ML18101A480

Monthly Operating Rept for Apr 1989 for Salem,Unit 2.W/ 890511 Ltr

ML18101A480
Person / Time
Site:	Salem
Issue date:	04/30/1989
From:	MILLER L K, ORTICELLE A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905230347
Download: ML18101A480 (10)

Text

.... 0 PSl<<i* 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 :May 11 r 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 April 1989 are being sent to you. RH:sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Safety Valve Challenges 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 19406 Enclosures 8-l-7.R4 The Energy People 95-2189 (SM) 12-88 Completed by Month APRIL AVERAGE DAILY UNIT POWER LEVEL Art Orticelle 1989 Docket No. Unit Name Date Telephone Extension Day Average Daily Power Level Day Average Daily (MWe-NET) (MWe-NET) 1 180 17 1058 2 354 18 1084 3 934 19 1088 4 1030 20 1065 5 10 62 21 1103 6 1087 22 1083 7 1099 23 1103 8 1085 24 1092 9 1074 25 1111 10 1002 26 1083 11 914 27 1097 12 0 28 1077 13 0 29 1079 14 0 30 1094 15 0 31 16 791 Pg. 8.1-7 Rl 50-311 Salem # 2 5-09-89 609-935-6000 4451 Power Level OPERATING DATA REPORT 50-311 5-09-89 Completed by Pell White Docket No. Date Telephone Extension 935-6000 4451 Operating Status Unit Name Salem No. 2 Notes Reporting Period --April 198 9 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) 1170 Design Electrical Rating (Net MWe) TITS Maximum Dependable Capacity(Gross MWe)ll49 Maximum Dependable Capacity (Net MWe) 1106. 1. 2. 3. 4. 5. 6. 7. 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 719 2879 66168 12. No. of Hrs. Reactor was Critical 632.9 2415.5 40771.3 13. Reactor Reserve Shutdown Hrs. 0 0 0 14. Hours Generator On-Line 609.23 2273.73 39396.3 15. Unit Reserve Shutdown Hours 0 0 0 16. Gross Thermal Energy Generated (MWH) 1978951.2 7350640.8 72015737.8

17. Gross Elec. Energy Generated (MWH) 6 4 7 91 0 2 4 0 6 6 15 4 0 2 9 0 915 18. Net Elec. Energy Generated (MWH) 637458 2348193 38323498 19. Unit Service Factor 84.7 78.9 59.5 20. Unit Availability Factor 84.7 78.9 59.5 21. Unit Capacity Factor (using MDC Net) 80.2 73.7 52.4 22. Unit Capacity Factor (using DER Net) 79.5 74.7 51.9 23. Unit Forced Outage Rate 15.3 21.0 28.2 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: N/A 8-l-7.R2 Completed by No. Date 0095 04-01-89 0096 04-01-89 0102 04-01-89 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH APRIL 1989 Docket No. 50-311 Unit Name Date Telephone Extension Salem No.2 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1 2 Rea eta r Rep art F 8.65 A 3 F 0 A 5 F 101.12 A 3 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refue ling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Component Code 4 Code 5 IE INSTRU HE VAL VEX IE INSTRU 3 Method 1-Manual 2-Manual Scram. 3-Automatic Scram. 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 5-09-89 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence S/G STEAM FLOW INSTRUMENTATION TURBINE CONTROL VALVES e STEAM GENERATOR INSTRUMENTATION 4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Salem as Source WO NO 880712163 890123050 890222134 890405095 890405096 890417182 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2 23 INNER PEN FAILURE DESCRIPTION:

23 INNER PEN AREA EX FAN/REPLACE PER 2SM-00672.

2 22GB3 FAILURE DESCRIPTION:

BODY TO BONNET LEAK/LEAK REPAIR D-73. 2 2CV32 6 FAILURE DESCRIPTION:

PACKING LEAK. OLD TYPE PACKING-ADJUST.

2 CHANGEOUT OF MECH. SNUBBER 2S-MSASN-155 FAILURE DESCRIPTION:

PER ENGINEERING REQUEST CHANGEOUT PSA-3 MECHANICAL SNUBBER. 2 CHANGEOUT OF MECH. SNUBBER 2S-22FWSN-013B FAILURE DESCRIPTION:

PER ENGINEERING REQUEST CHANGEOUT PSA-3 MECHANICAL SNUBBER. 2 2C 125 VDC BTRY RM EXH FAN MTR FAILURE DESCRIPTION:

2C 125 VDC BTRY RM EXH FAN MTR/ INOPERABLE/

REWORK.

