NL-89-556, Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station

Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station

ML20246P874
Person / Time
Site:	Rancho Seco
Issue date:	06/30/1989
From:	Crunk S, Mueller M SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NL-89-556, NUDOCS 8907200343
Download: ML20246P874 (7)

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JOsuun~ SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830, Sacramento CA 95832-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA NL 89-556

' July 18, 1989 l

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station Licente No. DPR-54 OPERAJING PLANT STATUS REPORT Attention: George Knighton Enclosed is the June 1989 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station. The District submits this report pursuant to Technic ' . Specification 6.9.3.

Rancho Seco was shut down June 7 following the negative outcome of the public vote regarding continued operation of the plant by Sacramento Mu"*cipal Utility District. The District has no plans to restart the plant; however, deliberations regarding the sale of the plant are under way.

Sincerely,

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L y - v-Steve t . Crunk Matt ger Nuclear Licensing Enc 1 (5) cc: J. B. Hartin, NRC, Walnut Creek A. D'Angelo, NRC, Rancho Seco INP0 R. Twilley, Jr.

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RANCHO SECO NUCLEAR GENERATING STATION D 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935

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JUNE 1989 i

SUMMARY

OF PLANT OPERATIONS Rancho Seco' operated'at approximately 60% power until it was shut down on LJune 7 following the negative outcome of the public vote on continued operation of the plant by SMUD. Reactor shutdown started at 0842 hours0.00975 days <br />0.234 hours <br />0.00139 weeks <br />3.20381e-4 months <br />, the generator taken off-line at l' 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, hot standby reached at 1139 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.333895e-4 months <br />, and hot shutdown at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />. Cc s shutdown ~was reached at 1843 on June 9. The plant remains in cold shutdown.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 The pmot staff accepted documentation packages in June 1989 for the facility changes, procedure changes and tests described below which required detailed safety analysis. These changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).

1. DCP R89-0012 replaced carbon steel valve FHS-542 with a stainless steel valve and restored the valve to service per original design. This modification did not increasti the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor was the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created. This modification did not involve an Unreviewed Safety Question.

2. DCP R88-0108 installed a card reader. controlled door (with required electrical UPS power and control' wiring) in the +40 foot elevation level adjacent to the spent fuel entry door. This modification added a new vital area security controlled door and has no impact to Class 1 or 2 safety equipment. This modification did not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor was the possibility for an accident or malfunction of a different type than any

.. valuated previously in the USAR created. An Unreviewed Safety Question was not involved.

3. Procedure RT-IAS-005, Quarterly Verification of C-900D Auto-Starts, was revised to bring the unit to sta ld-by status following the test. The air compressor is not safety related and does not interface with safety related components during the performance of this routine test. This procedure change does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created. This procedure change does not involve an Unreviewed Safety Question.

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'. MAJOR SAFETY-RELATED MAINTENANCE, TESTS AND MODIFICATIONS NOT REQUIRING-DETAILED SAFETY ANALYSES 1

1. During June 1989, maintenance was. performed on the "A" and "B" TDI diesel ,

generators,.two control modules for the "A" feedwater pump, the Nuclear i Service Water System, make-up pump, "B" decay heat pump, and "B" Bruce-GM diesel' generator. -The steam generators and main steam lines were filled swith chemically-treated water.to prevent corrosion. Nitrogen was added to prevent corrosion in' secondary system components not previously filled

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1 with chemically treated water. Condenser vacuum was broken and the-condensate system was ' shut down. Modifications and maintenance of the l fuel handling system were performed. l

2. ECN A-3753, Revision 1, provided a chemical addition system to the auxiliary boiler. This system.was added because of the inadequacy of the main feedwater chemistry control for the auxiliary boiler feedwater.

3. DCP R88-0068 modified pipe supports on the line from the "B" m'isture separator reheateriextraction steam coil vent condenser drain to the feedwater heaters to reduce vibration levels on the lire and-to enhance system reliability. j

4. DCP R88-0069AA c4ded vibration restraints to two Decay Heat System lines to reduce vibration levels on the line and to enhance system reliability.

