ML20054B288

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Monthly Operating Repts for Mar 1981
ML20054B288
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/09/1981
From: Jackie Cook
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20054B285 List:
References
NUDOCS 8204160459
Download: ML20054B288 (11)


Text

-

OPERATING DATA REPORT DOCKET NO.

80.297 DATE 4-9-P/

COMPLETED BY s tri.coog TELEPHONE 3a2-7 Wi g yy G x r.. % 3 OPERATING S TATUS Elon On IT !

1. Unit Name:
2. Reporting Period': C CO 8/0301
  • d'/OO 8/033/
3. Licensed Thermal Power (MWt):

DW

4. Nameplate Rating (Gross MWe):

/b d

5. Design Electrical Rating (Net MWe):

/OVO

6. Maximum Dependable Capacity (Gross MWe):

/D N

7. Maximum Dependable Capacity (Net MWe):

/OYO

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

41/4

9. Power Level To Which Restricted,if Any (Net MWe):

^)/A

10. Reasons For Restrictions,If Any:

A> l A-

.5iae con,mercwC.

eperA.-He rm a 2 -3 f 23 This Month Yr.-to.Date Cumulative

11. Hours In Reporting Period N

A /(00 61 Sfd

12. Number Of Hours Reactor Was Critical O

W/.3 vv. N3. 6 J[/o 2 /. 8

13. Reactor Reserve Shutdown Hours O

O

14. Hours Generator On.Line O

290.8 W 5905"

15. Unit Reserve Shutdown Hours O

o

'o

16. Gross Thermal Energy Generated (MWH)

O 990.3n 7

/ 2 7. c.?o f r 2-

17. Gross Electrical Energy Generated (MWH) 0 29N;990 4Ci % 2 j~ aW
18. Net Electrical Energy Generated (MWH)

O 4 7 7 7 ro ai.1 %,Rs7

'A. 6

19. Unit Sersice Factor O

/f f

/

20. Unit Availability Factor O

IX.f

(.e f. G

21. Unit Capacity Factor (Using MDC Net)

O

/J '/

Wo. '/

22. Unit Capacity Factor (Using DER Net) o

/AN S(o V i

23. Unit Forced Outage Rate a.O s.0 fA,9 j
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

l xJla

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

4l77/d M ; A 8/

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY Alh INITIAL ELECTRICITY COMMERCIA L OPER ATION 8204160459 810409 l

PDR ADOCK 05000295 I'#lI7 I R

PDR L

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

80 29f UNIT SIC" Mo $ r /

DATE 4-9-9/

COMPLETED BY I M- (con TELEPilONE 3/J-7We -JC# V E17543 MONTH M4PC /I /98/

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe. Net)

C/

-Y 17 1

~5 18

-Y 2

-Y

~5 19 3

-Y

-3 20 4

-4 J

21 s

-3

'/

22 6

~9

-5 23 7

-4

-Y 14 8

-Y 5

25 "b

"5 26 10

-5 27

-7 f

II l

-6 5

28 l

12

~7

~

13 29

-7

~5 30 I4

-V

-7 3i is

~5 16 INSTRUCTIONS On this format,hst the average daily unit power levelin MWe Net for each day in the reporting month. Compute to f

the nearest whole megawatt.

i i

(9/77) l

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

80 <24 f UNIT N AME R io n U n l'r* I DATE

'/ J' f COMPLETED BY 1M CecE REPORT MONTH /M A eM 192 /

TELEPHONE 3 'O 7(/G - 2 ck 'l

&+ 36,3 "i

-g" s -me

.=E _

E

,E4 Licensee 54 c.

Cause & Corrective No.

Date g

3g g

jg5 Event

??

S."E Action to

$5 5

j di j Report c

$0 0

Prevent Recurrence 5

l 9/030I

.5 JW.o C-1 A],

gjjA p)p

[On %vMie n o $ [t/Cle'V-S Re 4v elih o-1 I

2 3

4 F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram.

Entsy Sheets for Licensee C-Refueling 3-Automatic Scram.

Event ReporI(LER) File (NUREG-D-Regulatory Restriction 4-01her (Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5

Goperational Error (Explain)

Exhibit 1 - Same Source (9/77)

Il-Other (Explain)

I

OPERATING DATA REPORT DOCKET NO.

