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 CPS~G Pub Iic 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.

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 RH:pc 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 Docket No.: 50-272 Unit Name: Salem #1 Date: 10/11/90 Completed by: Art Orticelle Telephone: 609-339-2122 Month SEPTEMBER 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 951 2 0 18 932 3 0 19 989 4 0 20 1039 5 0 21 1062 6 0 22 1067 7 0 23 *1043 8 291 24 1059 9 736 25 1059 10 402 26 1070 11 0 27 1084 12 0 28 1088 13 0 29 1105 14 178 30 1052 15 514 31 16 766 P. 8.1-7 Rl

.. ~ 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) ~~--"-'N~/~A'--~~~~~-

10. Reasons for Restrictions, if any ~=N~/=A"--~~~~~~~~~~~~~~~~

This Month Year to Date Cumulative

11. Hours in Reporting Period 720 6651 116184

12. No. of Hrs. Rx. was Critical . 512. 7 3845.9 74754.5

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 464.5 3662.8 72358.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1377753.6 11725956.0 226826882.0

17. Gross Elec. Energy Generated (MWH) 441300 3847430 75308790

18. Net Elec. Energy Gen. (MWH) 411537 3652059 71663769

19. Unit Service Factor 64.5 55.9 62.3

20. Unit Availability Factor 64.5 55.9 62.3

21. Unit Capacity Factor (using MDC Net) 51.7 50.4 55.8

22. Unit Capacity Factor (using DER Net) 51.3 50.0 55.3

23. Unit Forced Outage Rate 35.5 44.1 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

UNIT SHUTDOWN AND POWER REDUCTIONS DOCKET NO.: 50-272 REPORT MONTH ~EPTEMBER 1990 UNIT NAME: Salem #1 DATE: 10£10£90 COMPLETED BY: Art Orticel l.'l.-

TELEPHONE: 339-2122

-r-I METHOD OF I I SHUTTING LICENSE I DURATION 2 I DOWN EVENT SYSTE~ COMPO~ENT I CAUSE AND CORRECTIVE ACTION NO. DATE TYPE (HOURS) REASON I REACTOR REPORT # CODE CODE I TO PREVENT RECURRENCE 0058 09/01/90 I F 75.3 A 4 --------- CB MOTORX #14 RCP Motor Replacement 0060 09/04/90 I F 89.6 A 4 --------- WG PUMP XX #13 Aux Feed Pump Problem 0059 09/08/90 F 9.7 A 5 , HB HTEXCH MSR Trouble 0061 09/09/90 I F 114.6 A 5 HH PUMPXX #12 Condensate Pump 0062 09/10/90 I F 90.6 A 3 HB VAL VEX Turbine E.H. System 0063 09/15/90 I F 23.4 A 5 CH INSTRU #12 SGFP Ground Problem 0067 09/24/90 I F 5.0 B 5 cc INSTRU Steam Flow Transmitters I I

2 3 4 5 F: Forced Reason: Method: Exhibit G - Instructions Exhibit 1 - Same s: Scheduled A-Equipment Failure (Explain) 1-Man~al for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report CLER) File D-Regulatory Restriction 4-Continuation of (NUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - SEPTEMBER 1990 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 WO NO

• UNIT EQUIPMENT IDENTIFICATION 890221197 1 11 & 21 HYDROGEN ANALYZERS FAILURE DESCRIPTION: CALIBRATION UNSUCCESSFUL DUE TO LOSS OF HIGH CAL. - TROUBLESHOOT 900303075 1 FIRE DAMPER 1CVF602 FAILURE DESCRIPTION: FIRE DAMPER FAILED TO ANNUNCIATE DURING SURVEILLANCE -

TROUBLESHOOT

~-------------------------------------------------------------------------

900801211 1 MAIN STEAM PIPING FAILURE DESCRIPTION: PERFORM UT EXAMINATIONS OF SELECTED WELDS 900821021 1 11SW34, 36, 38, 47, 53 & 77 FAILURE DESCRIPTION: PERFORM RADIOGRAPHY TO VERIFY THE VALVE POSITIONS

- -- -- --*-* **~- -. -*--. ,. ""'"""

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - SEPTEMBER 1990 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRON!

TELEPHONE: (609) 339-2068

• DCR PRINCIPAL SYSTEM DESCRIPTION None for the period.

• DCR - Design Change Request

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 SEPTEMBER 1990 SALEM UNIT NO. 1 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 attempt~ng 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 DOCKET NO: 50:...272 MONTH: - SEPTEMBER 1990 UNIT NAME: SALEM 1 DATE: OCTOBER 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 MONTH SEPTEMBER 1990

1. Refueling information has changed from last month:

YES NO X

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 ~x~~

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