ML20212E186

Monthly Operating Rept for Jan 1987

ML20212E186
Person / Time
Site:	Rancho Seco
Issue date:	01/31/1987
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-87-142, NUDOCS 8703040288
Download: ML20212E186 (7)

Text

, . . . -- -. ... - . . - . - . , ,

),Hi o, .

S JANUARY 1987 4

s SUNNARY OF PLANT OPERATIONS The plant has been in cold shutdown for the entire month of January.1987. ' 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.

SUNNARY OF CHANGES IN ACCORDANCE WITH 10 CFR PART 50.59 In accordance .with commitments made in the District's response to the Violation in Inspection Report 86-13, the District has i caught-up with the back-log of 50.59 changes that needed to be summarized in our Monthl

completed documentation.y Operating Since the Report response, based the on having has District

. begun to report 50.59 changes which have been accepted by the l plant staff, but are not completely signed off per procedure QCI-

5. This new philosophy causes the District to report significantly older 50.59 ' changes not previously summarized.

4 These older 50.59 changes were not in the backlog population discussed in the response to the violation since the corresponding documentation was not completely signed-off. Now, the District is reporting older 50.59 ~ changes which are between

. acceptance by plant staff and the final signature on the package.

l The' District is currently determining the number of 50.59 changes

.which falls in this in-between category. This new group of older i

50.59 changes will be fully reflected in the Districts Monthly Report by the time the Monthly Report for April 1987 is issued.

4 The plant staff accepted documentation packages for the following i

facility changes in January 1987. These changes were subjected t 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, procedure changes, or

! experiments during January 1987.

I

! 1. When repairs to older Bergen-Patterson manufactured f

I snubber manifold flow control assemblies are required during functional testing of Class 1 piping snubber restraints (earthquake protection), the District instituted a program to replace manifold type snubber I

fluid flow control bodies with new flow control bodies using larger heat treated poppets and related i parts. The old assemblies had broken springs. This

change was lef t in an open status until all snubber flow control bodies were replaced.

ll 8703040288 870131 PDR ADOCK 05000312 l

1

.---,-.-.----_,......___.4. -, ..-._mm .- . ..m -.m-mm .,,. w, .- - ,,.%,.. ,,.,.m.,--,.. m-u.-,,,,,,.--,,,,-y

c_ r. i ' .r 7

._3__

e This program decreases the probability of Class 1 snubber malfunction by improving the reliability of the controlling parts of the snubber manifold. The new flow control body works essentially the same 'way the old one :l did.. None of the Technical' Specification bases-are affected by this program, therefore, no changes to the Technical Specifications were required pursuant to this -

replacement program. (Log Number 219, Revision 0)..

2.- _To provide. greater. assurance that the voltage protection system relay trip ' values to -within the Technical.

Specification. limits, the specification, .for the safety - ,

related 4A,.4B, 4A2 and-~4B2 4160 volt bus under-voltage protection trip relay _ settings, was changed to allow a tolerance of - +0.3V when calibrations' of it are done.

L This change wIll keep the under-voltage ~ relay inverse

time delay. characteristic calibration points from drifting outside the Technical Specification requirements. There are no existing industry standards specifying the tolerance band for the under-voltage

, relays-pick-up voltage settings. Common practice led to the use of 14 of setpoint which was the operational tolerance of the relay. The tolerance band specified by this change was derived using test results which verify

, that the time delay setpoints (which is_ dependent on how close together _the pick-up voltage setpoint is set) are 3 within-the Technical Specification limits.

The under-voltage relay is less likely to malfunction as a result of the closer-tolerances applied to the specifications. The function of the under-voltage relay remained unchanged. Therefore, the margin of safety defined'in the basis of Technical' specifications remains unaffected as a result of  :

this change. (Log Number 678, Revision 1).

MAJOR ITEMS OF SAFETY RELAT'.D MAINTENANCE

1. Mechanical insta . tion of the upper and middle pressurizer heater bundles was completed by the District during January 1987.

2. Emergency Feedwater Initiation and Control level L taps on the once-Through steam Generators were completed.

l The installation of the new EFIC HISSE Control Room Panel

began.

l

3. A successful run of the rebuilt Make-up Pump was performed this month.

4. Preparations are underway for installation of the new I turbine bypass-valves. The new Limitorque operators were moved to the fabrication shop for check-out.

5. The "No-Load" mechanical run of the new "A" TDI Diesel L Generator was run at the end of the month.

I i

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 .o .

AVERAGE DAILY UNIT POWER LEVEL-00CKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 1/31/87 COMPLETED BY- R. Colombo TELEPHONE (916) 452-3211' MONTH January 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' O 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.

g'a i

,,J a.f' *~

. . +

OPERATING DATA REPORT DOCKET NO. 50-312 DATE 1/31/87 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes

2. - Reporting Period: January 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 744 744 103.369

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) -3.660 -3.660 38.285.125

19. Unit' Service Factor 0.0% 0.0% 48.7%

- 20. . Unit Availability Factor 0.0% 0.0% 49.9%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 42.4%

22. Unit Capacity Factor (Using DER Net) 0.0% 0.0% 40.3%

23. Unit Forced Outage Rate 100.0% 100.0% 37.9%

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

_ .o

• ~ .w.

DOCKET NO. 50-312 I' NIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME - Rancho Seco Unit l- ,

' DATE 0 1/.31/ 6 / _y K. Colombo REPORT MONTH January 1987 COMPLETED BY TELEPHONE (916) 452-3211 ,

e

. "E -

1,

=

2_

i 8

3 no m 7 .s X Licensee 53, 5*

c ., Cause & Corrective

%. Date g 3g g ,3 g g Event :s ? E.3 Action to t$ E 5 jiy Report # tE 0 0 Prevent Recurrence 6

1 85/12/26 F 744 D 3 85-25 CB Instru Rx trip fol'owing loss of ICS powerr i 2 3 4 T' 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) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I Same Source s'*i77 ) IIOther (Explain)

m

• 0

$)SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RWC 87-142 February 17, 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 Enclosed is the January 1987 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)

MIPC (2)

INPO m

M b p 5 E -Si B 2 m ' I5 181 Q

cn C) 0 k

[$ ' b RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Hoad, Herald, CA 95638-9799,(209) 333 2935