ML20044D006

Monthly Operating Rept for Apr 1993 for Millstone Nuclear Power Station Unit 3

ML20044D006
Person / Time
Site:	Millstone
Issue date:	04/30/1993
From:	Doboe L, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-370, NUDOCS 9305140293
Download: ML20044D006 (5)

Text

.

i NORTHEAST UTILITIES o,ne,,, omce,. seicen s:,,m se,nn. con,m,c.,,

m m :,w m n n e cw -.

l O O BOX 270 I

.isu m :,m-sucw " "

UN H ARTFoRD. CONNECTICUT 05141-0270

[

k J

(203) 665-S000

= w.ec.. ~.n. ew...

May 7, 1993 MP-93-370 Re: 10CFR50.71(a) l U.S. Nuclear Regulatory Commission l

Document Control Desk l

Washington, D.C. 20555 l

Reference:

Facility Operating License No. NPF-49 j

Docket No. 50-423 Dear Sir-In accordance with reporting requirements of Technical Specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 93-05 covering operation for the month of April is hereby forwarded.

Very truly yours, i

NORTHEAST NUCLEAR ENERGY COMPANY t

Step en E.scace t

Vice President, Millstone Station - NNECO t

Attachment

{

cc: T.T. Martin, Region I Administraton P. Swetland, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 i

V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 i

i k

l

[

l

?

I 1 P70 A 1 A i

9305140293 930430 PDR ADOCK 05000423 R

PDR 4

I OS342 REV,448

/

/ f i

l

', r

• • • • • • • WRC OPERAT!WG STATUS REPORT COMPLETED BY REACTOR ENGlWEER1kG *******

i l

1.

DOCKET.... 50-423 OPERAT!WG STATUS 2.

REPORTING PERIOD... APRIL 1993 OUT AGE + DNLIkE HOURS.. 215.5

• 503.5

= 719.0 r

3.

UT I L I T Y CONT ACT................. L. C. Doboe 203-447-1795 x 6076 4 LI CE NSED T HE RMA L P0WE R....................................... 3411

• MILLSTONE

• 5.

hAMEPLATE RATING (GROSS MWE)...................................

1,253 MJ

• UNIT 3 i

f 6.

DES I GN E LE CTR I CAL RAT ! kG ( WET MWE )............................. 1,153. 6 7.

max! MJM DEPE NDABLE CAP ACI T Y ( GROS S MWE )......................... 1,1S4.2 8.

MAX I MUM DE PE W0 ABLE CAPACI T Y ( WE T MWE )........................... 1,137.0 9.

I F CHAN GE S DCCUR ABOVE S I NCE L AST RE PORT, EE ASOWS ARE...........

W/A

10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (WET MWE)...............N/A

11. REASON FOR RESTRICT!DW, IF ANY....k/A MONTH TEAR TO DATE CUMULATIVE 10 CATE i

12. HOURS !W REPORilWC PERIOD 719.0 2,Blv.0 61,559.0 l

13. WUMBER OF HOURS THE REACTOR WAS CRITICAL 5 64.6 2,701.6 45,739.7 f

14. REACTOR RESERVE SHUTDOWW HOURS 0.0 0.0 6,466.5

15. HOURS GEkERATOR ONLINE 503.5 2,640.5 44,771.5

16. UNIT RE*ERVE SHUTDOWN HOURS 0.0 0.0 0.0 h

17. GROSS THERMAL ENERGY GENERATED (MWH) 1,685,792.0 8,'00,001.0 145,890,279.6

18. GROSS ELECTRICAL ENERGY GENERATED (MWM) 569,052.0 2,968,945.5 50,287,184.1

19. WET ELECTRICAL ENERGY GEWERATED (MWM) 533,648.4 2,814,119.1 47,801,3B6.4

20. UNIT SERVICE FACTOR 70.0 91.7 72.7 i

21. UNIT AVAILABILITY FACTOR 70.0 91.7 72.7

22. UNIT CAPACITY FACTOR (USING MDC NET) 65.3 56.0 68.1 j

23. UNIT CAPACITY FACTOR (US!WG DER NET) 64.3 B4.7 67.3 I

24. UNIT FORCED OUTAGE RATE 30.0 8.3 18.2

25. UNIT FORCED OUTAGE NOURS 215.5 238.5 9,970.9 i

SHUTDOWNS SCHEDULED DVER NEXT SIK MDWTHS (TYPE, DATE, AND DURATION OF EACH)..............

Refuet Dutage - July 31,1993 - 59 Days,1B Hours 1F CURREUTLY SHUTDOWh, ESi! MATED STARTUP DATE.....W/A i

l i

AVER AGE D AILY UNIT POWER LEVEL DOCKET NO: 50-423 l

UNIT:

h.flLLSTONE UNIT 3 DATE:

May 3.1993 j

COMPLETED BY:L. C. Doboe 203-447-1791 x 6076 MONTH April 1993 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

OdWE-NET) 1 0

16 1118 2

0 17 1115 3

0 18 1118

)

4 o

19 1115 i

5 0

20 1117 b

6 0

21 1114 j

7 0

22 1115 8

0 23 1116 9

0 24 1115 10 439 25 1114 11 1005 26 1114 12 1035 27 1116 J

l 13 1081 28 1114 14 1118 29 1114 15 1114 30 1113

U N I T S il U T D O W N S A N D POWER R E D U CTIO N S DOCKET NO:

50-423 UNIT:

MILLSTONE UNIT 3 -

DATE:

hiav 3.1993 COMPLETED BY: L C. Doboe TELEPilONE:

203-447-1791 x 6076 Number Date Type Duration Reason Method of Licensec System Component Cause and Corrective Action to Prevent (1)

(llours)

(2)

Shutting Event Report Code Code Recurrence Down the Number (4)

(5)

Reactor (3) 93-03 930331 F

215.5 A

4 93-004-00 TG JX Reactor and turbine trip caused by steam generator low low level aller an EllC power supply failure caused turbine valves to close.

The failed power supply was replaced and other system power supplies will be replaced during RF04.

I:

F: Forced 2:

Reasons:

3: Method 4: Table 1 -

5: Scheduled A Equipment Failure (Explain) 1 Manual IEEE Std 805/D5 - 1984 B Maintenance or Test 2 Manual Scram C Refueling 3 Automatic Scram 5: Tabic 2 -

D Regulatory Restriction 4 Continued from Previous Month IEEE Std 803 A - 1983 E Operator Training & Ijcense 5 Power Reduction Exam (Duration = 0)

F Administrative 9 Other (Explain)

G Operational Error (Explain) 11 Other

d R EFUELING IN FOR M A TIO N REO UE ST i

1 April 1993 q

?

1. Name offacility: Millstone 3.

f

2. Scheduled date for next refueling shutdown: July 31.1993

3. Scheduled date for restart following refueling: September 28.1993

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

change or otherlicense amendments?

l Yes

5. Scheduled date for submitting licensing action and supporting information.

Submitted March 15.1993

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

new or different fuel design or supplier, unreviewed design of performance analysis methods, significant changes in fuel design, new operating procedures:

k Millstone Unit 3 current fuel design incorporates a stainless steel skeleton and zircalloy fuel cladding design. Cycle 5 design will incorporate a zirlo skeleton and zirlo fuel cladding on feed assemblies. A Technical Specification change was submitted as per question 5 above.

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

i (a): 193 (b): 248 i

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage cr. pachy ihet has been sequested or is planned, in number of fuel assembhes:

Present size - 756.

i No increase reauested.

9. The projected date of the last refueling that can be discharged to the spent fuel pool

)

l assuming the present licensed capacity:

End of cycle 5.

i