ML18093A792

Monthly Operating Rept for Mar 1988.W/880411 Ltr

ML18093A792
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 8804190048
Download: ML18093A792 (11)

Text

., AVERAGE DAILY UNIT POWER LEVEL 50-27 2 Salem # 1 Completed by Pell White Docket No. Unit Name Date Telephone Extension April 10, 1988 609-935-6000 Month MARCH 1988 Day Average Daily Power (MWe-NET) 1 928 2 1061 3 1134 4 1125 5 1097 6 1138 7 1081 8 10 98 9 1109 10 1112 11 1110 12 1122 13 1103 14 1110 15 1110 16 1107 P. 8.1-7 Rl 19004*:3 :3:30:::::31 PDR ADOCK 05000272 R DCD 4451 Level Day Average Daily Power Level (MWe-NET) 17 1116 18 1101 19 1127 20 1120 21 110 2 22 1116 23 1108 24 1112 25 1112 26 1109 27 1135 28 1111 29 1112 30 516 31 0

-OPERATING DATA REPORT Docket No .50-272 April 10,1988 Date: Telephone:

935-6000 Completed by Pell White Extension:

4451 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period March 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 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 95713 12. No. of Hrs. Reactor was Critical 70 7. 8 849.0 58544.1 1 3. Reactor Reserve Shutdown Hrs. 0 0 0 14. Hours Generator On-Line 707.8 7 7 1. 5 56563.3 1 5 . Unit Reserve Shutdown Hours 0 0 0 16. Gross Thermal Energy Generated (MWH) 2404896 2521985 174790994

17. Gross Elec. Energy Generated (MWH) 812940 845350 58072250 1 8. Net Elec. Energy Generated (MWH) 780378 788565 55192961 19. Unit Service Factor 95. 1 35.3 60.0 2 0. Unit Availability Factor 9 5. 1 35.3 60.0 21. Unit Capacity Factor (using MDC Net) 94. 8 32.6 52.9 22. Unit Capacity Factor (using DER Net) 94. 1 32.4 52.5 2 3. Unit Forced Outage Rate 2.8 4.7 24.0 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: 4-13-88 8-1-7.R2 Completed by No. Date 0031 3-30-88 0032 3-31-88 1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH MARCH 1988 Docket No.50-272 Unit Name _S_a_l_e_m--N-o-.

-1=-* ---Pell White Method of Duration Shutting License Type Hours Reason Down Event 1 2 Reactor Report F 20.2 A 2 s 16.0 B 4 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Adm in is t rat ive G-Operational Error-explain H-Other-explain Date April 10, 1988 Telephone 609-935-6000 Extension 4451 System Component Code 4 Code 5 HA INSTRU CB HTEXCH 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 TURBINE HYDRAULIC SYSTEM NUCLEAR STEAM GENERATOR TUBE LEAK-4 Exhibit G Instructions for tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Sou re e WO NO 870406024 870513047 871014074 880113113 880115085 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1 14MS175 FAILURE DESCRIPTION:

VALVE LEAKS THRU REPLACE VALVE BONNET. 1 11MS131 FAILURE DESCRIPTION:

HAS A FURMANITED BONNET AND IS BLOWING STEAM. 1 1MS204 FAILURE DESCRIPTION:

VALVE LEAKS THRU REPLACE VALVE 1 POLAR CRANE/AUX HST PAWL DAMAGED FAILURE DESCRIPTION:

THE AUX HOIST LOAD BRAKE RATCHET PAWL. 1 13 cc 19 7 FAILURE DESCRIPTION:

WELD REPAIR BROKEN LINE WHERE INSTRUMENT LINE TIES INTO THE ROOT VALVE.

SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880129101 1 1SJ12 FAILURE DESCRIPTION:

LEAKS BY ITS SEATS. PERFORM VALVE DISK MODIFICATION 880129102 1 1SW310 FAILURE DESCRIPTION:

LEAK IN WELD, REPAIR WELD. 880217106 1 lRCE 1 FAILURE DESCRIPTION:

INCORE SYSTEM H.P. SEALS LEAKING/REPAIR. "THREE H.P. SEALS. 880302127 1 llSJ93 FAILURE DESCRIPTION:

EXCEEDED PREVIOUS STROKE TIME BY GRATER THAT 25%. 880309059 1 P/A CONVERTER FOR ROD IND FAILURE DESCRIPTION:

FAILED, TROUBLESHOOT 880310109 1 1FA5505/14CFCU FLOW IND. FAILURE DESCRIPTION:

ERRATIC/INVESTIGATE AND REPAIR SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 880314053 1 1G8D/4KV BRK FAILURE DESCRIPTION:

SPRINGS WILL NOT CHARGE OR CLOSE/THROUBLESHOOT.

MAJOR PLANT MODIFICATIONS REPORT March 1988 *DCR NO. lEC-1959 lEC-2060 PRINCIPAL SYSTEM Bldg. & Equip Drns Flood & Sump Pumps Containment Airlocks

• DCR -Design Change Request DOCKET NO.: 50-272 UN IT NAME: Salem 1 DATE: April 10,1988 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 DESCRIPTION This design change replaced Nos. 11, 12, and 14 Turbine Area Sump Pumps with submersible slurry type pumps. This change is being made because the previous model of the Turbine Area Sump Pumps was discontinued by the manufacturer.

The new pumps area adequately designed for the erosive and corrosive water collected in the sumps. This design change replaced the teflon packing in the shaft seal assemblies of the Containment Airlocks with grafoil packing. At high levels of radiation, teflon can experience some degree of degradation, however, testing has shown that the grafoil replacement packing can withstand LOCA radiation doses.

MAJOR PLANT MODIFICATIONS REPORT MONTH MARCH 1988 DOCKET NO. 50-272 UN IT NAME: Salem 1 *DCR lEC-1959 lEC-2060 DATE: April 10,1988 COMPLETED BY: J. Ronafalvy TELEPHONE:

609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This design change improved the function and accessibility of the system for scheduled maintenance.

The design change does not affect the safe shutdown of the reactor or introduce any new fire hazards. No changes have been made to any plant process or discharge or the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

The graf oil packing installed by this design change is an acceptable alternative for teflon packing in the Containment Airlocks.

The grafoil packing has a higher resistance to radiation induced damage and is well able to withstand the design accident dose rate. This design change did not alter any plant process or discharge and did not affect the environmental impact of the plant. No unreviewed safety or environmental questions are involved.

• DCR -Design Change Request

' ,, SALEM UNIT NO. 1 SALBM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT NO. 1 MARCH 1988 The Unit began the period operating at 80% power for evaluation of a primary to secondary tube leak in No. 13 Stearn Generator.

On March 2, 1988, power was increased to 100% and the Unit continued to operate at full power until March 30, 1988, when it was manually tripped due to the loss of the electro-hydraulic control oil pumps. The Unit continued shutdown throughout the remainder of the period for repairs to the tube leak in No. 13 S/G. The calculated leak rate in No. 13 S/G varied throughout the month, first decreasing to a low of 20-30 gpd and subsequently increasing to a high of 103 gpd at the conclusion of the month. The Reactor Vessel Head Air Particulate Monitor, installed following the recent CRDM column leaks, has been placed in service and is indicating normal background levels.

PEFUET,ING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: J. Ronafalvv UNIT NAME: Salem 1 DATE: April 10,1988 TELEPHONE:

609/935-6000 EXTENSION:

Month MARCH 1988 1. Refueling information has changed from last month: YES NO X 2. Scheduled date for next refueling:

April 15, 19 89 3. Scheduled date for restart following refueling:

May 30, 1989 4. A) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO 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 1989 5. Scheduled date(s) for submitting proposed licensing action: February 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 193 464 1170 1170 September 2001 e

• 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. 1 DOCKET NO. 50-272 1-\pril 11, 1988 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of March 1988 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 Sincerely yours, J.9::1:;:!2:

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 1 /r 95-2189 (11 M) 12-84