ML20212Q908

Monthly Operating Rept for Dec 1986

ML20212Q908
Person / Time
Site:	Rancho Seco
Issue date:	12/31/1986
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-87-27, NUDOCS 8702020412
Download: ML20212Q908 (8)

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DECEMBER 1986

SUMMARY

OF PLANT OPERATIONS The plant has been in cold shutdown for the entire month of December 1986. The initial shutdown was due to the December 26, 1985 loss of ICS 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 The final documentation packages for the following facility change and procedure change were completed in December 1986.

These changes were 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 tests or experiments during December 1986.

1. Remote control high point vents on each Reactor Coolant System (RCS) Hot Leg and on the Pressurizer were

, installed. This change provides the capability of i venting the RCS form the Control Room. This change addresses the general requirements of NUREG-0737, Item II.B.1, Reactor Coolant System Vents.

The RCS vent system (i.e., vent valves, position indication devices, cable terminations, panel housing, I

controls and indications) are seismically and environmentally qualified in accordance with IEEE 344-1975 and IEEE 323-1974 respectively as supplemented by l

Regulatory Guide 1.100, 1.92 and SEP 3.92, 3.4 3. and 3.10.

The vent lines and components are qualified seismic Class 1, and as Quality Group A of Nuclear Regulatory Guide 1.26. The vent line segment downstream of the second closed solenoid valve will be designated non-seismic Class 1, Quality Group D. This segment includes one side of the flange and the sparger for each line.

Each vent line is provided with a piezoelectric accelerometer which will alarm to the computer for any flow in the line.

8702020412 861231  % /

PDR ADOCK 05000312 R PDR ///

All remote operated valves are the fail close type, with power required to open and power required to maintain open. The solenoid valves have proven fail closed action on loss of power. No packings are permissible.

For any vont assembly, two valves in series with

! individual controls will prevent the possibility of the system failing to isolate, subsequent to the failure of any single control function.

The flow limiting orifice in each RCS vent line ensures that a break ih the added RCS vent piping will not lead to an increase in the probability of a loss-of-coolant beyond the capability of the Make-up Pump to maintain l inventory in the RCS. (Log Number 211, Revision 0).

2. Operating Procedure B.2A, " Plant Operation in Cold Shutdown with Both DHS Trains Not Operable," provides major operator guidance for preparing the plant and maintaining cold shutdown, using the once-Through steam Generators (OTSG's) for RCS heat removal, while neither DHS Train is operable.

The preparation of B.2A is necessary to provide a normal operating procedure for the planned evolution for removing both decay heat loops from service for maintenance and repairs.

Casualty Procedure C.12, Revision 3, " Loss of Decay Heat Removal System," is revised to provide additional l operator guidance upon the loss of operability of l both decay heat loops, with the RCS filled and ,

vented. -

The revision to C.12 is an enhancement which provides more detailed guidance for maintaining decay heat removal using the OTSG's in the casualty event of loss of both decay heat loops with the RCS filled and vented.

With forced flow a single steam generator can maintain RCS temperatures below 220 F. No Licensing Condition has been identified that prohibits leaving Cold Shutdown, including the NRC December 26, 1985 Confirmatory Action Letter.

Neither of the subject procedure actions requires a change or addition to Technical Specifications.

An RCS LOCA is not a required assumption. High energy line breaks are not considered for lines which do not exceed 200 F and 275 psig (USAR Section 4.1.2.3). In the unlikely event that RCS inventory is lost, or that multiple failures of the steam generator decay heat removal capability occur, alternate methods of removing decay heat are available.

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. . T These procedure actions will not result in system operation in any way that may increase the probability or consequences of any accident previously analyzed or that may result in an accident of a different type. The .

margin of safety as defined in the basis of Technical Specifications is maintained. Therefore, these procedure changes do not involve an unreviewed safety question.

(Iog Number 615, Revision 0). ,

MAJOR ITEMS OF SAFETY REIATED MAINTENANCE a

1. A replacement middle pressurizer heater bundle was received by the District on December 31, 1986. The upper replacement heater bundle was seal welded into place. (

2. Installation of tubing, conduit, cable and terminations continued during the month.

Modification work for replacement of the Auxiliary Feedwater Control valves is in progress.

3. The refurbishment of 173 motor operated valves is in progress. (

4. General Electric is inspecting both of the Trans America '

Delaval (TDI) Diesel Generators.

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l REFUELING INFORMATION REQUEST ,

1. Name of Facility Rancho Seco Unit 1

2. Scheduled date for next refueling shutdown: 09/15/88

3. Scheduled date for restart following refueling: 01/15/89

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: 03/15/88

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

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 to the Spent Fuel Pool: 12/03/2001 e

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 12/31/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH December 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 NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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I OPERATING DATA REPORT DOCKET NO. 50-312 DATE 12/31/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes

2. Reporting Period: December 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 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 8.760 102.625

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) -3.551 -41.317 38.288.785

19. Unit Service Factor 0.0% 0.0% 49.1%

20. Unit Availability Factor 0.0% 0.0% 50.3%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 42.7%

22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 40.6%

23. Unit Forced Outage Rate 100.0% 100.0% 37.3%

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: I.1 definite

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 UNIT NAME Ranchn Rocn '

DATE 12/31/ 2 COMPLETED BY R. Colonsbo REPORT MONTH Decembor 1986 TELEPHONE ('316) 452-3211 ,

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_5 ? 3 .} .E 3 Licensee ,E g ja. Cause & Corrective w Date g g 4 .g g 5 Event gg o.3 Action to H

$- 5 e t jj g c Report a mO !O o

Prevent Recurrence g

Q 1 85-12-26 F 744 A 3 85-25 CB Inst.ru Rx trip following loss of ICS power l

3 4 1 2 Method: Exhibit G - Instructions F Forced Reason:

for Preparation of Data 5 Scheduled A. Equipment Failure (Explain) 1-Manual 2 Manual Scrarn. Entry Sheets for Licensee l B. Maintenance of Test Event Report (LER) File (NUREG-i C Refueling 3 Automatic Scram.

D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination 5

F-Administ rative G-Operational Error (Explain) Exhibit I - Same Source to/77) II-Other (Explain)

esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street. P.O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RWC 87-27 4

January 15, 198%

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 Enclosed is the December 1986 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station pursuant to Technical Specification 6.9.3.

R. W. COLOMBO REGULATORY COMPLIANCE SUPERINTENDENT Encl (5) cc: I&E Wash (12)

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