ML20050F833

Monthly Operating Rept for Oct 1981

ML20050F833
Person / Time
Site:	Millstone
Issue date:	11/09/1981
From:	Howlett G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20050F811	List: ML20050F796 ML20050F833
References
NUDOCS 8204130385
Download: ML20050F833 (6)

Text

e OPERAII.NG DATA RLPORT DOCKET NO. .50-336_.

DA I E _LL.9,8L.

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COSIPLElCD liY G._IlJinwlett 1ELEPilONE _(2031._4_4.7-1791 X4431 OPI'RT ilNG 5 f A 1 US Notes

• Items 21 & 22

1. Unit N.nne: 11t11 stone. 2-._ __ _ Cumulative are computed

2. Rcrosting Period: October __1981 _ _ _ _

using a weighted average.

3. I,.icenwd Thennal Power (*.!Wr): .2Z00 --

4. Namept.ite !!.. ting (Gron $1We): _909 _

5. Design Electrical Rating (Net a!We):870

6. ?.!a.simum Dependable Capicity (Gross $1We): 895-

7. Sf asimum Dege.!abic Capacity (Nct 31We): .864

8. If Changes Occur in Capacity Ratings (Ituns Number 3 Through 7) Since Last Report,Gise Reasons:

Nonn

. _ . =

9. Power I.ocl To Whi;h Restricted,if Any (Nc StWe): N0fle

10. Reasons for Restrictions,if Any: f[one ___

This 51onth Yr. to.Date Cumulatise

11. !!oun In Reporting Period 745__ 7,296 SL288_.

12. Number Of flours Reactor Was Critical 735 E- E.535 37.26L3

13. Re.ictor Resene Shuidown !!ours 0 0 2;0_6J 7

14. Ilours Generator On Line 710.4 6,411 36.180_

15. Unit Rexne Shutdown llours 0 0 468.2

16. Crow Thermal Energy Generated (siWil) 1 86L6]3 16.969 d83__ 90.205.304

17. Gron Elcetsical Energy Generated (5f Wil) 609.B80... 5,60LE60 _2L2B2._477

18. Net Electrical Energy Generated (31WH) RR6.996 5_401_241 2R_n61.114

19. Unit Senice Factor 4 5 _ 4 _. R7.4 70.5 71.5

20. Unit Asailability Factor 95.4 87.9_

21. Unit Capacity Factor (Using 51DC Net) 91.2 8 5 . 7 -. 65.B*

22. Unit Capacit3 ractor (Using DER Net) 90.6 85.1 64.7*

23. Unit Forced Outage Rate 4.6 12.1 21.0

24. Shutdowns Scheduled Oser Nest 6 31onths (Type.Date.and Duration of Eacht:

Refueling. Dec. 5, 1981, 8 weeks.

25, if Shut Down At End Of Report Period, Estimated Date of Startup: N/A

26. Units in Test Status (Prior to Commercial Operation): Forecut Achiesed INITI A L CRITICA LITY N/A N/A INIII AL ELECTRICITY N/A N/A COststERCI AL OPER A1 ION N/A N/A Note: Errors in September 1981 report; Items 21 and 22 cumulative, should have q Read. (#21) 65.4 and (#22) 64.3. iop7:

8204130385 811113 PDR ADOCK 05000336 R

PDR _

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336 -

UNITNAME Millstone 2 DATE 11-12-81 COMPLETED BY n _ H _ Hewlptt REPORT MONTH October 1981 TELEPHONE f2nM aa7.1701 X4431

. "i -

N". Date

, .! ? 3 h Yf:; Licensee [ t, h. Cause & Cuirectne i 5? 4 2sE Event  ?? c?

0 Action to

$ E jg= Report a <N 0 Present Recurrence 6

9 81 11 16 F 26.8 B 3 N/A N/A N/A While troubleshooting feedwater control circuitry a faulty signal was generated causing a Reactor trip on Steam Generator level.

10 81 11 27 F' 7.8 B 3 N/A N/A N/A While Eddy Current Testing the Main Condenser, tube plugs were removed resulting in a loss of Condenser vacuum due to gross air in leakage with a subsequent turbine / Reactor trip. The condenser was repaired and normal plant operations were resumed.

Summary: The unit operated at or near 100% rated power throughout the report period except for the outages of the 16th and 27th.

0 A\ ! R AGE !)stLT L' NIT i Owl R LEVEL i>ocK ET No. _50-336_ __ _

, UNIT tiillstone 2 DATE .11ovember_13m 1981 G. H. Howlett CostN.E TE D 11Y

, , g t ti,lioNE (203) W - W X4431

.:os tii

. October 1981 DAY AVER AGE DAILY POWER LEYFL DAY AVERAGE DAILY f OWER LEVEL

(\!Wr Net) (MWe-Net)

_ 856 37 805 2 _

857 850

, is 3 _ 857 850 39 ,

4 857 ,o 851 3

857

' 21 854 6

788 854 y

7 853 ,3 85.3 g 854 853 i 24 9 852 25 853 10 857 852 26 794 27 406.

12 .855 _ _

s 549--

13 856 851 29 14 857 851 30 is 854 33 851 16 - - -

66--

INS 1RUCilONS Or, thh formst.!!st the asetoye d:ily ur.i: p.mer kselin MWe-Net for each day in the reportine :nar.th. Compute 10 ' -

the r.catesi v hole :r.cpw ait.

l t'

'#7)

coc4wt !.o. 50-336 Page I of I Date 11/12/81 Unit Name Millstone 2

< Completed 3y G. H. Hewlett Telephone (203) 447-1791 X4431 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month September 1981 DATE SYSTEM COMPONENT MAINTENANCE ACTION 9/1/81 Reactor Protection Channel ' A' Low Steam Generator Removed Low S/G Press. Bistable and replaced R5 Bypass Potentiometer.

9/3/81 Reactor Regulating Power Ratio Calculator Removed and replaced Multiplier / Divider Module, Type 19-302 (84,5).

9/8/81 Chemical & Volume Charging Pump P-18C Repacked pump.

Control 9/9/81 Chemical & Volume j Charging Pump P-18B Repacked pump.

Control j i

9/9/81 Service Water l Chiller,X-181B Repaired tube leak.

I 9/10/81 Enclosure Building 'A' EBFS Discharge Damper Replaced air operator on fan damper.

Filtration 2-EB-52 9/11/81 Chemical & Volume Charging Pump P-18 A Repacked pump.

Control 9/18/81 Chemical & Volume I Charging Pump P48 C Replaced various internal parts and repacked pump.

Control k

~" ~~ * ' * * * * * ~ - ~ ~

^e~-me wee - e

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Docket No. 50-336 Date: 11/13/81 Completed.By: G.H. Howlett III Telephone: 20'374f7-1971 X4431 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown:

Commenced refuel outage December 5,1981.

i 3. Schedule date for restart following refueling: February 1, 1982

4. Will refueling or resumption of operation thereafter require a technical

specification change or other license amendment?

i It is anticipated that Cycle 5 operations will require

1. Technical Specification changes or other License amendments.

5 .- Scheduled date(s) for submitting licensing action and supporting information:

Licensing documentation will be provided a minimum of.90 days

prior ~ to start-up of Cycle 5 or as documented in the R.A. Clark letter to W.G. Counsil, dated 10/6/80, authorizing Cycle 4 4 operation.

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

N/A

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

{ (a) In Core: 217 (b) .216

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

667

9. The projected date of the last refueling that can be discharged to the spent fuel pooliassuming the present licensed capacity:

r

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

! .1987, Core Full, Spent Fuel Pool contains 648 bundles.

I

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