ML20050F873

Monthly Operating Rept for June 1981

ML20050F873
Person / Time
Site:	Millstone
Issue date:	07/06/1981
From:	Howlett G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20050F870	List: ML20050F869 ML20050F873
References
NUDOCS 8204130405
Download: ML20050F873 (5)

Text

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Docket No. 50-336 Date: 7/6/R1 Completed B~y :~G.H. Howlett III Telephone: 20374~4TT97TTK4-REFUELING INFORMATION REQUEST

1. f,ame of facility: Millstone 2

2. Scheduled date for next refueling shutdown:

Commenced refuel outage December 5,1981.

3. Schedule date for restart following refueling: January 16, 1982

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

It is not anticipated that Cycle 5 operations will require Technical Specification changes or other License amendments.

5. Scheduled date(s) for submitting licensing action and

supporting infonnation

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 opera tion.

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:

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 E. The present licensed spent fuel pool storage capacity and the size of any l increase in licensed storage capacity that has been requested or is planned, j

'in number of fuel assemblies: <

667

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.

1987, Core Full, Spent Fuel Pool contains 648 bundles, e204130405 e10709 PDR ADOCK 05000336 R PDR

Oi tR ON. D G 51. ; ORT i v>u.L I ?.O. .50-336 DALE 07/.03/81, Howlett CO'tPU 1rD BY (G. _H.

I ri u i!or,E 203)_447-1791 ext. 346 OliR s fisc s r u t:s N"ic5

• Items 21 & 22

1. Unii x me: .billstone_2_.._______ .

2. n roriin; rcrind. June 1981 -- Cumulative are computed using a weighted average.

3. Licinw d Thenaal rov.. t'.!V. i): .27.00_. -

4. hphte Rating 1,cioss 3Dve): _9]70

5. Dm;n riectrical Rating tNct 3DVe):

6. Stasimum Dupendal.le Ccpacity (Grus Siwe): __ 5

7. \!asimem Depnd:ble Capwity (N:: 5!We): -

b. If Cl anges Oscur in Capacity Hatir.;,(liems Number 3 Through 7) Since Last Report, Gise Reasons:

.___ NQne _

9. Power Lesel To Which Restricted.lf Any (Net 5tWe): None

10. Re:: ons for Restrictions. lf Any. None This 5!onth Yr..t o.Dat e Cumulatis e ~

• 720 4,343 48,335

11. Ilours in Reporting Period

12. Number Of Ilours Reactor W.u Critical 699.3 3,586.5 34,835.8

13. Reactor Resene Shutdown !!ours 0 0 . 2_, Q7 M _ .

14. Ilours Generator On l.ine 693) 3.525.9_ 3L294'.9

15. Unit Resene Shutdown llours 0 0 468'.2

16. Gross Thermal Energy Generated (51Wil) 12 853,185 9,309,779 82,545,100 .

17. Gross Electrical Energy Generated ('i1Wil) 611,400 , _ ,

3,094,090 26,767,007 IS. Net Electrical Energy Generated (51Wil) 589,374 2,976,830 -

25,638,876

19. Unit Senice factor 96.4 81 .2 68.9

20. Unit Availability Factor 96.4 81.2 69.9 l 21. Unit Capacity Factor (Using 31DC Net) 95.7 79.3_ 63.9 94 I 78.8 62.8

22. Unit Capacity Factor (Using DER Net) .

3.6 -18.8 22.3

23. Unit Forced Outare Rate

24. Shutdowns Scheduled Oser Nest 6 hionths (Type. Date.and Duration of Eachl: .

Refuelin9, December 5, 1981, 44 Days .

l 25. If Shut Doun At End Of h >rt Period.Esiimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forecast Achiesed INITI A L CRITICA LITY N/A N/A INITI \L ELECTRICIIY N/A N/A CON!\lERCIAL OPER ATION -N/A ..N/A (4/771

J As I r. IGE D AILY L*N17 I obi R L EVEL ~

o DOCLE T No. _ 50-336 _

, g.g _ Millstone 2 DATE 07/03/81 CO'.!PLE TED BY ._ . H. HOWlett 1ELEPHONE _(2031 447 _179,1 Ext. 364 MONill June 1981 DAY AVER AGE DAILY POWER t.EVEL DAY ~ AVERAGE DAILY TOWER LEVEL

(MWNet) (MWe Net) 1 _. 862 860-37 2 862 859 4

g i' '

3 _ 861 19 85,9 4 860 yo 859 -

5 .

