ML20010C183

Monthly Operating Rept for Jul 1981

ML20010C183
Person / Time
Site:	Rancho Seco
Issue date:	07/31/1981
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20010C182	List: ML20010C181 ML20010C183
References
NUDOCS 8108190224
Download: ML20010C183 (9)

Text

T'

SUMMARY

' 0F PLANT OPERATIONS 7-1 0106 Reducing power to 58% @ 50 Mw/ minute 0116 Reactor at 58%

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0117 increasing power to 78%

Feedwater Pump Testing 0133 Reducing power to 58% @ 96 Mw/ minute 0136 Reactor at 59%

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0138 increasing power to 78%

0221 Increasing power to 92%

0521 Reactor at 87%--began 5-hour hold 1506 Increasing power to 100% @ 3% per hour 1933 Reactor at 100% power 7-2 to 7-31 Continuous operation at 100% power. Performed routine surveillance and preventive maintenance.

PERSONNEL CHANGES REQUIRING REPORTlHG No personnel changes that reqei re reporting in accordance with Technical Specifications Figure 6.2-2 were made in June, 1981.

MAJOR ITEMS OF SAFETY-RELATED MAINTENANCE i

1.

Repaired broken positioner feedback arm on turbine bypass valve.

2.

Increased air supply to pressurizer relief tank sampic valve.

3 Cleaned pilot of atmospheric dump valve.

4.

Adjusted packing of isolation valve for atmospheric dump valve.

5 Installed-new casine gasket on boric acid addition pump.

6.

Replaced leaking expansion joint ~ on. emergency diesel generator.

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7. -Added oil to governor of diesel generator.

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8.' Replaced motor operated auto _ voltage control of diesel generator.

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SbHMARY OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59(b) 1.

Provided the operator in the control room with an unambigious indication of valve position (open or closed) for the pressurizer PORV and the two safety code valves so that appropriate operator actions can be taken.

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SUPPLEMENT TO MONTHLY PLANT OPERATIONS REPORT POWER ESCALATION During this past month.the power escalation test program was completed following the OTSG tube leak repair. The test results through the 75% power plateaus were reported in the June Plant 0perations Report.

1.

Core Power Distribution The 100% power core power distribution data was completed on July 3, 1981. The purpose of these measurements was to verify that the minimum DNBR, maximum linear heat rate, quadrant power tile, power imbalance, and related power peaking factors would not exceed allowable limits.

In each case the measured variables were extrap-olated to the over power trip setpoint for the next test plateau so as to assess the margin of conservatism prior to estal. tion. A summary of the test resul'.s fol lows :

Date of Data: July 3, 1981 Measured / Predicted Power level, %FP 99.7/100 Core Burnup, EFPD 14.8/25.0 Group 1-5, %WD 100/100 Group 6, %WD 100/100 Group 7, %WD 89.9/87.1 Group 8, %WD 23.0/22.3 Boron Concentration, ppmB 651/650 Axial imbalance, %FP

-0.98/-0.38 Max. Core Quadrant Power Tilt, %FP 1.55/<3.40 Minimum DNBR

.19/>1.30 Worst Case LHR, Kw/ft 11.21/<20.4 Max. Radial Power Peak 1.279/1.259 Max. Total Power Peak 1.475/1.473 j

Max. Peak at Core Grid K-12/K-12 Max. Peak in Fuel Batch Number 7/7

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Equilibrium Xenon Yes Ext rapolat ions done to, %FP 112 Ext rapolat ion acceptable.

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POWER ESCALATION SUPPLEMENT (Continued)

.2 Temperature / Moderator Coef ficient Measurement at 1007 Power A verification is performed that the moderator coefficient, at 100% power, is less than zero. The measured value was

-0.93 x 10-4 Ak/k/F at a boron concentration of 651 ppmB.

The vendor prediction was -1.68 x 10-4 Ak/k/F.

No deviation criteria is associated with this measurement.

3 Power Coefficient Measurement at 100% Power The power coef ficient measurement demonstrated that the power coefficient was -0.79 x 10-4 Ak/k/%FP. The acceptance cri teria for this measurement is that the coefficient be less than

-0.55 x 10 '+ Ak/k/%FP.

