ML19262D012

Monthly Operating Rept for Mar 1980

ML19262D012
Person / Time
Site:	Millstone
Issue date:	04/08/1980
From:	Howlett G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19262D011	List: ML19262D010 ML19262D012
References
NUDOCS 8004220413
Download: ML19262D012 (6)

Text

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OPERATING DATA REPORT DOCKET No. 50-336 DA rE ADril 8.1980 CO.\\lPLETED BY G.H. Howlett TELEPHONE 203 447~-1791 X364 OPERATING STATUS Millstone 2 Notes

• Items 21 & 22,

1. Unit N3me.

March 1980 Cummulative are computed

2. Reportin; Period:

3. Licen>cd Thermal Power $5tht): 2700 using a weighted average.

4. Nameplate Rating iGross \\lwe):

909

5. Desi;n Electrical Rating (Net SIWE):870

6. Stasimum Dependable Capacity (Gross 31Wep: 895

\\

864

7.. lasimum Dependable Capacity dNet stwe):

'i. If Chamges Occur :n Capacity Ratin;3 titems Nurnber 3 Through 7) since Last Report. Gise Reasonc None

9. Power Lese! To hhich Restricted. If Any INet.\\lhe):

None

10. Reasons For Restrictions. If Any:

None This.\\!onth Yr..to.Date Cumularise

11. Hours In Reporting Period 744 2,184 37,392

12. Number Of Hours Reactor has Critical 698.5 2,112.6 27,191.7

13. Reactor Re>ene Shutdown !!ours 0

0 q,0 %

l-1. Hours Generator On.Line 678.0 2.059.1 25,879.3

15. Unit Re<ene Shutdown Hours 0

0 3~35 7

16. Gros, Thermal Ener;> Generated (51%I1)

I,740,751

_5f25,544 63,124,172~~~~

l-Gros, E:e:tr:e.'l Energy Generated isti.Hi 567,033 1,778,469 20,363,114 li Net E'e trical Ener;> Generate!,3thH)

Sf4,23T- ~ ~

1,7TO 893 T9,T4T,151 It Unit Senice Faetor 91.1 94.3 69.2

20. Unit u.'iiabdity Factor 91.1 94.3 70.1

i enit C;p av F2etar it,;n; \\iDC Neri 84.7 9.0.7 63.6

cmr cy,,gc3 p,c.y,,esia; DER Net) 84.1 90.0 62.3

.1 Unit Forced ouage Rate 8.9 5.7 22.6

4. Shatdowa, Seheduled Oser Nest o stonths tty pe. Dire. and Duration of Eachr Refueling (Cycle 4), July 1,1980,9 weeks.

NA

- If Wr Dm n \\t End Of R eport P.. d. E-

>JDe af :

up.

h Units in Test Status iPrior to CommerJat Onr2 tion t Foreea,r Achiewd INITI AL CRITN A LtT'r N/A N/A INITIAL ELECTRIUTY N/A _

N/A C0\\isiERc! AL CPn iT!o',

N/A N/A "0TE: Correction to February Report Item 18.

Should read Month 528 95T -

Yr-To-Date 1,166,662, Cumulative 18.935,920.

Item 22 Year to Date sncuTd read 93.1 8004220g3

AVER AGE D All.Y UNIT POWER LEVEL 50-336 DOCKET NO.

Millstone 2 m.,7 DATE April 8,1980 CO\\!PLETED BY G.H. Howlett TELEPHONE (203)447-1791 X364 March 1980

,g.

DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL Dik,e-Net) anve. Net) 850 849 1

1,e 2

852 850 33 3

781 849 39 4

815 750 20 5

R14 21 289 6

820 536 22 7

850 13 73 8

851 484

,4 9

R51

,5 343 10 850 846 26 11 850 847 12 0

(-7)

,s 847 13 307 847

,9 847 84'/

34 3g 15 827 847 3

16 849 IN S TR UCTIC.N S On this Drm.n. i.c -'.: n se 6:h :..: p. e b d.., ' 9.'ie.N*c. r.; em 33 g, g, 9.g.- &c.yw

.e r e a en.i F. ': -- _, a :