MAJOR PLANT .REPORT MONTH APRIL 19 8 9 *OCR NO. PRINCIPAL SYSTEM 2EC-02019 Turbine Controls 2EC-02235 Main Steam 2SC-00538 Boric Acid 2SC-01617 Rad. Monitoring 2SM-00319 Safety Injection

• Design Change Request DOCKET 9: UNIT NAME: .DATE: COMPLETED BY: TELEPHONE:

DESCRIPTION 50-311 Salem 2 May 10, 1989 P. White 609/339-4455 This design change replaced the existing Westinghouse manufactured supervisory instruments with ones manufactured by Bentley-Nevada.

This design change increased the oil reservoir capacity to the 21, 22, 23 & 24 MS167 Valves. This design change replaced 'Nos. 21 & 22 Boric Acid Evaporator Concentrates Pumps with Goulds Model 3196MT. The 2" suction piping and valves were also replaced with 3" piping and valves. This design change takes an air sample from the CRDM exhaust fans and pipes it to an RMS detector to enable detection of any Rd-88. This design change removed the clutch tripping mechanism from the SJ44 Valve limitorque operators.

e 0 MAJOR PLANT MODIFICATIONS REPQRT MONTH APRIL 1989 e DOCKET UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

• DCR SAFETY EVALUATION 10 CFR 50.59 50-272 Salem 2 May 10, 1989 P. White (609)339-4455 2EC-02019 This design change replaced the existing Westinghouse manufactured supervisory instruments with ones manufactured by Bentley-Nevada.

The following systems were included:

vibration; casing expansion; zero speed; rotor eccentricity;.

differential expansion;.

and rotor position.

Also included with the system are analog multi pen recorders to provide a permanent record of critical trends. 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.

2EC-02235 The extension allows for the expansion and/or surging of the hydraulic fluid. The actual quantity of fluid in the system remained the same and the function and operation of the system remained unchanged.

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-00538 The replacement pumps suse mechanical seals which have been service proven on boric acid transfer pumps and have a lower required net positive suction head. The suction line size increase will significantly increase the availabie net positive suction head. 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-01617 This change was made in response to an NRC commitment and provides the capability to detect a Rx head leak. 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-00319 This design change removed the clutch tripping mechanism from the SJ44 Valve limitorque operators.

This modification eliminated potential failures of the valve operator gear assemblies.

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 APRIL 1989 The Unit began the period shutdown following problems discovered with the Auxiliary Building Ventilation System. The problems were corrected and a Unit startup was commenced on April 1, 1989. During the subsequent power escalation recalibrations were performed on several steam flow indication The Unit achieved full power on April 4, 1989, and continued to operate at essentially full power until April 11, 1989, when the Reactor tripped during the performance of surveillance testing. The Unit was restored to full power on April 16, 1989, and continued to operate at essentially full power for the remainder of the period.

REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY: P. White DATE: May 10, 1989 TELEPHONE:

609/935-6000 EXTENSION 4455 Month April 1989 1. Refueling information has changed from last month: 2. 3. 4. YES NO X Scheduled date for next refueling:

March 23, 1991 Scheduled date for restart following refueling:

June 5, 1991 A) B) Will Technical Specification changes or other license amendments be required?

YES NO NOT X Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled?

February 1991 5. Scheduled date(s) for submitting proposed licensing action: January 1991 6. Important licensing considerations*associated with refueling:

NONE

7. 8. 9. 8-l-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

TO PORVs or SAFETY VALVES Salerri Unit 2 In accordance with the requirements of Salem Generating Station Unit 2 Technical Specifications Section 6.9.1.6, the following recent challenges to PORVs or Safety Valves are being reported:

04-11-89 -On April 11, 1989, Salem Unit 2 experienced a Reactor Trip on No. 24 Steam Generator Low Level. Following this occurrence, Main Main Steam Line Safety Valve 24MS15 lifted twice. The first valve lift occured at its setpoint of 1070 psig, after which it seater properly.

Approximately one hour later the second lift occurred at a steam line pressure of 1010 psig. The valve remained open for approximately one hour. Reactor Coolant System average temperature was reduced to 535°F to have the valve fully reseat.