.4 Summary / Conclusions of Cycle 5 Zero Power and Power Esce!ation Testing All measurements made in this test progran were found to meet their acceptance criteria, f..

f SUPPLEMF.NT TO l10NTHLY PLANT OPERATIONS REPORT EDDY CURRENT INSPECTION OF OTSG TUBES - 1981 REFUELING OUTAGE DESCRIPTION A-0TSG B-0TSG Number of Tubes Inspected 929 (6%)

None Number of Tubes Plugged None None Location of Tubes Plugged Locations of I ndi cations 320%, <40%

75-7:

30 - 35% OD Wear / Thinning @ 15th TSP 95-113:

20 - 25% OD Between 15th TSP and UTS 141-10:

20% OD Between 10th and lith TSP Gene ral :

The tubes were examined full-length at 400 KHZ. The sample included 100%

of tubes adjacent to the open lane, 50% of tubes in rows one row away, an d 25% of tubes in rows two rows away f rom the open lane.

"he sample was weighted by selecting peripheral tubes (outboard 20) vs. interior tubes by an approximate ratio of 3 to 1.

f OPERATING DATA REPORT DOCKET NO. Gn-at?

DATE 81-07-11 COMPLETED BY R. W. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS Notes

1. Urdt Name:

Rancho Seco Unit 1

2. Reporting Period:

Ju1v. 1081

3. Licensed Thermal Power (MWt):

7777

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 Whi:h Restricted,if Any (Net MWe):

N/A 10.' Reasons For Restrictions,If Any:

N/A This Month Yr..to-Date Cumulative

11. Hours In Reporting Period 744 G.087 55.128

12. Number Of Hours Reactor Was Critical 744 2,064.1 33,560.3

13. Reactor Reserve Shutdown Hours 0

0 4.469.6

14. Hours Generator On.Line 744 1.976.2 32.221.8

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15. Unit Reserve Shutdown Hours 0

0 1.210.2

16. Gross Thermal Energy Generated (MWil) 2.053.175 4.981.392 81.953.647

17. Gross Electrical Energy Generated (MWHj G44 164 1 G10 414 77 478.244

18. Net Electrical Energy Generated (MWH) 565.906 1.431.231 25.957.356

19. Unit Service Factor 100 18.8 98.4

20. Unit Availability Factor 100 38.8 60.6

21. Unit Capacity Factor (Using MDC Net) 87.1 32.2 53.9

22. Unit Capacity Factor (Using DER Net) 82.9 30.6 51.3

23. Unit Forced Outage Rate 0

27.1 28.9

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

N/A

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

N/A

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIA L CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPER ATION N/A N/A (0/77 )

f AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 81-7-31 COMPLETED By R. W. Colombo TELEPHONE (916) 452-321,1 July, 198 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) iMWe-Net) 716 g7 791 2

776 is 788 3

775 39 783 4

777 20 783 5

780 21 781 6

770 22 785 7

785 23

'786 8

783 24 782 9

783 25 785 10 786 26 787 789 27 787 12 790 2g 783 13 785 29 785 34 781 788 30 15 781 31 789 16 788 INSTR'JCTIONS On this format.hst t' e aserage daily unit power lesel m MWe Net for each day in the reportmg month. Compute to the nearest whole meganait.

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-312 UNIT N A'.!E Rancho Seco Un,it 1 DNIE 81-07 '4f REPORT MONTig July, 1981 COMPI ET ED itY R. W_

rninmhn TEll:!'llONE (916) 452-3211 1

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Date g-3g y

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Action to H

$5 jd Report #

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Prevent Recurrence o

NO OUTAGES OR SIGNIFICNir POWER REDUCTION (GREATER WAN 20% REDUCTION IN AVERAGE DAILY PONER LEVEL FOR Tile PRECEDING 21! HOURS) BIS IONE.

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4 F: Forced Itcauni:

Melluxt:

Exhibit G Instructions S: Scheduled A 1ilu;pment Failure (Explain) l-Manual for Picpar.ition of Data 11 M.'intenans e of Test 2-Manual Scram.

lintey Sheets for I.icentre C-1:rtneling 3-Automatic Sciam.

Event Report (LliR) File (NUREG-l). Iter.nl:itniy Itcstriction 4-Other (Explain) 0161) l E-()peralos Ti.iining & t.icense Examination i

F A.iministrative 5

G Operational lirror (Explain)

Exhibit I - Same Source (9/77)

Il-Other (Explain) l

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REFUELING INFORMATION REQUEST 1.

'Name of Facility:

Rancho Seco Unit 1 2.

Scheduled date for next refueling shutdown:

April. 1982 3.

Scheduled date for restart following refueling:

October, 1982 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:

Februarv 14R?

6.

Important licensing considerations associated with refueling:

None 7.

Number of fuel assemblies:

a) In the core:

177 b)

In the Spent Fuel Pool:

196 8.

Present licensed spent fuel capacity:

579 9.

Projected date of the last refueling that can be discharged to the Spent Fuel Poo'l:

1987

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