ML18095A641

Monthly Operating Rept for Nov 1990 for Salem 2.W/901214 Ltr

ML18095A641
Person / Time
Site:	Salem
Issue date:	11/30/1990
From:	LABRUNA S, ORTICELLE A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012210136
Download: ML18095A641 (8)

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department December 14, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 November 1990 are being sent to you. RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations 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::) .* R4 The Energy People !,-----CJ() 1-?**;* 1 " .? .. ..._.,...

._. -* ** "" * .... *-* .. PDR ADOCK 05000311 R PDR 95-2168 (100M) 12-84 AVERAGE DAILY UNIT POWER.EVEL Completed by: Art Orticelle Month November 1990 Day Average Daily Power Level (MWe-NET) 1 1085 2 1097 3 1080 4 1103 5 1087 6 1114 7 1106 8 1087 9 1102 10 1108 11 1095 12 1091 13 1081 14 577 15 969 16 1089 P. 8.1-7 Rl Day Docket No.: 50-311 Unit Name: Salem #2 Date: 12/10/90 Telephone:

339-2122 Average Daily Power Level (MWe-NET) 17 1103 18 1082 19 1087 20 1107 21 1099 22 1099 23 1108 24 1085 25 1115 26 1115 27 1115 28 1114 29 1110 30 1040 31 e OPERATING DATA REPO., Docket No: 50-311 Date: 12/10/90 Completed by: Art Orticelle Telephone:

339-2122 Operating status 1. Unit Name Salem No. 2 Notes 2. Reporting Period November 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 NA 9. Power Level to Which Restricted, if any (Net MWe) N/A 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 720 720 0 720 0 2403902.4 814343 782421 100 100 98.3 97.5 0 Year to Date 8016 4606.4 0 4420.9 0 14456426.4 4847011 4602812 55.2 55.2 51.9 51.5 7.1 cumulative 80065 50612.2 0 48966.1 0 103508165.8 50894063 48402718 61.2 61. 2 54. 7 ' 54.2 24.6 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: NA 8-l-7.R2 NO. DATE 0100 11/13/90 0099 11/15/90 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 F 24.7 F 9.5 Reason A-Equipment Failure (explain)

B-Maintenance or Test C-Refueling D-Requlatory Restriction A A UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH NOVEMBER 1990 METHOD OF SHUTTING DOYN REACTOR 5 5 3 LICENSE EVENT REPORT # ---------------Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 HA HA E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain>

H-Other (Explain) 4 DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 . Salem #2 12/10/90 Art Orticel le 339-2122 ' COMPONENT CAUSE AND CORRECTIVE ACTION CODE 5 TO PREVENT RECURRENCE GENERA GENERATOR H 2 LEAK GENERA GENERATOR H 2 LEAK Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161)

-5 Exhibit 1 -same Source e-SAFETY RELATED MAINTENANCE MONTH: -NOVEMBER 1990 DOCKET NO: UNIT NAME: 50-311 SALEM 2 WO NO UNIT 880728117 2 890320149 2 890601561 2 901008201 2 901022283 2 901031131 2 2S27C DATE: COMPLETED BY: TELEPHONE:

DECEMBER 10, 1990 F. THOMSON (609)339-2904 EQUIPMENT IDENTIFICATION FAILURE DESCRIPTION:

FLANGES AND PIPING ERODED -REWORK 2FHV5 DAMPER FAILURE DESCRIPTION:

FHB DAMPER OPERATOR MISSING BOLT -REWORK 23SW25 FAILURE DESCRIPTION:

SPINDLE MISSING -REPLACE SPINDLE AND BONNET 25SW2 FAILURE DESCRIPTION:

REPLACE THE VALVE AS PER THE CODE JOB PACKAGE 21 SW PUMP STRNR FAILURE DESCRIPTION:

AUTO STRAINER HIGH DELTA P -TROUBLESHOOT AND REPAIR 2SV920 FAILURE DESCRIPTION:

21 CFCU HEPA FILTER OUTLET DAMPER WILL NOT CLOSE -TROUBLESHOOT 10CFR50.59 EVALUATIONS MONTH: -NOVEMBER 1990 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

50-311 SALEM 2 DECEMBER 10, 1990 F. THOMSON (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.

The Station Operations Review Committee has reviewed these evaluations and agrees with their conclusions that these items do not present Unreviewed Safety Questions (USQs). ITEM A. Design Change Packages 2SC-2160 Pkg. 1 2SC-2161 Pkg. 1 B. Procedures and Revisions 2IC-18.1.013

SUMMARY

"C02 System Automation" -The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry.

To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation.

The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154) "C02 System Automation" -The purpose of this design change is to modify the manually actuated C02 Fire Suppression System to include automatic actuation circuitry.

To accomplish this, new spot thermal detection will be added to the affected rooms. The new thermal type detectors will be utilized for automatic C02 system actuation.

The existing ionization type detection zones will remain in place but will be rewired to provide an "early warning" signal only. (SORC 90-154) "Train A & B Reactor Trip Breaker Operability Test" Rev. 4 -The purpose of this revision is incorporate a change in the NRC reporting requirements from one (1) hour to thirty (30) days and provide a method of testing with a loss of the P-250 computer. (SORC 90-150)

SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

-UNIT 2 NOVEMBER 1990 The Unit began the period operating at 100% power. Power was reduced to 50% on 11/14/90, due to increased hydrogen consumption in the Main Generator.

The source of the leakage, identified as RTD and thermocouple electrical penetration seals, was corrected and the Unit restored to full power on 11/15/90.

The Unit continued to operate at essentially full power throughout the remainder of the period.

REFUELING INFORMATION MONTH: -NOVEMBER 1990 MONTH NOVEMBER 1990 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:

1. Refueling information has changed from last month: YES NO 50-311 SALEM 2 DECEMBER 10, 1990 F. THOMSON (609)339-2904

2. Scheduled date for next refueling:

November 30, 1991 3. Scheduled date for restart following refueling:

February 9, 1992 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?:

October 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 316 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:

March 2003 8-1-7.R4