Text

Monthly Operating Rept for Apr 1989 for Davis-Beese Nuclear Power Station
	ML20247B522
Person / Time
Site:	Davis Besse
Issue date:	05/10/1989
From:	Sarsour B, Storz L; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	KB89-00248, KB89-248, NUDOCS 8905240152
	Download: ML20247B522 (6)
	v • d • e

_ _ _ _ _ _,. _-. _ _ _ _ _

[,*

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 L

. UNIT Davis-Besse #1 DATE May 10, 1989-

' COMPLETED BY Bilal Snranur TELEPHONE (419)'321-7384~

MONTH April 1989 DAY

. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) g 886 862 37 2

844*

18 759 3

882

.gg 149 4

'882 20 430 5'

084 877 21 l

6 885 22 886-7 885' 23 885 8'

884' 24 854

[

9-866 880 25 10 887 26 883' 11 885 27 883 12 884 2g 885 13 886 29 885 14 881 30 886 15-880 3;

16 881

Based on the average of 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months generation due to the time change.

INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting inonth. Compuie to the nearest whole rnegawati, to/77 i 8905240152 890510 C

PDR ADDCK 05000346 !C

{%

I R

PNU Q

g g

i

4 1

O OPERATING DATA REPORT DOCKET NO. 50-346 DATE May 10. 1989 COMPLETED BY B.11n1 Sarsour TELEPilONE (419) 121-7384 OPERATING STATUS

1. Unit Name:

Davis-Besse #1 Notes

. 2. Reporting Period:

April 1989

3. Licensed Thermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe):

925 S. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

918

7. Maximum Dependable Capacity (Net MWe):

874

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

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

10. Reasons For Restrictions.If Any:

I This Month Yr.-to-Date Cumulative P

11. Hours in Reporting Period 719 2,879.0 94,248

12. Number Of Hours Reactor Was Critical 719-2.681.3 4R.78R.8

13. Reactor Reserve Shutdown Hours 0.0 73.8 s.378.5

14. Hours Generator On-Line 719 2.660.2 46,354.0

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 1,890,726 7,151,760 109,021,149_

17. Gross Electrical Energy Generated (MWH) 633.996,_,

2.394.711 36.035.895

18. Net Electrical Energy Generated (MWH) 602,377 2,268,411

_33,733,463

19. Unit Service Factor 100.0 92.4 49.2

20. Unit Availability Factor 100.0 92.4 51.0

21. Unit Capacity Factor (Using MDC Net) 95.9 90.2 41.0

22. Unit Capacity Factor (Using DER Net) 92.5 87.0 39.5

23. Unit Forced Outage Rate 0.0 4.8 31.2

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

i

25. liShut Down'At End Of Report Period. Estimated Date of Startup:

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

Forecast Achiesed A

INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIA L OPER ATION I

(4/77)

e 9 e

a 3

a e8 S 7 m

s 9 l 1 o

s 1 e

a 2 t r r

6 n l

3 i

o a

4

-. i

)

d a f

t S

3 s 0 a

4 i s

ep L

)

0 v 1 t

y c e.

S a Y

(

e d

B a

I 4

f R n yB ur" r

o E O E aD E v

c N M ME N i

n eo6 m

n(

o n

T 0 t

e rt P m

i t T a E n c

r E

I P

e o r S

u t r a o R T E P z r t u s%"

S r p r

e a4 a e C I r M r O M a O E o n,

D u D C T c o a w2 e l s p R e

i v

al r t

& t t r yl ni P n c n e

e A e el a oa r v s

v wev i t o E u

e f

ot t e a

r e

C P

par ad s e me r

n s o n rit er i e oxa pe t c c i t ow Oh u L crd t

r

)

ape er t r 1 s o 6 e pe eu nf 1 R af Sf I

0 s -

- t G e E G e R h U t S N i

e b y

(

E i r e A

h t l y3

/

x n i N

E E F SN O

IT 9

CU 8

gu D

9

("g

/A E

1 R

N R

l m

E i

a W

r O

r m c P

p a S o D

A rc c t N

S i A

'a t

i e

e

l l S

m a a t.

d u r o t P W

t t o n et n u

n.