.5. DCP R88-0121 modified mcnitoring panels' H4PBA and H4PBB to provide room and visibility of the calibration pots so that electricians are not exposed to electric shock hazard during routine calibration of those panels.

6. ECN A-5001A, Revision 1,~ relocated the Stock Equipment Co. compactor and removed its concrete pad to so that the room can be used to process low level radioactive waste.

7. ECN A-5001B, Revision 0, removed the Consolidated Baling Macnine compactor, Cynaloc tank, associated equipment and concrete pads from the radwaste compacting room so that the room can be used to process low level radioactive waste.

8. DCP R88-0114AA provided connections in the Auxiliary Steam System, Diesel fuel Oil System and Haste Water Disposal System to permit installation of a temporary truck-mounted steam boiler while the plant is operating.

These connections permit rapid installation of a 60,000 lb/hr truck-mounted boiler in the event of a failure of an existing boiler.

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--REFUELfNG INFORMATION REQUEST. 1 W ,

41.. Name'of Facility' Rancho Seco- _

l "2. Scheduled date' for next refueling shutdown:

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3. Scheduled ~date,for restart following': refueling: *

4. Technical Specification change or. other ' license.amentiment. required:  ;

.5; Scheduled-date(s)'for submitting proposed licensing action: _

6. 1mportant-licensing considerations associated with refueling:

-7. -Number of fuel assemblies:

, a)- In the core: 177 b) In the Spent: Fuel? Pool: 316

' : 8. Present licensed spent fuel capacity: 1080

9. Projected 'date of the last refueling that can be discharged te the. Spent' Fuel Pool: December 3. 2001

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i c' Plant shut down June 7 following negative outcome of public vote regarding continued operation of Rancho Seco by SMUD.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco DATE 6/30/39 COMPLETED BY Maria Mueller TELEPHONE (916) 452-3211 l

" MONTH June 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 501 17 0 2 539 18 0 3 573 19 0 4 575 20 0 i 5 571 21 0 6 564 22 0 7 410 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 1

14 0 30 0 15 0 31 -

16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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• 1 OPERATING DATA REPORT DOCKET NO. '50-312 DATE 6/30/89 g

COMPLETED BY Maria Mueller-TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Notes:

2. Reporting Period: June 1989

3. Licensed Thermal Power (MHt): 2.772

4. Nameplate Rating (Gross MHe): 963

~5. Design Electrical Rating (Net MHe): 918

6. . Maximum Dependable Capacity (Gross.MWe): '917

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Maximum Dependable Capacity (Net MWe); 873

8. If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report,.

Give Reasons: - F/A

9. Power ' ? vel to Which Restricted, If Any (Net MHe):

. N/A 10 Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 4.343 124.511

12. Number of Hours Reactor Has Critical 155.6 ..

2.155.7 62.221 5 .

13. ~ Reactor Reserve Shutdown Hours 564.4 600.4 10.9002 6

14. Hours Generator On-Line 154.7 2.217.6 57.811.1

15. Unit Reserve Shutdown Hours . 565_.J_. 601 3 1.811.5

16. Gross Thermal Energy Generated (MHH) 268.221* 4.623.125* 141.951.953*

17. Gross Electrical Energy Generated (MHH) 90.673 1.575.699 4L_2U.924

18. . Net Electrical Energy Generated (MWH) 77.113 1.439.735' 42.40.618

19. Unit' Scrvice Factor 21.5% 51.1% 46.4%

20. Unit Availability Factor 100.0% 64.9% 47J%

'21. ' Unit: Capacity Factor (Using MDC Net) 12.3% 38.0% 39.11

22. Unit Capacity Factor (Using DER Net) 11.7% 36.1% 37.2%

23. Unit Forced' Outage Rate 0.0% 40.7% 42.7%

24. Shutdowns Scheduled Over Next 6 h0nths (Type Date, and Duration of Each):

25. If Shut Down At End Of Report Period. Estimated Date of Startup: **

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A _N/A COMMERCIAL OPERATION N/A N/A

• Corrections for May 1989: 1,526,259 (Month); 4/354,904 (Year); 141,683,732 (Cumulative)

• • Plant shut down June 7 following negative outcome of public vote regarding

' continued operation of Rancho Seco by SMUD.

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