ML18095A282
| ML18095A282 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/31/1990 |
| From: | MILLER L K, MORRONI M, ORTICELLE A Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9006190091 | |
| Download: ML18095A282 (9) | |
Text
{{#Wiki_filter:., . 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 June 12, 1990 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 May 1990 are being sent to you. Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance RH:pc Major Plant Modifications Operating Summary Refueling Information Sincerely yours, L. K. Miller 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 9006190091-900531 PDR ADOCK 05000272 R PDC pf.I '// 95-2189 (11 M) 12-84 .. Month MAY, 1990 Day Average Daily Power (MWe-NET) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 P. 8.1-7 Rl AVERAGE DAILY UNIT POWER LEVEL Level Docket No. Unit Name Date Completed by Telephone 50-272 Salem # 1 06-10-90 Art Orticelle 609-339-2122 Day Average Daily Power Level (MWe-NET) 17 0 18 0 19 0 20 0 21 0 22 0 23 0 24 0 25 0 26 0 27 0 28 0 29 0 30 0 31 0 .. OPERATING DATA REPORT Docket No: 50-272 Date: 06-10-90 Completed by: Art Orticelle Telephone: 609-339-2122 Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period May 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 This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 3623 113256 12. No. of Hrs. Reactor was Critical 0 2162.7 73071.2 13. Reactor Reserve Shutdown Hrs. 0 0 0 14. Hours Generator On-Line 0 2102.8 70798.6 15. Unit Reserve Shutdown Hours 0 0 0 16. Gross Thermal Energy Generated (MWH) 0 6892562.4 221993488.4
- 17. Gross Elec. Energy Generated (MWH) 0 2290760 73752120 18. Net Elec. Energy Generated (MWH) -10044 2193174 70204884 19. Unit Service Factor 0 58.0 62.5 20. Unit Availability Factor 0 58.0 62.5 21. Unit Capacity Factor -{using MDC Net) 0 54.7 56.0 22. Unit Capacity Factor {using DER Net) 0 54.3 55.6 23. Unit Forced Outage Rate 100 41. 9 22.3 24. Shutdowns scheduled over next 6 months (type, date and duration of each) Unit #1 Ninth Refueling scheduled on October 6, 1990 and lasting 45 davs. 25. If shutdown at end of Report Period, Estimated Date of Startup: Estimated start-up date of June 7, 1990. 8-l-7.R2 NO. DATE 0035 5-01-90 i i i 1 F: Forced S: Scheduled UNIT SHUTOOWN AND POWER REDUCTIONS lXJCKEI'NO.:
___ _ r-uNTH ___ _ UNIT NAME: Salem #1 '1YPE 1 F I 2 Reason: DURATION (BOORS) REASON 2 744 A l A-F.quiprent Failure (Explain) B-Maintenance or Test C-Refueling D-Regulatory Restriction MEI'HOD OF SHUTI'ING OOWN REACTOR 3 I E-Dperator Training & License Examination F-Administrative G-Dperational Error (R\.'J>lain) H-OthPr (J;'m l 'li n) LICENSE EVENT SYSTEM REIDRI' # CDDE 4 -------CH 3 Method: 1-Manual 2-Manual Scram 3-Autanatic Scram 4-COntinuation of Previous Outage 5-load Reduction 9--0ther ( DA'IE: 06-10-90 CiltPI.EI'ED BY: Art Orticelle TELEPHONE: 339-2122 cmroNENT CAUSE AND CDRRFCTIVE ACTION 4 CDDE 0 'ID PREVENT RECURRENCE INSTRU #12 S.G. FEED PUMP Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NURffi-0161) 5 Exhibit 1 -Same Source .* I I SAFETY RELATED MAINTENANCE MONTH: -MAY 1990 DOCKET NO: UNIT r.TAME: 50-272 SALEM 1 WO NO 890307143 900326142 900504117 900517136 900521058 900521068 900527061 UNIT 1 1 1 1 1 DATE: COMPLETED BY: TELEPHONE: JUNE 10, 1990 M. MORRONI (609) 339-2068 EQUIPMENT IDENTIFICATION 11 SAFETY INJECTION PUMP FAILURE DESCRIPTION: CHANGE OUT ROTATING ASSEMBLY REACTOR COOLANT WIDE RANGE PRESSURE INDICATION FAILURE DESCRIPTION: HIGH INDICATION -TROUBLESHOOT 11 CHARGING PUMP FAILURE DESCRIPTION: REWELD ALIGNING DOWEL AND CENTERING PIN BLOCK CABLE SEPARATION FAILURE DESCRIPTION: CORRECT CABLE SEPARATION CRITERIA VIOLATIONS 1RC41 REACTOR HEAD VENT SOLENOID FAILURE DESCRIPTION: VALVE DOES NOT OPEN -INVESTIGATE 1 1 1RC43 REACTOR HEAD VENT FAILURE DESCRIPTION: VALVE DOES NOT OPEN -INVESTIGATE 12CV19 FAILURE DESCRIPTION: NO OPEN OR CLOSE INDICATION -TROUBLESHOOT AND REPAIR MAJOR PLANT MODIFICATIONS MONTH: -MAY 1990 *DCR PRINCIPAL SYSTEM lSC-2233 Main Transformer
- DCR -Design Change Request DOCKET NO: 50-272 UNIT NAME: SALEM 1 DATE: COMPLETED BY: 'TELEPHONE:
JUNE 10, 1990 M. MORRONI (609) 339-2068 DESCRIPTION This design change replaced the Main Generator Transformer Phases "A", "B", and "C" with transformers obtained from the Washington Public Power Supply System. MAJOR PLANT MODIFICATIONS MONTH: -MAY 1990 DOCKET NO: UNIT NAME: 50-272 SALEM 1 *DCR lSC-2233 DATE: COMPLETED BY: TELEPHONE: SAFETY EVALUATION 10 CFR 50.59 JUNE 10, 1990 11. MORRONI (609) 339-2068 This design change replaced the Main Generator Transformer Phases "A", "B", and "C" with transformers obtained from the Washington Public Power Supply System. The replacement transformers have been analyzed and found to be acceptable for this application. There is no change to any plant process or discharge or to the environmental impact of the plant. No unreviewed safety or environmental questions are involved.
- DCR -Design Change Request SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-UNIT 1 MAY 1990 The Unit remained shutdown throughout the period for investigation and resolution of Emergency Core Cooling System (ECCS) issues. During this period, issues related to cable separation criteria and Residual Heat Removal (RHR) problems, were also addressed.
J ' . , , REFUELING INFORMATION MONTH: -MAY 1990 MONTH MAY 1990 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
- 1. Refueling information has changed from last month: YES x NO 50-272 SALEH 1 JUNE 10, 1990 11. MORRONI (609) 339-2068 2 . Scheduled date for next refueling:
October 2Q, 1990 3. Scheduled date for restart following refueling: December 13, 1990 4. a) Will Technical Specification changes or other license amendments be required?: YES NO l\TO'I' DETERMINED TO DATE -=x __ b) Has the reload fuel design been reviewed by the Station Operating Review Committee?: YES NO If no, when is it scheduled?: Se-otember 1990 5. Scheduled date(s) for submitting proposed licensing action: N/A 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
- a. In core 193 b. In Spent Fuel Storage 540 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}}