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.

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 RH:pc cc: Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8::). *R4 The Energy People

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~J PDR ADOCK 05000311 95-2168 (100M) 12-84 R PDR

~ AVERAGE DAILY UNIT POWER.EVEL Docket No.: 50-311 Unit Name: Salem #2 Date: 12/10/90 Completed by: Art Orticelle Telephone: 339-2122 Month November 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 1085 17 1103 2 1097 18 1082 3 1080 19 1087 4 1103 20 1107 5 1087 21 1099 6 1114 22 1099 7 1106 23 1108 8 1087 24 1085 9 1102 25 1115 10 1108 26 1115 11 1095 27 1115 12 1091 28 1114 13 1081 29 1110 14 577 30 1040 15 969 31 16 1089 P. 8.1-7 Rl

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 ~~~~N--...-A~~~~~~~~~~~~~~~

This Month Year to Date cumulative

11. Hours in Reporting Period 720 8016 80065

12. No. of Hrs. Rx. was Critical 720 4606.4 50612.2

13. Reactor Reserve Shutdown Hrs. 0 0 0

14. Hours Generator On-Line 720 4420.9 48966.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2403902.4 14456426.4 103508165.8

17. Gross Elec. Energy Generated (MWH) 814343 4847011 50894063

18. Net Elec. Energy Gen. (MWH) 782421 4602812 48402718

19. Unit Service Factor 100 55.2 61.2

20. Unit Availability Factor 100 55.2 61. 2

21. Unit Capacity Factor (using MDC Net) 98.3 51.9 54. 7 '

22. Unit Capacity Factor (using DER Net) 97.5 51.5 54.2

23. Unit Forced Outage Rate. 0 7.1 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

UNIT SHUTDOYN AND POYER REDUCTIONS REPORT MONTH NOVEMBER 1990 DOCKET NO. 50-311 .

UNIT NAME Salem #2 DATE 12/10/90 COMPLETED BY Art Orticel le TELEPHONE 339-2122 '

METHOD OF SHUTTING LICENSE DURATION DOYN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 0100 11/13/90 F 24.7 A 5 ------- HA GENERA GENERATOR H2 LEAK 0099 11/15/90 F 9.5 A 5 ------- - HA GENERA GENERATOR H2 LEAK 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - same S: Scheduled A-Equipment Failure (explain) 1-Manual 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-Requlatory Restriction 4-Continuation of CNUREG-0161)

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

e-SAFETY RELATED MAINTENANCE DOCKET NO: 50-311 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 WO NO UNIT EQUIPMENT IDENTIFICATION 880728117 2 2S27C FAILURE DESCRIPTION: FLANGES AND PIPING ERODED -

REWORK 890320149 2 2FHV5 DAMPER FAILURE DESCRIPTION: FHB DAMPER OPERATOR MISSING BOLT

- REWORK 890601561 2 23SW25 FAILURE DESCRIPTION: SPINDLE MISSING - REPLACE SPINDLE AND BONNET 901008201 2 25SW2 FAILURE DESCRIPTION: REPLACE THE VALVE AS PER THE CODE JOB PACKAGE 901022283 2 21 SW PUMP STRNR FAILURE DESCRIPTION: AUTO STRAINER HIGH DELTA P -

TROUBLESHOOT AND REPAIR 901031131 2 2SV920 FAILURE DESCRIPTION: 21 CFCU HEPA FILTER OUTLET DAMPER WILL NOT CLOSE - TROUBLESHOOT

10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (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

SUMMARY

A. Design Change Packages 2SC-2160 Pkg. 1 "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) 2SC-2161 Pkg. 1 "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)

B. Procedures and Revisions 2IC-18.1.013 "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 GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 NOVEMBER 1990 SALEM UNIT NO. 2 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 DOCKET NO: 50-311 MONTH: - NOVEMBER 1990 UNIT NAME: SALEM 2 DATE: DECEMBER 10, 1990 COMPLETED BY: F. THOMSON TELEPHONE: (609)339-2904 MONTH NOVEMBER 1990

1. Refueling information has changed from last month:

YES NO ~~X~~

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 ~=x~-

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