ML19305E769

Monthly Operating Rept for Apr 1980

ML19305E769
Person / Time
Site:	Millstone
Issue date:	05/04/1980
From:	Harran G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19305E767	List: ML19305E766 ML19305E769
References
NUDOCS 8005200389
Download: ML19305E769 (6)

Text

8005200 M]

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-245 UNIT Millstone - 1 I

DATE 800404 G. Harran COMPLETED BY TELEPHONE 203/447-1792 ext. 655 MONnt Aoril DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 647 1

656 37 2

653 18 647 653 3

19 647 652 647 4

20 5

651 21 645 603 634 6

22 655 468 7

3 8

24 653 655 9

657 25 656 655 10 26 656 I1 27 655 12 655 654 28 655 13 gg3 655 14 30 649 15 33 643 16 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

Note: MDC of 654 MWE - Net based on conmitment to New England Power Exchange.

(9/77)

.n

i OPERATING DATA REPORT

~

DOCKET NO.

50-245 DATE 800404 COMPLETED BY G. Harran i

TELEPHONE 203/447-1792 OPERATING STATUS

1. Unit Name:

Millstone Unit 1 Notes March 1980

2. Reporting Period:

3. Licensed Thermal Power (MWt):

2011

4. Namtplate Rating (Gross MWe):

662

5. Design Electrical Rating (Net MWe): 660 684

6. Maximum Dependable Capacity (Gross MWe):

7. Sf aximum l>ependable Capacity (Net MWe):

654

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A j

N/A

9. Power Level To Which Restricted.If An (Net MWe):

N/A NA

10. Reasons For Restrictions.If Any:

This Month Yr to.Date Cumulative 719 2903.0 82583.0

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 719 2903.0 63288.0

13. Reactor Reserve Shutdown Hours 0

0 935.0 719 2903.0 60998.9

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0

0 0.0

16. Gross Thermal Energy Generated I.MWH) 1,413,400 4.677.RM 108,725,528

17. Gross Electrical Energy Generated (MWH) 484,000 1.583.300 36,814,696

18. Net Electrical Energy Generated (MWH) 463,061 1,511,437

1. >l31.219

19. Unit Service Factor 100 100 73.9

20. Unit Availability Factor 100 100 73.9

21. Unit Capacity Factor (Using MDC Net) 98.5 79.6 65.1

22. Unit Capacity Factor (Using DER Net) 97.6 78.9 04.3

23. Unit Forced Outage Rate 0

0 16.0

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

Annual refuel and maintenance autaan <chedulpd to Comm E Q_SEDtember 19. 1980 _

for accroximately 8 - 10 weeks.

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

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

Forecast Achiesed INITIA L CRITICALITY l

INITIAL ELECTRICITY N/A COMMERCIA L OPERATION i

l (9[771

.=

OPERATING HISTORY April 1,1980 Steady state, reactor power 100%.

April 6, 1980 0001 Hours Dacreasing reactor power for recirc. motor generator

'A' rebrushing, and turbine stop valve testing.

0120 Hours Reactor power at 50%.

0200 Hours Turbine stop valve testing complete. Commenced increasing reactor power.

0245 Hours Recirc. motor generator 'A' rebrushing and condenser backwash complete. Commenced increasing reactor power.

1230 Hours Reactor power at 100%.

April 16,1980 0025 Hours Reducing reactor power for turbine stop valve testing.

0110 Hours Turbine stop valve testing complete, commenced condenser backwash.

0200 Hours Condenser backwash complete.

Increasing reactor power.

0240 Hours Reactor power at 100%.

April 22, 1980 2203 Hours Reducing reactor power to 85%

for control rod pattern adjust-ment, turbine stop valve testing, and condenser backwash.

2310 Hours Turbine stop valve testing and condenser backwashing complete.

2330 Hours Decreasing reactor power to 45%

because of high condenser con-ductivity.

April 23, 1980 0055 Hours Reactor power at 45%.

0815 Hours Increasing reactor power after condenser repairs and control l

rod pattern adjustment.

0230 Hours Reactor power at 100%.

l l

Docket No.

50-245 Page of Date 800305 Unit Name Millstone Unit 1 Completed By _G. Harran Telephone 203/447-1792 ext. 655-CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month April DATE SYSTEM COMPONENT MAINTENANCE ACTION 800104 Control Rod Drive Cr.D 14-15, Accumulator Removed Accumulator (2782) and installed a new one because of leakage by the piston.

802304 Control Rod Drive Accumulator, SER #2782 Worn 'O' rings. Removed, rebuilt and re-installed Accumulator.

4 1

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-245

)

UNIT NAME MilIstone -1 DATE R00404 REPORT MONT11 APfl)

COMPLETED BY G. Harran TELEPIIONE 203/447-1792 ext. 655 EO "E

Licensee Ev Cause & Corrective No.

Date h

j!

3$

Event (i

Action to yI j@

Report a mV Pievent Recu rence H

g O

02 800423 F

0 A

4 fi/A llB PIPEXX Unit power was reduced to plug leaking Main Condenser tubes.

!l Unit power was increased after leaking tubes were. plugged.

t t

i

,s

' i l

l

' I l

i 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instruction's i

S: Scheduled A E,Wpment 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 Repor (LER) File (NUREG-D Regulatory R:striction 4 Other (Explain) 0161) li-Ope ator Training & license Examination F-Administ rative 5

G Operational I?sior (lixplain).

Exhibit I Same Sourec (9/77) 11 Othe: (Explain)

REFUELING INFOR!tATION REQUEST 1.

Name of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

Fall 1980 3.

Scheduled date for restart foll,owing refueling:

Late Fall 1980 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes. Technical Specification changes reg'arding:

(1) Maximum Averace Planar Linear Heat Generatino Rate (2) Maximum Critical Power Ratio 5.

Scheduled date(s) for submitting proposed ifcensing action and supporting information :

Summer 1980 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

16R " Retrofit" 8 X 8 fuel assemblies are scheduled for insertion in cycle 8 (reload 7).

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool :

(a) In Core:

580 (b) In SFP:

776 8.

The present licensed spent fuel pool storage capacity and the size of any in-crease in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

21Ra assemblibs 1

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1985, Spent Fuel Pool, full core off load capability is reached.

1991, Core Full, Spent Fuel Pool contains 2120 bundles.

RHY:rmj

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