I

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I PAGE 1 of 2 h

I T

llNII SilUIDOWNS AND POWER REDUCTIONS one 2 A E DATE April 9,1980 COMPLETED l!Y G.H. Howlett til RE PORT MONIll flarch 1980 203 447-1791 X364 l ELEPilONE 5

E

{g

'h

_$ E' ~;

t.icensee E r, h

Cause & Corrective

,t hic 3g j

jsy livent y?

gU3 Action to f-y jg

Repo, u

mV Prevent Recurrence H

6 4

800312 F

29 A

3 ft/A

.;l VAL"vl (

Feedwater Regulating valve (2-fW-51B) locked-up (closed), resulting in a reactor trip on Low Steam generator level.

5 800320 F

0 A

4 N/A RB CRDRVE Dropped C.E.A. #7-1 due to failed Control Element Drive Mechanism power supply.

Reduced power to 65%.

6 800321 F

18.3 8/G 3

ft/A ZZ ZZZZZZ Instrumentation 'echnician removed flain feed pump suction pressure trans-mitter from service for calibration.

This lead to the camp tripping on low suction pressure and a subsequent reactor trip on Low Steam Generator level.

SilMMARY: The unit operated at or near 100% rated thermal power throughout the reporting period except for the following; 3/2-3/6 operations at 96% power in preparation of a Moderator Temperature Coefficient Test, 3/20 Dropped CEA and reactor trips on 3/21 and 3/23.

fl0TES:

Correction to February, Unit Shutdowns and Power Reductions; Item #1 Duration (Hours) should have read 23.5 not 24.5.

Item #2 Duration (llours) should have read 16.3 not 16.4.

i9///)

J l'AGI 2 of 2 50-336 U

UNil S!!U1 DOWNS AND POWl:R RE!)UC1 IONS

' MIIISl""" d U l P A 1E DATE April 9,1980 COMPI.ETLD liY G. ll. Howlett II REPolt'I MON fli March 1980 l tttpliONE 203 ^47-1791 X364 I

=

e 3g

'b J, Y l t.ite m ee

,E-r, L' n, cause & corrective p2 j

j5$

twn:

Lf '2

!i?

Attion to No.

Date H,

dE 3 ;y, S Rep.n: u eU UU Prevent Recurrence j

4 0

f C

l 7

800323 F

18.7 A

J N/A lill VALVEX Feedwater Re9ulatinq Valve (2-FW-51A) lill llTEXCil locked-up (closed) during a power reduction for a feedwater heater problem. The reactor tripped from 20% power on Low Steam Generator Level.

hy Ed3 v

@a@@,,

<2 n)

R,

Docket No. 50-336 P'8 9e I Of I

Date April 10, 1980 Unit Name ' Millstone 2 Completed By G. li. Ilowlett III Telephone (zu3J44/-i/91 x3b4 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month February 1980 DATE SYSTEM COMP 0NENT MAINTENANCE ACTION 2/4/80 Reactor Protection R.P.S. Ch. "B" Reactor Coolant Replaced and calibrated converter.

Pump Speed Sensing, Frequency to Voltage converter.

2/2//80 Safety injection 2-SI-466 Safety Inj Tk Fill Line Valve leaked through.

Rebuilt valve.

Relief Valve

Docket No.

50-336 Date:

April 11, 1980 Completed By G.H. Howlett III Telephone:

2037447-1971 X364 REFUELING IflFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown: July 1, 1980 3.

Schedule date for restart following refueling: September 1, 1980 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?

Technical Specification changes will be necessary as a result of the change in fuel and safety analysis supplier.

5.

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

The schedule for submitting license actica is as follows:

Basic Safety Report 3-6-80 ECCS Results 5-15-80 Reload Safety Evaluation 5-15-80 6.

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

Cycle 4 will be unique in that it will be the first where the fuel and safety analysis will be supplied by Westinghouse.

7.

The n mber of fuel assemblies (a) in the ccre and (b) in the sper.: tel c

storage pool:

(a)

In Core:

217 (b) 144 3.

The present licensed spent fuel pool storage capacity and *M size of any increase in licensed storage capacity that has been recuested 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 pool assuming the present licensed capacity:

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

1987, Core Full, Scent Pael Pool contains 648 bundles.

U l