ML18095A531

Monthly Operating Rept for Sept 1990 for Salem Unit 1.W/ 901012 Ltr

ML18095A531
Person / Time
Site:	Salem
Issue date:	09/30/1990
From:	LABRUNA S, MORRONI M, ORTICELLE A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9010240133
Download: ML18095A531 (8)

Text

. e Pub I ic Service Electric and Gas Company P .0. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station, October 12, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 September 1990 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours, General Manager -Salem Operations cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7. R4 ,.---The Energy People 95-21 89 (11 M) 1 2-84

'* .BRAGE DAILY UNIT POWER LEIL Completed by: Art Orticelle Month SEPTEMBER 1990 Day Average Daily Power Level (MWe-NET) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 291 9 736 10 402 11 0 12 0 13 0 14 178 15 514 16 766 P. 8.1-7 Rl Day Docket No.: 50-272 Unit Name: Salem #1 Date: 10/11/90 Telephone:

609-339-2122 Average Daily Power Level (MWe-NET) 17 951 18 932 19 989 20 1039 21 1062 22 1067 23 *1043 24 1059 25 1059 26 1070 27 1084 28 1088 29 1105 30 1052 31

.. OPERATING DATA REPORT Docket No: 50-272 Date: 10-11-90 Completed by: Art Orticelle Telephone:

609-339-2122 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period SEPTEMBER 1990 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) 1149 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)

10. Reasons for Restrictions, if any

11. Hours in Reporting Period 12. No. of Hrs. Rx. 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 Gen. (MWH) 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 720 . 512. 7 0 464.5 0 1377753.6 441300 411537 64.5 64.5 51.7 51.3 35.5 Year to Date 6651 3845.9 0 3662.8 0 11725956.0 3847430 3652059 55.9 55.9 50.4 50.0 44.1 Cumulative 116184 74754.5 0 72358.5 0 226826882.0 75308790 71663769 62.3 62.3 55.8 55.3 23.0 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Refueling Outage scheduled to start 02/09/91 and last 55 days. 25. If shutdown at end of Report Period, Estimated Date of Startup: NA 8-1-7.R2 NO. DATE 0058 09/01/90 I 0060 09/04/90 I 0059 09/08/90 0061 09/09/90 I 0062 09/10/90 I 0063 09/15/90 I 0067 09/24/90 I F: Forced s: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH 1990 I METHOD OF I SHUTTING LICENSE DURATION 2 I DOWN EVENT TYPE (HOURS) REASON I REACTOR REPORT # CODE F F F F F F F 2 75.3 A 89.6 A 9.7 A 114.6 A 90.6 A 23.4 A 5.0 B Reason: A-Equipment Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction 4 4 5 5 3 5 5 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

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CB ---------WG 3 , HB HH HB CH cc Method:

2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4 .. DOCKET NO.: 50-272 UNIT NAME: Salem #1 DATE: 10£10£90 COMPLETED BY: Art Orticel l.'l.-TELEPHONE:

339-2122 -r-I I I CAUSE AND CORRECTIVE ACTION CODE I TO PREVENT RECURRENCE MOTORX #14 RCP Motor Replacement PUMP XX #13 Aux Feed Pump Problem HTEXCH MSR Trouble PUMPXX #12 Condensate Pump VAL VEX Turbine E.H. System INSTRU #12 SGFP Ground Problem INSTRU Steam Flow Transmitters 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)

Exhibit 1 -Same Source I I

... , -SAFETY RELATED MAINTENANCE MONTH: -SEPTEMBER 1990 DOCKET NO: UNIT NAME: 50-272 SALEM 1 DATE: COMPLETED BY: TELEPHONE:

OCTOBER 10, 1990 M. MORRONI (609) 339-2068 --------------------------------------------------------------------------

WO NO

• UNIT EQUIPMENT IDENTIFICATION

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890221197 1 900303075 1 11 & 21 HYDROGEN ANALYZERS FAILURE DESCRIPTION:

CALIBRATION UNSUCCESSFUL DUE TO LOSS OF HIGH CAL. -TROUBLESHOOT FIRE DAMPER 1CVF602 FAILURE DESCRIPTION:

FIRE DAMPER FAILED TO ANNUNCIATE DURING SURVEILLANCE

-TROUBLESHOOT 900801211 1 900821021 1 ' ;' MAIN STEAM PIPING FAILURE DESCRIPTION:

PERFORM UT EXAMINATIONS OF SELECTED WELDS 11SW34, 36, 38, 47, 53 & 77 FAILURE DESCRIPTION:

PERFORM RADIOGRAPHY TO VERIFY THE VALVE POSITIONS

., .*'

• --------*-* -. -*--. ,. ""'""" ... MAJOR PLANT MODIFICATIONS MONTH: -SEPTEMBER 1990 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-272 SALEM 1 OCTOBER 10, 1990 M. MORRON! (609) 339-2068 -----------------------------------------------------------------------------

• DCR PRINCIPAL SYSTEM DESCRIPTION

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None for the period. *DCR -Design Change Request SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 1 SEPTEMBER 1990 The Unit began the period shutdown following replacement of No. 14 Reactor Coolant pump (RCP) Motor. During startup preparations, difficulties were encountered with a recirculation line relief valve during a surveillance test on No. 13 Auxiliary Feedwater Pump. Subsequent modifications were performed to the auxiliary feed recirculation flow paths. The Unit was returned to service on September 7, 1990, and a power escalation commenced.

The power escalation was held at two points for repair to moisture separator reheater controls, and replacement of No. 12 Condensate Pump mechanical seal. On September 10, 1990, a Reactor Trip from 78% power occurred on a Lo Lo level in No. 13 Steam Generator.

The Lo Lo level resulted from a turbine runback while to isolate one control valve with a failed drain line. The Unit returned to service on September 14, 1990. The subsequent power escalation was held at several points for investigation of a ground in No. 12 Steam Generator Feedwater Pump (SGFP) control circuitry and to calibrate steam flow instrumentation.

The Unit achieved 100% power on September 25, 1990, and continued to operate at essentially full power for the remainder of the period.

...... * .. *...+' REFUELING INFORMATION MONTH: -SEPTEMBER 1990 MONTH SEPTEMBER 1990 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES NO X 50:...272 SALEM 1 OCTOBER 10, 1990 M. MORRONI (609) 339-2068 2. Scheduled date for next refueling:

February 9, 1991 3. Scheduled date for restart following refueling:

April 10, 1991 4. a) Will Technical Specification changes or other license amendments be required?:

YES NO NOT DETERMINED TO DATE b) Has the reload fuel design been reviewed by the Station Operating Review Committee?:

YES NO x If no, when is it scheduled?:

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

7. Number of Fuel Assemblies:

a. Incore 193 b. In Spent Fuel Storage 588 8. Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

September 2001 8-1-7.R4