60dOY DATE 4-9.PL COMPLETED BY _3./77. acu TELEPilONE 3 /0 '>Wo c)c3 '/

OPERATING STATUS b /o A 8 O n T d

1. Urdt Name:
2. Reporting Period': mon //034/ m dyon f/033 /
3. Licensed Thermal Power (MWt):

23Cd

4. Nameplate Rating (Gross MWe):

/o K

5. Design Electrical Rating (Net MWe):

/oUO

6. Maximum Dependable Capacity (Gross MWe):

/08 I

7. Maximum Dependable Capacity (Net MWe):

/0YO

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

a/A o

9. Power Level To Which Restricted lf Any(Net MWe):

x> /A

10. Reasons For Restrictions. If Any:

Al,/A

.5tHCE cygEec/AL U

/

This Month Yr to.Date mutative NY d. / (a O SA 4 /,[

I1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical M Cl. D 25/SO 3 4'/ '8 '/lo. a

~'

13. Reactor Reserve Shutdown Hours O

o b o,. /

14. Hours Generator On.Line 7 4 I

'l d, / V7. 9 4 0 #/,. 6 2

15. Unit Reserve Shutdown Hours O

O

'C I6. Gross Thermal Energy Generated (MWH)

d. /d 3, 9 /0

/> A D9. 4 / '7

///o 3/9.OCle

17. Gross Electrical Energy Generated (MWH)

/olo 9,, t 7 O

),' 9 f D, (c o f

_'2 *f.J 36'r 39 O lo /O. 79 I il 8 9 O. 8 W

_S. 5'. M ~I./(o f C

18. Net Electrical Energy Generated (MWH)
19. Unit Service Factor 47.0

'99.d 91.E'

20. Unit Availability Factor 9 t. O 94.O 71.3
21. Unit Capacity Factor (Using MDC Net)

E2 8 7 h. '.>

59M

22. Unit Capacity Factor (Using DER Net) 3A 8 D.3

.5 0). 4

23. Unit Forced Outage Rate

.3. C)

1. O

/ G. '7

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):

0t'StHLll'bm Sr Nt& If k Cor % wher 1% I% I Ee ntn $ richol 4hl eLia k vb 4R WL 1 it '

I d

+

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

^/ 4

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

Forecast Achiesed INITI A L CRITICA LITY INITIAL ELECTRICITY N%

COMMERCIAL OPERATION (9/77)

AVERAGE DAILY UNIT POWER LEVEL 0 O - ?> O '/

DOCKET NO.

UNIT E Io n d o I-T 1 DATE N-9-P/

COMPLETED BY 7/Y7fodd T ELEPIIONE 3 M -7 W e 3 0 8'/

E x v.3& B MONT11 A7A OCN

/98l DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe-Net)

  1. 7/

899 i7 i

909 900 is 2

R 9 #7 S Olo 19 3-E9t/

9 08 20 4

900 560 2

5 89V 691 22 6

904 90b 23 7

909 893 24 8

9/O 880 25 9

EM b 90h 26 10 k dle 38 A 27 11 SQ(D S[D $

28 12 N) 908 2,

13 9/O h00 30 14 l

79 5 Nb 31 15 hN 16 i

INSTRUCTIONS On this format,hst the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

l (9/77)

(

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-JoV UNIT N AME 2/oM UniTd DATE

'/ 91 COMPLETED BY

'T M Ceof REPORT MONTH /DA #cM 198 /

TELEPHONE 31J -7We-JC6*(/

Ext.3co3 "L

j.a 2 E

=

ce Licensee g,,,

ge,,

c,,,, g co,,,c, j,,

No.

Date El.

k_$

5 3g3 Event g,7 ag gy,,,,,,

II E O

E3e gmj Report #

in u o

Prevent Recurrence oO E

c5

/

8/D W F

II 2-A 3

uIA AIa ala

%e.s-l-rv < bine. + r;p Som ac. sna n ge.nva:to< 1-ow Low Le ve ( clu<_ -to s a 6 freew a 4er comp + rip.

Rea.clor }-fit bsne Nes p Emm 2

el03Il F

10 3 p

3 yl^

N)R

"]n con 4ractor c utG V -rfrorgy L ca6/c cAv5sn6- /oss of feeewa.+er eum ps Resou'n&-

low - low leve I +ri e in

',n

~' C '.s te n ~ cre ne rMen i

2 3

4 F: Forced Reason:

Method:

Exlubit G -Instructions S: Scheduled A Equipment Failure (Explain)

I-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event ReporI(LER) File (NURI:G-D-Regulatory Restriction 4-Other (Explain) 0161)

EOperator Training & Ucense Examination F Administrative 5

G. Operational Error (Explain)

Estubit I - Same Source (il/77)

IIOther(Explain)

I

O I

SUMMARY

OF OPERATING EXPERIENCE UNIT 1 The Unit entered the reporting period shutdown for the continuation of the Cycle V-VI scheduled refueling.

