ML20209C118

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Monthly Operating Rept for Mar 1987
ML20209C118
Person / Time
Site: Rancho Seco
Issue date: 03/31/1987
From: Colombo R
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-87-292, NUDOCS 8704280591
Download: ML20209C118 (9)
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  • MARCH 1987 j

SUMMARY

OF PLANT OPERATIONS I The plant has been in cold shutdown for the entire month of March 1987. The initial shutdown was due to the December 26, 1985, loss of Integrated Control System power event. PERSONNEL CHANGES REQUIRING REPORT 

;                     There were no changes in personnel which require reporting pursuant to Technical Specification Figure 6.2-2.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR PART 50.59 i l The plant staff accepted documentation packages for the following facility changes in March 1987 that are described below. These changes were approved and reviewed by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC). There were no documentation packages completed for tests, procedure changes, or experiments during March 1987.

1. ECN A-5754, Revision 1, upgraded to seismic category 1 (new classification 21N3) the spent fuel cooling j system line 27020-8"-HD from the spent fuel cooler,
E-270, to the spent fuel storage pool, including all j

branch lines up to and including the first isolation j valve. All equipment and/or devices mounted on the line i j were also upgraded to seismic category 1, as necessary. ' ! This change addresses an NRC-identified concern raised I 

)                                  during the spent fuel storage expansion submittal.                                                        )

! Previously, the spent fuel pool cooling system, being i ! seismic category II, was assumed to fail during an j operating or design basis earthquake, after which it would be thereafter incapable of removing decay heat from the pool. (Log No. 653, Revision 0) . f i i 1 'l l . 8704280591 870331 d 4 i PDR R ADOCK 05000312 PDR yy ) i l 1 _ _ . _ _ _ ___ _ _ _ _ . _ J

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2. The plant accepted a portion of ECN A-3646 covering the j
fire protection system for the Interim Onsite Storage ,

{ Building (IOSB) . l 1 l The IOSB is of non-combustible construction and also has l a fire protection system that is designed to be i expandable to accommodate increased facility sizing for up to ten years' waste accumulation. l The fire protection system is designed in accordance with l appropriate National Fire Protection Association (NFPA) National Fire Codes, the Uniform Building Code and with fire insurance underwriter recommendations. This system ! provides fire detection, audible and visual alarms, fire 1 extinguishing systems incorporating both automatic and manual features, and controls the spread of the fire. Upon fire suppression systems actuation, fixed fire , extinguishing systems will automatically actuate in ! appropriate areas of the facility. Concurrently, audible j and visual alarms will be activated locally, in the j facility control room and in the main plant control room. In addition, a variety of manually-operable fire ! extinguishing equipment will be available for manual 4 control and extinguishing fires involving various classes l of hazard. 1 In addition to the sprinkler system and its associated I alarms and control room annuncations, there are manual l pull box-type fire alarms on each floor of the facility and local and remote alarm bells. Flashing red alarm j lights and buzzer units are provided to give audible and i visual signals at the facility control room. The system is designed in accordance with NFPA 72D, " Proprietary

Protective Signaling Systems."

1 i Ionization-type smoke detectors are provided throughout the facility to automatically detect fires in the , incipient stage. Detectors are located in the Service j Head, Truck Bay, Cell Storage Area, Dry Active Waste Handling Area and Dry Active Waste Storage Area. Smoke detectors are also located in the facility HVAC system (as required). Activation of any ' smoke detector will be indicated visually and i audibly at the fire protection control panel in l' the facility control room and remotely in the plant control room, and will shut off the HVAC supply and exhaust fans in the appropriate zone. This will effectively isolate the building. i _- ~ . _ _

t . Located in the facility control room, the fire annunciator panel monitors the power supply and provides all control and supervisory functions required for.the sprinkler, standpipe .and hose, and fire alarm and detection systems. A common fire or trouble signal will 4 be transmitted to the main plant control room from the annunciator panel. The annunciator panel is provided with a battery backup, should the normal 120-volt AC power be interrupted. (Log No. 263, Revision 2, Partial). MAJOR ITEMS OF SAFETY-REIATED MAINTENANCE

1. The reactor coolant system was filled and vented in preparation for the decay heat outage. As part of the filling and venting process, a bubble was drawn in the pressurizer, and leak testing was completed..

