ML20030C519

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Monthly Operating Rept for Jul 1981
ML20030C519
Person / Time
Site: Millstone 
Issue date: 08/04/1981
From: Harran G
NORTHEAST UTILITIES
To:
Shared Package
ML20030C518 List:
References
NUDOCS 8108260194
Download: ML20030C519 (7)
v • d • e


Text

l AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-245 UNIT _ Millstone 1 DATE -81nana COMPLETED BY G_ Harran I

TELEPl!ONE -(203)447-1791 X-655 t

MONTli JulV DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 578 586 37 2

574 is 324 3

423-550 19 4

RR7 20 RR6 5

^^8 21 586 6

259 22 583 7

RdA 23 RR3 8

RR5 24 582 9

RR7 25 583 10 ER1 26 684 11 RR2 27 ER4 12 ano 28 586 13 23 29 582 14 425 30 587 15 R74 31 586 l

l 16 586 INSTRUCTIONS On this fornn'.. list the average daily unit power levelin MWe Net for each dayin the reporting month. Compute to the nearest whole megawatt.

MDC of 654 based on conmitment to New England Power Exchange (9/77) 0108260194 B10813 DR ADOCK 05000

OPERATING DATA REPORT DOCKET NO. 50-?a4 DATE c1 none:

l C051PLETED 11Y 5 ' ~U7rran I

TELEi'llONE YdI/4472T791 X-655 OPERATING STATUS I. Unit Name: Millstnno finit l' Notes

2. Reporting Period: June 1981 (Corrections)
3. Licensed Thermal Power (51W ):

2011 662

4. Nameplate Rating (Gross 5the):
5. Design Electrical Rating (Net SIWey 660
6. hf aximum Dependable Capacity (Gross 51We): 684
7. h1aximum Dependable Capacity (Net 31We).

654

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

NA NA

9. Power Lesel To Which Restricted. !f Any (Net SIWE):

NA

10. Reasons For Restrictions,If Any:

NA NA NA This hionth Yr. to.Date Cumulative

11. liours in Reporting Period 770 4143

'- 92807

12. Number Of flours Reactor Was Critical 441 51 5 66974
13. Reactor Resene Shutdown liours 267 1248.5 2775.8
14. liours Generator On.Line
  • 316.5
  • 354.5
  • f4480.7
15. Unit Resene Shutdown liours 0

0 26.R

16. Gross Thermal Energy Generated (51Wii)

RR174R 567002 114997129

17. Gross Electrical Energy Generated (NtWill 167700 _ _ _,

1/2200 38968096 IS. Net Electrical Energy Generated (51Wif) 157207 148733 37178687

19. Unit Senice Factor
  • 43.9
  • 8.2 69.5
20. Unit Availability Factor
  • ol 9
  • 8.2 69.5
21. Unit Capacity Factor (Using 51DC Net) 33.4 5.2 61.3
22. Unit Capacity Factor (Using DER Net) 33.1 5.2 60.7
23. Unit Forced Outage Rate
  • R6 0
  • 79.6 16.8
24. Shutdowns Scheduled Oscr Nest 6 5fonths (Type. Date,and Duration of Each):

NA

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

NA

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

Forecast Achiesed INITI A 1. CRITICA LITY INITI AL ELECTRICITY NA C05t%1ERCI AL OPI'R ATION

(*) Changes made to the June operating data report due to an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> error in the months generato' on-line hours.

(9/~ 7 )

t

s UNITSliUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-245 UNIT NAME M411stene finit 1 DATE Alnann REPORT MONTil.Tunn (rnrractions)

TELEPlf0NE 203/447-1791 X-655 u

O c

,{g

}

$,Y h Licensee

[c-r, fo Cause & Corrective No.

Date g

3g y

jsE Event g3 gO Action to 3

t-f-

5 3 5 =s Report #

mU Prevent Recurrence o

e u

Q 3b 810421 F

  • 390.7 A

4 N/A CA ZZZZZ Balancing problems caused continued Turbine turbine outages.

Trips 4

810615 F

12.8 A

3 N/A N/A N/A Reactor mode switch failure.

I 2

3 4

F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain).

Method:

Exhibit G -Instructions 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) Fde (NUREG-D-Regulatory Res:rietion 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source 9

(9/77) (*) Change made to th(e June) report due to an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> error in the no iI-Other Exnlain

. 3b shutdown.

C

4 OPERATING DATA REPORT

~

DOCKET NO. 5f1 245 DATE 810805 i

CO51PLETED BY c umrran I

TELEPlf0NE !03/EhE1791 X-655 OPERATING STATUS Notes

1. Unit Name: Mill etnno linit 1
2. Reporting Period: July 1981 2011
3. Licensed Thermal Power tMwt):
4. Nameplate Rating (Gross MWe):

662

5. Design Electrical Rating (Net 31We): 660 004
6. Maximum Dependable Capacity (Gross 51We):
7. Maximum Dependable Capacity (Net SIWE):

654

8. If Changes Occur in Capacity Ratings (1: ems Number 3 Through 7) Since Last Report. Gise Re sons:

NA NA

9. Power Lesel To Which Restricted,if Any (Net MWe): NA
10. Reasons For Restrictiens. lf Any:

NA NA a

NA This Month Yr. to-Date Cumulative

11. Hours In Reporting Period 744 5087

' ' - '93551

12. Number Of liours Reactor Was Critical 729 1244 67703
13. Reactor Resene Shutdown llours 0

1248.5 2775.8

18. licurs Generator On Line 718 1072.5 65198.7
15. Unit Reserve Shutdown Ifours 0

