Text

Monthly Operating Rept for May 1980
	ML19323H993
Person / Time
Site:	Millstone
Issue date:	06/05/1980
From:	Harran G; NORTHEAST UTILITIES
To:	;
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ML19323H992	List: ML19323H991; ML19323H993;
References
	NUDOCS 8006170440
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AVERAGE DAILY UNIT POWER LEVEL I

DOCKET NO.

50-245 UNIT - Millstone-1 800505 DATE arran COMPLETED BY s

TELEPHONE 203/447-1792 ext. 655

.!ONTH May DAY AVERAGE ILY P WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

I 654 17 645 653 2

is 643 652 644 3

9 4

650 20 604 5

652 560 21 626 486 6

22 7

601 486 3

8 328 485 24 9

575 482 25 10 643 26 483 648 482 27 12 6d4 482 28 13 649 29 645 14 30 444 648 15 1

' 16 647

+

INSTRUCTIONS On this format, list the averege daily unit power level in MWe. Net for en day in the reporting month. Compute to the nearest whole megawatt.

NOTE: MDC of 654 MWE - Net based on commitment to New England Power Exchange.

(9/77) l S006176440

OPERATING DATA REPORT

~

DOCKET NO.

50-245 DATE 800505 COMPLETED BY G. Harran TELEWONE 203-447-1792 ext. 655 i

OPERATING STATUS Millstone Unit 1 Notes

1. Unit Name:

2. Aeporting Period:

Mav 1980

3. Licensed Thermal Power (MWt):

2011 662

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

660

6. Maximum Dependable Capacity (Gross MWe):

684 654

7. Maximum Dependable Capacity (Net MWe):

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

N/A N/A l

9. Power Level To which Restricted,if Any (Net MWe):

N/A

10. Reasons For Restrictions,If Any:

N/A N/A N/A This Month Yr..to.Date Cumulative 744 3647.0 83327.0

11. hours In Reporting Period

12. Number Of Hours Reactor Was Critical 724.5 3627.5 64012.5

13. Reactor Reserve Shutdown Hours 19.5 19.5 954.5

14. Hours Generator On-Line 720.5 3623.5 61719.4 i

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1272306 5949889 109997834 i

17. Gross Electrical Energy Generated (MWH) 502800 2086100 37317496

18. Net Electrical Energy Ger.erated (MWH) 482728 199416b 35633947

19. Unit Service Factor 96.8 99.4 74.1 1

20. Unit Availability Factor 96.8 99.4 74.1

21. Unit Capacity Factor (Using MDC Net) 99.2 83.6 65.4

)

98.3

22. Unit Capacity Factor (Using DER Net) 82.8 64.8

23. Unit Forced Outage Rate n

U 15.9 j

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

)

Annual Refuel and Maintenance outage scheduled to coninence Sectamber 19, 1980 for approximatelv 8 - 10 weeks l

l 800622 25._ If Shut Down At End Of Report Period, Estimated Date of Startup:

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

Forecast Achieved INITIAL CRITICALITY

.N/A INITIA L ELECTRICITY

. COMMERCIAL OPERATION (9/77 )

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

May 6, 1980 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months Reduced power to 90%

because of main condenser conductivi ty.

1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months Reactor 100%.

11ay'8, 1980 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Reducing reactor power to repair main condenser and rebrush reactor recirc. M.G.

sets. A rod pattern adjustment to be made at this time also.

0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months Reactor power at 45%.

1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months Increasing reactor power to 100%.

May 10, 1980 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months Reactor pcticr at 100%.

1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months Reducing reactor pewer to 94% to maintain cordenser as limits.

2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months Increasing reactor power.

May 11, 1980 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Reactor power at 100%.

May 14, 1980 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Reducing power for turbine stop valve testing.

0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months Reactor power 90%.

0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months Turbine stop valve testing complete. Reactor power at 100%.

May 20, 1980 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months Showing a loss of MWE.

Feedwater heater protubations also occurring.

1320 hours0.0153 days 0.367 hours 0.00218 weeks 5.0226e-4 months Reducing reactor power.

1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months Reactor power at 88%.

" May 21, 1980

'0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months Increasing reactor power to 98%. Still showing a loss in MWE.

1735 hours0.0201 days 0.482 hours 0.00287 weeks 6.601675e-4 months Suspected leak in the 8th or 9th stage extraction steam expansion joint off 'A' L.P. turbine.

Reducing power to 82%.

1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months Reactor power 82%, 515 MWE.

May 22, 1980 Maintaining power at app aximately 82%, 515 MWE.

May 30, 1980 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months Commenced shutdown to inspect and repair suspected steam expansion joint damage off 'A' L.P. turbine.

May 31, 1980 0031 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months Turbine off line.

0437 hours0.00506 days 0.121 hours 7.225529e-4 weeks 1.662785e-4 months All control rods inserted.

Reactor shutdown.

=

s UNIT SifUTDOWNS AND POWER REDUCTIONS COCKET NO.

50-245 UNIT NAME Millstone-1 DATE 800505 REPORT MONTil May COMPLETED BY G. liarran TELEPHONE 203-447-1792 ext. 655 "i

.3 ee n c

en n

.2 e s

-3.s ;;;

Licensee i t, c.

Cause & Corrective 8-3 Action to No.

Date g

3g jij

,g g 5 Event u?

jdg Report #

<N 0

[U c3 5 5

Prevent Recurrence Q

03 800530 S

23.5 A

4 N/A ild Turbin Unit was removed from service to inspect and repair as necessarj a steam leak in the extraction steam expansion joint off L.P. turbine.

I 2

3 4

F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain).

Method:

Exhibit G-Instructions l-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 Tra'ning & License Examination F-Administrative 5

G Operational 'Irror (Explain)

Exhibit I-Same Source (9/77)

Il-O her (Exp'.:in) t 9

REFUELING.INFORitATION REQUEST l.

Name of facility:

Millstone 1

^

2.

Scheduled date for next refueling shutdown:

Fall 1980 3.

Scheduled date for restart following refueling:

Late Fall 1980 4.

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

Yes. Technical Soecification changes regarding:

(1) Maximum Average Planar Linear Heat Generating Rate (2) Maximum Critical Power Ratio 5.

Scheduled date(s) for submitting proposed licensing 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:

168 Retrofit" 8 x 8 fuel assemblies are scheduled for insertion in cycle 8 (reload 7).

4 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 fue' assemblies:

2184 a.semblies 9.

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

i l

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

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

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ML19323H993

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