ML18095A282

Monthly Operating Rept for May 1990 for Salem Unit 1. W/900612 Ltr

ML18095A282
Person / Time
Site:	Salem
Issue date:	05/31/1990
From:	Miller L, Morroni M, Orticelle A Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006190091
Download: ML18095A282 (9)

Text

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  *ops~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June 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 May 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, L. K. Miller 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 9006190091- 900531 PDR R ADOCK 05000272 PDC pf.I

                                                                                        ' / / 95-2189 (11 M) 12-84

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date 06-10-90 Completed by Art Orticelle Telephone 609-339-2122 Month MAY, 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 P. 8.1-7 Rl

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) ~~-=N~/~A=--~~~~~~-

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

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

UNIT SHUTOOWN AND POWER REDUCTIONS lXJCKEI'NO.: _5~0-~~~,7=2_ _ __

                                                                   ~RI' r-uNTH ~MA=Y"--=19'""'9-'-0_ _ __                                 UNIT NAME: Salem #1 DA'IE: 06-10-90 CiltPI.EI'ED BY: Art Orticelle TELEPHONE: 339-2122 MEI'HOD OF SHUTI'ING      LICENSE DURATION                      OOWN          EVENT                SYSTEM    cmroNENT             CAUSE AND CDRRFCTIVE ACTION NO.       DATE     '1YPE 1     (BOORS)            REASON 2   REACTOR        REIDRI' #           CDDE 4    CDDE 0                  'ID PREVENT RECURRENCE 0035      5-01-90       F         744                  A           3          -------               CH      INSTRU          #12 S.G. FEED PUMP I

( i i i I l I I 1 2 3 4 5 F: Forced Reason: Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-F.quiprent Failure (Explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Autanatic Scram Event Report (LER) File D-Regulatory Restriction 4-COntinuation of (NURffi-0161) E-Dperator Training &License Examination Previous Outage F-Administrative 5-load Reduction G-Dperational Error (R\.'J>lain) 9--0ther H-OthPr (J;'m l 'li n)

SAFETY RELATED MAINTENANCE DOCKET NO: 50-272 MONTH: - MAY 1990 UNIT r.TAME: SALEM 1 DATE: JUNE 10, 1990 COMPLETED BY: M. MORRONI TELEPHONE: (609) 339-2068 WO NO UNIT EQUIPMENT IDENTIFICATION 890307143 1 11 SAFETY INJECTION PUMP FAILURE DESCRIPTION: CHANGE OUT ROTATING ASSEMBLY 900326142 1 REACTOR COOLANT WIDE RANGE PRESSURE INDICATION FAILURE DESCRIPTION: HIGH INDICATION - TROUBLESHOOT 900504117 1 11 CHARGING PUMP FAILURE DESCRIPTION: REWELD ALIGNING DOWEL AND CENTERING PIN BLOCK 900517136 1 CABLE SEPARATION FAILURE DESCRIPTION: CORRECT CABLE SEPARATION CRITERIA VIOLATIONS 900521058 1 1RC41 REACTOR HEAD VENT SOLENOID FAILURE DESCRIPTION: VALVE DOES NOT OPEN - INVESTIGATE 900521068 1 1RC43 REACTOR HEAD VENT FAILURE DESCRIPTION: VALVE DOES NOT OPEN - INVESTIGATE 900527061 1 12CV19 FAILURE DESCRIPTION: NO OPEN OR CLOSE INDICATION - TROUBLESHOOT AND REPAIR

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - MAY 1990 UNIT NAME: SALEM 1 DATE: JUNE 10, 1990 COMPLETED BY: M. MORRONI

                                      'TELEPHONE:   (609) 339-2068
   *DCR          PRINCIPAL SYSTEM           DESCRIPTION lSC-2233       Main Transformer This design change replaced the Main Generator Transformer Phases "A",
                                  "B", and "C" with transformers obtained from the Washington Public Power Supply System.
  *DCR - Design Change Request

MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 MONTH: - MAY 1990 UNIT NAME: SALEM 1 DATE: JUNE 10, 1990 COMPLETED BY: 11. MORRONI TELEPHONE: (609) 339-2068

   *DCR          SAFETY EVALUATION 10 CFR 50.59 lSC-2233       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 GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 MAY 1990 SALEM UNIT NO. 1 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 DOCKET NO: 50-272 MONTH: - MAY 1990 UNIT NAME: SALEH 1 DATE: JUNE 10, 1990 COMPLETED BY: 11. MORRONI TELEPHONE: (609) 339-2068 MONTH MAY 1990

1. Refueling information has changed from last month:

YES x NO

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}}