O n

r h a J

u D

e o

t M M A C f

t c v p e - - -

f T

i, E e M 1 2 3 4 F

I R

1 R

S O

A P

T E

/

I R

N N

J t

[jW I

$Yr A

/

y N

)n ia l

,8 j B

p x

E 4

(

ts e e r T u

l r

3$

0 i o 3

a 2

c F e t

n g r n a n o r e n i t o m e l

p t e l n i n u u r o u i f S

s q a e e p d p a E M R R e - - -

R A B C

8 o

1 e

4 t

0 d

a e

D l

9 d u 8

e d c e r h o c F S 3

F S o

N l

Operational Summary April, 1989 Reactor power was maintained at approximately 100% full power until 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months on April 9, 1989, when a manual power reduction to approximately 84% vas initiated to perform turbine stop valve and control valve testing. The turbine valve test was successfully completed at 0750 hours0.00868 days 0.208 hours 0.00124 weeks 2.85375e-4 months on April 9, 1989.

l Reactor power was slowly increased to approximately 92% which was attained at l

0919 hours0.0106 days 0.255 hours 0.00152 weeks 3.496795e-4 months on April 9, 1989.. Reactor power was maintained at this power level to perform Control Rod Drive (CRD) exercise testing.

After the completion of the CRD exercise testing, reactor power was slowly increased to approximately 100% at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months on April 9, 1989.

Reactor power was maintained at approximately 100% full power until 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on April 17, 1989, when a manual power reduction to approximately 95% vas initiated as a result of a main feedvater transient (sving).

Investigation revealed that the main feedvater sving was due to main feedvater control valve (SP6B) problem. As a result, a manual power reduction to approximately 24%

was initiated at 1632 hours0.0189 days 0.453 hours 0.0027 weeks 6.20976e-4 months on April 18, 1989 in order to repair SP6B. The valve was isolated, valve positioner was rebuilt and further testing revealed a leak in the air lockout valve to the actuator (HVSP6B1). This was rebuilt and the main valve was tested and response acceptable.

i At 1541 hours0.0178 days 0.428 hours 0.00255 weeks 5.863505e-4 months on April 19, 1989, a reactor power escalation to approximately 100% full power began. Reactor power was slowly increased to approximately 100% full power at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months on April 21, 1989.

Reactor power was maintained at approximately 100% full power until 1007 hours0.0117 days 0.28 hours 0.00167 weeks 3.831635e-4 months on April 24, 1989, when power was reduced to approximately 74% due to a dropped Control Rod (group 7, rod 7), caused by a blown fuse in "B" phase.

The fuse was replaced and reactor power was slowly increased to approximately 100% full power which was attained at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months on April 24, 1989 and maintained at this power level for the rest of the month.

l

O

- REFUELING INFORMATION Date: April 1989 1.

Name of facility:

Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? February 1990 3.

Scheduled date for restart from current refueling:

N/A 4.

Vill refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what in general vill 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)?

Ans: A license amendment request is planned to remove cycle-specific values from Section 3 of the Technical Specifications. This submittal is planned for June 1989 and will be based on Generic Letter 88-16.

Assuming approval of this submittal by November 1989, no Cycle 7 Technical Specification changes are expected for Section 3 of the Technical Specifications.

Cycle-specific changes to Section 2 of Technical Specifications vill likely be made. This depends on the date of approval of a document on criteria and methodology, which is presently under development by the B&V Owners Group.

5.

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

For Section 2, January, 1990.

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.

Sixty Batch Reload 3.61% enriched instead of 64 Batch Reload, a.

b.

New fuel design Mark B8 (Reconstitutable, removable upper end fitting, Zircaloy grid spacer, debris resistant lover end cap, lower prepressurization, and annealed guide tubes.

7.

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

(a) 177 (b) 268 (c) 0 8.

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

Present:

735 Increased size by: 0 (zero) 9.

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

Date:

1995 - assuming ability to unload the entire core into the spent fuel pool is maintained

i L

.=

L 4..

TOLECX)

EDISON -

EDISON PMZA -

3CO MADISON AVENUE TOLEDO, OHIO 43652-0001 May 10, 1989

-KB89-00248 Docket No. 50-346 License No. NPF-3 Document Control Desk U.. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda,.MD.

20555 Gentlemen:

-Monthly Operating Report, April, 1989 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten' copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No. I for the month of April, 1989.

If you have any questions, please contact Bilal Sarsour at (419).321-7384.

Very truly yours, jf' /q7

~'

/

-/

Louis F. Storz

. Plant Manager Davis-Besse Nuclear Power Station BMS/mj b Enclosures cci Mr. A. Bert Davis Regional Administrator, Region III Hr. Paul Byron NRC Resident Inspector l($I Mr. T. V. Wambach NRC Senior Project Manager

' \\

t

__1_____.___

_.

ML20247B522

Text

Navigation menu

Search