ML20212P829

Monthly Operating Rept for Jul 1986

ML20212P829
Person / Time
Site:	Rancho Seco
Issue date:	07/31/1986
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-86-445, NUDOCS 8609030302
Download: ML20212P829 (7)

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IULY 1986

SUMMARY

OF PLATT OPERATIOM j I

The plant has been in cold shutdown for the entire month cf July 1955 The initial shutdown l was due to the December 26,1986 loss of ICS power event. '

PERSONNEL CHANGES REQUIRING REPORT Tnere were no changes in personnel which require reporting pursuant to Technical l Specification Figure 6 2 2.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 50 59 The finald_n_cumentation nackage for the following facility change was completed in July 1956.

This change was subjected to the review and approval of the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC). There were no documentation packages completed for procedures, tests, or experiments durin g July 1956.

A safety grade anticipatory trip ( ARTS) was implemented via the Reactor Protection System in accordance with the guidance of NUREG 0737 Section III 2.10 as reported for May 1935 (50.59 Item 15).

The new ARTS allowed the then existing control grade anticipatory (reactor) trip from the shunt trip coi! of Control Rod Drive System breakers A and B to be replaced with the generator-reactor manual trip. Additional wiring. conduit and cable trays were installed in the plant to connect the generator-reactor manual trip. The addition of the generator-reactor uanual trip did not increase the probability of occurrence or the consequences of an accidentor malfunction of equipment important to safety previously evaluated in the USAR or create the possibility for an accident or malfunction of a d.fferent type than any evaluated previously in the USAR or reduce the margir. of safety as defined in the basis for any TechnicalSpecification. The generator-reactor manual trip is not safety grade, nor did it use Class IE equipment. nor was it part of the new ARTS The generator-reactor manual trip was subsequently removed by ECN A-5141in May 19S5 The relay used for the shunt trip coilis now dedicated to an annunciator only (Log "416, Revision 1)

M A 10R ITEMS OF S AFETY RELATED M AINTENANCE 1, Repair efforts on the makeup pump (P-236) continued through the month of July 1956 l 2. The process of performing preventive maintenance on various plant valves continued through the month of July 1955 The District continued data collection on IEB S5-03 MOVs 3 PASS modifications continued through July 1956 4 Reworked cable inside Diesel Generator Pane! H2DGA as prescribed in NCR S-4540 disposition by replacing terminallugs 5 Continued localleak rate testing of reactor building penetrations

5. Cleaaed. inspected, and repaired RPS Channel A. B C. and D Bailey S50 modules per D&W 1etter PSC-10-S2 and MIDR IC-153 ,

7 Continued snubber testin g. PDR 8609030302 860731 ADOCK 05000312

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8, Cleaned the Diesel fuel Oil Storage tant level indicator (LI ss702A>, replace i the indication fluid and returned it to service.

i 1

REFUELING INFORNATION REQUEST

1. Name of Facility Rancho Seco Unit 1

2. Scheduled date for next refueling shutdown: March 1.1988

3. Scheduled date for restart following refueling: July 1. '1988

4. Technical Specification change or other license amendment required:

a) Change to Rod Index vs Power Level Curve (TS 3.5.2) b) Change to Core Imbalance vs Power Level Curve (TS 3.5.2) c) Tilt Limits (TS 3.5.2)

5. Scheduled date(s) for submitting proposed licensing action: September 1.1987

6. important licensing considerations associated with refueling: N/A

7. Naaber 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 to the Spent Fuel Pool: December 3. 2001 s

. AVERAGE DAILY UNIT POW 2R LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 07-31-86 COMPLETED BY R. Colombo TELEPiiONE (916) 452-3211 MONTH July 1986 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 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.

OPERATING DATA REPORT DOCKET NO. 50-312 i

DATE 07/31/86 COMPLETED 8Y R. Colombo TELEPHONE (916) 452-3211 2

OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1

2. Reporting Period: July 1986

3. Licensed Thermal Power (MWt)

2.772

4. Nameplate Rating (Gross MWe): 963

5. Design Electrical Rating (Net MWe): 918

6. Maximum Dependable Capacity (Gross MWe): 917

7. Maximum Dependable Capacity (Net MWe)

873

8. If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Rep;rt, Give Reasons: N/A

9. Power Level to Which Restricted, If Any (Net MWe): 0

10. Reasons For Restrictions, If Any: NRC Letter dated 12/26/85.

i This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 5.087 98.952

, 12. Number of Hours Reactor Was Critical 0 0 54.322

13. Reactor Reserve Shutdown Hours 0 0 10.300.2

14. Hours Generator On-Line 0 0 50.363.8

15. Unit Reserve Shutdown Hours 0 0 1.210.2

16. Gross Thernal Energy Generated (MWH) 0 0 127.861.688

17. Gross Electrical Energy Generated (MWH) 0 0 41.523.187

18. Net Electrical Energy Generated (MWH) -3.010 -23.801 38.306.301 l 19. Unit Service Factor 0.0% 0.0% 50.9%

20. Unit Availability Factor 0.0% 0.0% 52.1%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 44.3%

22. Unit Capacity Factor (Using DER Net) 0.0%__ 0.0% 42.2%

23. Unit Forced Outage Rate 100.0% 100.0% 34.6%

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

N/A 4

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

Indefinite

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

DOCKET NO.

50-312 .

UNIT SHUTDOWNS AND POWER REDUCTIONS MANLHU 5tLO .

UNIT NAME DATE Julv 31. 1986 .

JULY 1986 COMPLETED BY R Colnrnho REPORT MONTH TELEPHONE _ Wlb) 452-3211 4

- E c j? 3ij ,yj Y3 Licensee E*,,

• ,, Cause & Corrective

% .. Date Q yg Event d EO A' '"

• E Report a mO Prevent Recurrence

] $ j f3 g g i 3 1

1 12/26/85 F 744 A 3 85-25 CB INSTRU Redctor trip on high pressure.

) Preceded by total loss of ICS power. Corrective actions being implemented.

i i

i 2 3 4 i

F Forced Reason: Method: Exhibit G - Instructions 1-Manual for Preparation of Data

)

S Scheduled A. Equipment Failure (Explain)

B. Maintenance of Test 2-Manual Scram- Entry Sheets for Licensee

C Refueling 3-Automatic Scram. Event Reporn (LERI File tNUREG-j D Regulatory Restriction 4-Other (Explain) 0161)

) E-Operator Training & Ucense Examination 4 F-Administrative 5 G-Operational Error (Explain) . Exhibit I Same Source l'8/77) Il-Other (E xplain) s

e suu .

SACRAMENTO MUNICIPAL UTluTY DISTRICT O 62o1 S Street, P.O. Box 15830 Sacramento CA 95852-1830.(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RWC S6-445 August 18,19S6 @,

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J B MARTIN REGIONAL ADMINISTRATOR o)

REGION V 0FFICE OF INSPECfl0N AND ENFORCEMENT U S NUCLEuR REGULATORY COMMISSION 1450 MARIA LANE. SUITE 210 WALNUTCREEE.CA 945%

OPERATING PLANT STATUS REPORT DOCEET NO.50-312 Enclosed is the July 1986 Monthly Operating P.! ant Status Report for the Rancho Seco Nuc! car Generating Station pursuant to Technical Specification 6.9.3 R. W. COLOMB0 REGULATORY COMPLIANCE SUPERINTENDENT Enci (5) cc. I&E Wash (12)

MIPC (2)

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