21 BF40 VALVE FAILURE DESCRIPTION:

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

REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

WO NO 890529064 890529065 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2 23 BF40 VALVE FAILURE DESCRIPTION:

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

REPLACE TUBING/VALVE CHANGE TUBING FROM 3/8" TO 1/2".

• MAJOR PLANT MODIF .. TIONS REPORT MONTH MAY 1989 *DCR NO. 2EC-02193 2SC-01186 2SM-0607 PRINCIPAL SYSTEM Reactor Protection 4KV Group Bus Transformers

• Design Change Request DOCKET.: 50-311 UNIT NAME: Salem 2 DATE: June 10, 1989 COMPLETED BY: P. White TELEPHONE:

609/339-4455 DESCRIPTION This design change deleted the direct Reactor Trip following a turbine trip below 50% 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 design change provided for the installation of a microprocessor based on line transformer gas monitoring system.

MAJOR PLANT MODIFICATIONS REPORT.MONTH MAY 1989 DOCKET UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

• DCR SAFETY EVALUATJON 10 CFR 50.59 50-272 Salem 2 June 10, 19 89 P. White (609)339-4455 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 UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT NO. 2 MAY 1989 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: 2. 3. 4. YES X NO Scheduled date for next refueling:

March 3 0 , 19 9 0 Scheduled date for restart following refueling:

May 15, 1990 A) B) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMIN_E_D

__ T_O-DATE X 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. 8. 9. 8-1-7.R4 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:

193 224 1170 1170 March 2003