860

. 21 859 6 859 22 859 7 859 23 858 -

j g _858 -

24 858

. , 858 25 1 859 >

3o, 857 26 860 1i .857 27 R60 -

i 12 851 _

g 860 i

13 6.5 29 861 34 436 3o 861 1-

~ 15 858 _

33 ---

i. 16 859 i

l' INSTRUCTIONS On this form: 1.lis' the asente daily uni: pow er inclin MWe-Net for caeh day in the reponin; m.mth. C.im;me io ~

~

the r.estest wh61e metswatt.

(9/i71 i

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, _ , . _ - . . , _ ,_ -. . _ = _ . _ , - , ,

50-336 UNITS!!UTDOWNS AND POWER REDUCTIONS DCC"ET NO. -

UNIT NAM Millstone 2 DATE 07/03/81 REPORT MONTil June 1981 COMPLETED :Ly G H. Howlett TELEPliONE f 203) 447-1791 X364

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.=_. :ei  ? -a e 5

, .E :  : ,sa .

Licensee yr, s *, Cause & Correcuve I No. Date 5E ji5 i i Event-  ? . s.1 Action to \

$E 5 j@g Report 2 SU j' Present Recurrence 5

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5 810613 F 25.7 A 1 --

IA INSTRU The unit was manually shutdown to allow the refurbishment of 22 Reactor Coolant System RTD cable i

j connectors. Upon completion of repairs the unit returned to normal 100% power operations.

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SUMMARY

The unit operated at or near 100% of rated thermal power throughout the reporting period, except for the outage of the 13th.

(9/77)

Docket No. 50-336 Daga 1c1 Date -

07/06/81 Unit Nane Millstone 2 -

Completed By G. H. Howlett .

- Telephone (203) 447-1791 x364 N CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month May 1981 i

DATE l SYSTEM COMP 0NENT ' MAINTENANCE ACTION f

1/5/81 - 5/18/81 Various Mechanical Snubbers and Followed test program of acceptance or rejection associated hangers of mechanical snubbers. See LER 81-018 5/12/81 l Reactor Coolant Pressurizer Pressure Transmitter Replaceo bridge rectifier -

P-103 t

5/14/81 i Reactor Coolant 2-RC-402, Pressurizer Replaced valve i Relief Valve 5/14/81 1 Reactor Protection Ch 'D' Excore Detector Input Swapped Ch 'D' Excore input with Ch 'Y' Excore input ,

5/14/81 {ReactorCoolant 2-RC-65, Reactor Coolant System Repaired body to' bonnet leak Sanple Header Isolation Valve -

5/16/81 Chemical & Volume Heat Tracking Cht. 5-25 Repaired grounded circuit Control 5/18/81 Reactor Protection Ch 'A" RPS, Thermal Margin / Low Replaced T/C Max Selector Module

. Pressure Computation Module 5/28/81 Reactor Protection Ch 'B'RPS, F-1 Computation Replaced Module Module -

5/28/81 Auxilliary Feedwater Steam Driven Aux. Feed Pump Replaced turbine bearings, (See LER 81-019)

Turbine, H-21 5/28/81 Reactor Building 2-RB-8B, Spent Fuel Pool Heat Rebuilt valve Closed Cooling Water Exchanger Cooling Water Outlet Valve 5/29/81 Reactor Protection Ch 'B' RPS, F-1 Computation Module 4

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