B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With

Monthly Operating Rept for May 1999 for Mnps,Unit 1.With

ML20196A860
Person / Time
Site:	Millstone
Issue date:	05/31/1999
From:	Landeche D, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17807, NUDOCS 9906230006
Download: ML20196A860 (6)

Text

.. Northeri R Pe Feny Rd. (Rouw W), Wa dord, CT 063M Nuclear Energy moe Nocie., po er staeoo Northeast Nuclear Energy Company P.O. Ilox 128 Waterford, CT 06335-0128 (860) 447 1791 Faz (860) 444-4277 The Northeast Udlides System Jl.N I 41999  !

Docket No. 50-245 B17807 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthiv Operatina Report in accordance with the reporting requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the Monthly Operating Report for the month of May,1999.

Should you have any questions regarding this submittal, please contact Ms. Mari Jaworsky at (860) 447-1791, Ext. 5379. /

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

, /)

Mash.

D. Landeche

\

l Director - Unit 1 Operations '

Attachments (1) cc: H. J. Milier, Region l Administrator L. L. Wheeler, NRC Project Manager, Millstone Unit No.1 9906230006 990531 P G

PDR ADOCK 05000245 R PM L Os3422 5 RIT.12 %

i.

Qocket No. 50-245 B17807 Attachment 1 Millstone Nuclear Power Station Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report - May 1999 June 1999

r'- -

' . . U. Si Nuclear Regulatory Commission

~

.B17807\ Attachment 1\Page 1 REFUELING INFORMATION REQUEST l

1. Name of the facility: Millstone Unit No.1

2. Scheduled date for next refueling outage: Permanentiv ceased operation and certifications submitted to the NRC in accordance with 10CFR50.82.W

3. Scheduled date for restart following refueling: N/A

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

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

N/A

6. Important licensing considerations associated with refueling, e.g., naw 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:

In Core: (a) Q in Spent Fuel Pool: (b) 3068 Unconsolidated .

j

8. The present licensed spent fuel pool storage capacity and the size of any 1 increase in licensed storage capacity that has been requested or is 1 planned, in number of fuel assemblies:

Present Capacity: Maximum 3229 fuel assembly locations

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity: N/A

")

B. D, Kenyon letter to U. S. nuclear Regulatory Commission. " Millstone Nuclear Power Station, Unit No.1, Certification of Permanent Cessation of Power Operations and that Fuel has been permanently Removed from the Reactor," dated July 21,1998.

w

U. S. Nucl:ar Regulatory Commission B17807\ Attachment 1\Page 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245 UNIT: Millstone Unit 1 DATE: 6/07/99 COMPLETED BY: G. Newburgh TELEPHONE: (860) 444-5730 I I

MONTH: May 1999 i DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 I l

4 0 20 0

]

5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

~

. . U. Si Nuclear Regulatory Commission B17807\ Attachment 1\Page 3 .

UNIT NAME: Millstone Unit 1 DATE: 6/7/99 COMPLETED BY: G. Newburgh TELEPHONE: (860)444-5730 OPERATING STATUS

1. Docket Number 50-245

2. Reporting Period May 1999 Notes:

3. UtilityContact G. Newburgh

4. Licensed Thermal Power (MWt): 2011

5. Nameplate Rating (Gross MWe): 662

6. Design Electrical Rating (Net MWe): 660

7. Maximum Dependable Capacity (Gross MWe): 670

8. Maximum Dependable Capacity (Net MWe): 641

9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons: N/A

10. Power Level To Which Restricted, if any (Net MWe): 0 11.-Reasons For Restrictions,if Any: Permanently ceased operations and certifications submitted to the NRC in accordance with 10CFR50.82 l This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744.0 3623.0 249143.0

13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9  !

14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3

15. Hours Generator On-Line 0.0 0.0 166560.7

16. Unit Reserve Shutdown Hours 0.0 0.0 93.7

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0

18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0

19. Net Electiical Energy Generated (MWH) -1798.0 -9469.0 100984499.0 1

20. Unit Service Factor 0.0 0.0 66.9

21. Unit Availability Factor 0.0 0.0 66.9

22. Unit Capacity Factor (Using MDC Net) -0.4 -0.4 62.1

23. Unit Capacity Factor (Using DER Net) - -0.4 -0.4 61.4

24. Unit Forced Outage Rate 100.0 100.0 24.1

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

Shutdown at time of this report

26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup: Unit has permanently ceased operations.

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

Forecast Achieved INITIAL CRITICALITf N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

,snd 3, 0 i snd 1

h it g 3 e e )i) 8c n o n 4e a

8 9cnt eie n r 7 v c i(i( 9it 1 it olat 5 U u 5-i n ))

cist -

cie ne 4 b 4 t

c e 1 1

((

1

- aat n Aa t 2- e w 4 e r r )) 5r c ia 3 r a R n "s c

n r aa 0Pf 0 o e 4-r o ceu s 0Pid i norpie l

(( f ot 8 dni P "e 8 t

22 dt 5 t N de n amf it ls l

G 6

)0 CnR

&ito 88 00 de e d elit rd niwic ri rd e a d s on i

a deninCe ec n t

M 8 t 55

(

RR de n oa n ea d sAe v FF am mPF e amul i _

OEYE u

a e r CC t

Smtsa oyet rd e SmiqPrisiteio t

n NMBN C P 00 EcSl a on el t T ADO 1 1 Ee r ue cl EcUwic Ee cn r oau ENEH ERoNR I " f ERoPFF I " f KTTP CINLL EE t

• s n

O D UPE e n

MT o O p e A C m'd /

oo N hn )0 t

CC o=

Mno si ua or t

S iu N v O

m e 'e A eD r(

mPno t /

I T sd yo N C

U SC mrami) a coci t n -

D 9 rSf r ua c dp l

E 9 cdex R 9 1

e # SieRE laa au l

t R

E y

a s t r t uu mienr(e r W M n

eepno A

/

dnnotnwh oaa uoot t

hMMACPO O  : icve N P H LER t e - - - - - -

D T M1 23456 -

N _

N O _

A M r =

S o N T t c

R f a n W O o e o _

O P E

dngR it a

D oin t 4 n T

U R ht t

eh o uw im MSD a _

H x .

S E _

T I ) e N n s )

n

• ia n _

U n lp e ia _

o x ic lp s nL x a F Et o _

e ( s i&

t E R e rTe c

ig r

(

r lu r tsin o r

io a enieEi r )n a

n Fe c n

Rav yT a lalp ri t e nagor t

iso) r r n o x n t r 4 t io au r o 4 7

melniatosiE pt el ant nt uri rr i

t. (

s uH nuifinu e s D( o q a e gemeph e pd t im sEMRROA a OO - -

e - - - - - -

m 'ep RABCDEFGH o4 S Ce g T y

ya r

to\ P 3 1

a1 2 e 1 d lut g n t

a 5 9

le u

e e D de d Rm O c e rh r h O oc a c 0 FS et a o 1

FS lcA u\

t N

5 9 '

N7

. 0 S 78

.1 UB