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2. The Decay Heat Temperature Rise Measurement test was i completed in March 1987.

I 3. ECN R-1328, Revision 1, was completed. It added a radiation shield for Post-Accident Sampling System liquid sample line radiation monitor. i l 4. ECN R-1461 was performed on the Make-Up Pump wear rings. It documents the condition of the wear rings following

the repair directed by the disposition of NCR S-5697.

The NCR required that the wear ring grooves be machined 

;                                                to be oversized. Subsequently, the oversized machined
wear rings, were installed with others that have overs th agg9{gedoutsiaediameters. This change affectg the 8 3 stage suction (eye) wear rings and the 7 and 4 8 stage back (hub) wear rings.

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5. ECN Re0426 was performed on condensate pump (P-351B) to
provide proper venting from the pump case through the balance sleeve to the pump suction, or atmosphere.

I 4 i i 

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REFUELING INFORMATION REQUEST 

       .l . Name of Facility             Rancho Seco Unit 1
2. Scheduled date for next refueling shutdown: September 15. 1988
3. Scheduled date for restart following refueling: January 15. 1989
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: March 15.1988
     .4. Important licensing considerations associated with refueling:         N/A
7. Number of fuel assemblies:

a) In the core: 177 b) In the Spent Fuel Pool: 31 6

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 T

AVERAGE DAILY UNIT POWER LEVEL 

    ~

DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 3/31/87 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH March 1987 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 , O 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 DATE 3/31/87 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes
2. Reporting Period: March 1987
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 Report, 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 This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 744 2.160 104.785
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 Thermal 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) -4.423 -11.265 38.277.520
19. Unit Service Factor 0.0% 0.0% 48.1%
20. Unit Availability Factor 0.0% 0.0% 49.2%
21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 41.8%
22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 39.8%
23. Unit Forced Outage Rate 100.0% 100.0% 38.9%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

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 l

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i 50-312 '.. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. . UNIT NAME MANLHU btLU 

                                                                 <                                                                         DATE                                 March 31 1987                -

COMPLETED BY R. Colombo REPORT MONTH MARCH 1987 (916) 457 3711 TELEPHONE e. 

                                                              =                                         c jg        3j    j .Y h            Licensee            ,E g      je,                       Cause & Corrective Ni.             Date      g       3g              jj$                Event             g?         g3                            Action to H

f~ $ j ;f3 g Report # mu g U Prevent Recurrence 3 11 85/12/26 F 744 D 3 85-25 CB Instru Reactor trip on high pressure preceded by a loss of ICS power. i 1 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram- Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I- Same Source 19/77) _ ll-Other (Explain)

,4 - ISMU= RECElVED SACRAMENTO MUNICIPAL U*lLITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-183b, 16) 452-3211 AN ELECTRIC SYSTEM SERVING -{g gR OF A IF NIA RWC 87-292 10,y y April 15, 1987 J B MARTIN REGIONAL ADMINISTRATOR REGION V OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUT CREEK, CA 94596 OPERATING PLANT STATUS REPORT DOCKET NO. 50-312

Dear Mr. Martin:

Enclosed is the March 1987 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station. The District submits this report pursuant to Technical Specification 6.9.3. R. W. COLOMBO REGULATORY COMPLIANCE SUPERINTENDENT Encl (5) cc: I&E Wash (12) MIPC (2) INPO 

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                                                                                                            ~E RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935

OPLRAllNG PLANI SIAIUS RLPUR1 bc: General Manager MS 41 ( Deputy General Manager MS 209 Manager, Nuc lear Plant MS 254 Manager, Nuc lear 1 raining MS 296 Manager, Nuclear Licensing MS 286 Manager, Nuclear Engineering MS 208-6 Executive Assistan't MS 213 Public Information MS 204 Quality Assurance MS 271 Manager Maintenance MS 2S4 Reg. Compl. Superintendent MS 286 LRS Consultant (C. Andognini) MS 41 Pubite Affairs (J. Marx) MS 20

f. Burke (B&W) l'ourth floor Files MS 43 ,

Licensing files (3) MS 286 / RIC files MS 224 / 

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