0 26.5

16. Gross Thermal Energy Generated (MWil) 1331625 1898627 116328754 l
17. Gross Electrical Energy Generated (MWil) 409500 581700 39377596 i
18. Net ElectrLal Energy Generated (MWil) 1RR722 537455 37567409
19. Unit Senice Facter 96.5 21.1 _

69.7

20. Unit Availability Factor 96.5 21.1 69.7 i
21. Unit Capacity Factor IUsing MDC Net) 79.9 16.2 61.4
22. Unit Capacity Factor (Using DER Net) 79.1 16.0 60.8
23. Unit Forced Ourage Rate 3.5 56.9 16.7
24. Shutdowns Scheduled Oser Next 6 afonths (Type. Date.and Duration of Each,:

NA

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

N/A

26. Units in Test Str,tus (Prior to Commercial Operationi:

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY gjg COMMERCIAL Ol'I'R ATION (967)

- = -

4 i

UNITSMUTDOWNS AND POWER REDUCT!ONS DOCKET NO.

50-245 UNITNAME Millstone 1 DATE 810805 REPORT MONTil July COMPLETED 11Y - G. Harran TELEPIIONE (203) 447-1791 e

X655 i

IF

=. "'

-c 4.s.s.:

e,

.5 ?

E Licensee g

je.

Cause & Corrective

~

A o

No.

Date g

3g

(

,3g5 Event u?

E3 Action to H

$~

5 J. @ g Report #

SU EO Prevent Recurrence 5

u c

5 810703 '

S 0

H 1

XX XXXXXX Reactor Control Rod Pattern Change 6

810706 S

0 H

1 NA NA Process Computer Failure 7

810712 F

26 A

3 HH MECFUN Feedwater Regulation Valve Closure.

8' 810718 S

0 B

I HH MOTORX Condensate Booster Pump Repair, and l

HF VALVEX Service Water Cross-Over Valve i

Repair.

l I

2 3

4 F: Forced Reason:

S: Schedu!cd A Equipment Failure (Exp:ain).

Method:

Exhibit G Instructions

!-Manual for Preoaration of Data

!!. Maintenance of Test 2-Manual Scram. '

Entry Sheets for Licensee C-Refue!!ng 3-Automatic Scram.

0161)

Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain)

E Opera:or Trairing & License Examinatien F A,' innistratise 5

C 0,nera:ional Error (Exp!ain)

Exhibit !. Same Source 4

(9/77) 1I-O:her (Explain) 9 8

~~

Pa9e 1 of I Docket No.

50-245 Date Millstone 1

~

Unit Name 810408 Unit 1 I&C Department Completed By G. Harran Telephone (203) 447-1791

,4655 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month July

~

MTE SYSTEM COMPONENT MAINTENANCE ACTION t

7-6-81 Nuclear Instrumenta-tion IRM #16 Replaced Relay K9C 7-2-81 Fire System Fire Detector Replaced tubing to Diesel Fuel Day Tank Room Fire Detector 7-13-81 Feedwater System "A" Feed Valve Replace Positioner 7-13-81 Feedwater System "B" Feed Valve Replace Positioner 7-16-81 Nuc. Instrumentation IRM Channel 13 Preamp.

Repair & Replaced Q-2, Q-8, & C-32.

Replaced C-1 & C-2 on HV P.S., Main PC Board 7-22-81 Nuc. Instrumentation IRM Detector Power Supply Replaced C-1 & C-2 on Main Reg. PC Board 7-24-81 Rad. Monitoring Sys.

Steam Tunner Rad. Monitors (2)

Perform Product Acceptance Test after Repair by NMC 7-31-81 Makeup Water-System Condensate Storage Tank

. Replace Level Transmitter 7-50 &

Section of Tubing

~

7 I

~

REFUELING I;;FORFATIDM REQUEST 1.

Name of facility:

Millstone 1 Ili 2.

Scheduled date for nn.t refueling shutdo'<;n:

Fall 1982

,i 3.

Scheduled date for restart foll,cwing refueling:

Winter 1982 l

Will refueling or resumption of operation thereafter require a technical I

4.

specification change or other license amendment?

j.

ti Yes.

Technical Specification changes regarding:

0 4

(1) Maximum average planar linear heat generating rate Ig (2) Maximum critical power ratio

  • ii" R

s(;

N 5.

Scheduled date(s) for submitting proposed licensing action and supporting ll in formation :

4 s

H Summer 1982 H"

4 I

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis O

p methods, significant changes in fuel design, new operating procedures:

j h

172." Retrofit" 8 X 8 fuel ass' mblies are scheduled for insertion in Cycle 9 e

-]-

+

(Reload 8) i 7.

The number of fuel assenblies (a) in the core and (b) in the spent fuel storage

'ji pool:

t; l

(a) In Core:

580 (b) In SFP:

954 I)-

j l.

8.

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

' p

~

l U

l 2184 Assemblies i

t i

th I

li:

The projected date of the last refueling that can be discharged to the spent

~ 'lj 9.

fuel pool assuming the present licensed capacity:

h, h

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

y

\\

a j

1991, Core Full, spent fuel pool contains 2120 bundles j

k GRH:rmj l

I n

lI g

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