UNIT 2 The Unit entered the reporting period at a power level of' 940 MWe (92% reactor power).

On March 5th at 1533 l

hours a reactor / turbine trip occurred from 2C steam l

generator low-low level due to a 2B feedwater pump trip.

At 2006 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.63283e-4 months <br /> the Unit was made critical and on March 6th at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> was synchronized to the grid.

On March lith at 0813 hours0.00941 days <br />0.226 hours <br />0.00134 weeks <br />3.093465e-4 months <br /> a reactor / turbine trip occurred from a contractor cutting through a cable causing loss of feedwater pumps resulting in low-low level trip in "C"

steam generator.

The Unit was made critical at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> and at 1909 hours0.0221 days <br />0.53 hours <br />0.00316 weeks <br />7.263745e-4 months <br /> was synchronized to the grid.

The Unit remained on-line the remainder of the reporting period having an Availability Factor of 97.0% and a Capacity Factor of 82.9.

The Unit ended the month on-line at a power level of 940 MWe (91% Reactor Power).

4 --

s

-e n

-,-------w

+,

MARCH MAJOR SAFETY RELATED MAINTENANCE Equipment Name Work Done U-l Containment Installed PT-CS50 & PT-CSS 1 U-l Containment Installed a wide range contain-ment level system U-l Reactor IIcad Vent Installed the mechanical part of a Reactor Head Venting System U-l Power Relief Rewire Valve Isolation Valve U-l RCS Wide Range Replaced transmitter pressure transmitter 403 and 405

Page 1 of 3 REFUELING INFORM /sTION REQUEST Questions:

1.

Name of facility.

2.

Scheduled date for next refueling shutdown.

3.

Scheduled date for restart following refueling.

4.

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

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59) ?

If no such review has taken place, when is it scheduled?

5.

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

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.

7.

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

8.

The present licensed spent fuel pool storage capacity I

and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

{

1 i

4

Page 2 of 3 Unit 1 - Answers 1.

Zion Unit 1.

2.

January 15, 1981, was the starting date for the refuel-ing outage.

3.

April 13, 198L is the scheduled date for initial criticality following refueling.

4.

The reload fuel design and core configuration has undergone On-Site Review.

There are no unreviewed safety questions or Tech. Spec'. changes, therefore, the reload will be done under a 50.59 submittal.

The Off-Site Review is completed.

5.

If the need for Technical Specification changes or other license amendments arise from the review in 4 above, then November 1,1980, will be the schedul-ed date for submitting the required information.

D 6.

No important licensing considerations are anticipated

..,,^* 4 with this refueling.

7.

The number of fuel assemblies a) in the core is 193, and b) in the spent fuel storage pool, which have been discharged from Zion Unit 1, is 308~.

8.

The present licensed spent fuel pool storage capacity (shared with Zion Unit 2) is 2112 fuel assemblies.

The installation of the new storage racks is presently oc-curring.

9.

October, 1992, is the projected date of the last Zion Unit 1 refueling which can be discharged to the spent fuel pool assuming the present licensed capacity.

i w-

Page 3 of 3 Unit 2 - Answers 1.

Zion Unit 2 2.

September 13, 1981,is the scheduled date for the next refueling outage.

3.

November 8, 1981,is the scheduled date for initial criticality following refueling.

4.

The reload fuel design and core configuration has not undergone On-Site and Off-Site Review.

However, no Technical Specification changes or license amendments are anticipated.

The On-Site and Off-Site review of the Cycle VI fuel design and core configuration is currently scheduled for completion by July 15, 1981.

5.

If the need for Technical Specification changes or other license amendments arise from the review in 4 above, then August 1, 1981,will be the scheduled date for submitting the required information.

6.

No important licensing considerations are antic 7ated 4

with this refueling.

7.

The number of fuel assemblies

~-:

a) in the core is 193, and b) in the spent fuel storage pool which have been discharged by Zion Unit 2 is 260 8.

The present licensed spent fuel pool storage capacity j

(shared with Zion Unit 1) is 2112 fuel assemblies.

The installation of the new storage racks is presently I

occurring.

(

9.

October, 1992,is the projected date of the last Zion l

Unit 2 refueling, which can be discharged to the spent fuel pool assuming the present licensed capacity, l

l