ML19347B553

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Sept 1980
ML19347B553
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 10/08/1980
From: Ballentine J, Dupree D
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19347B551 List:
References
NUDOCS 8010150330
Download: ML19347B553 (9)
v • d • e


Text

_ _ _ _ -_

V .

TENNESSEE VALLEY AUTif0RITY DIVISION OF NUCLEAR POWER SEQUOYAll NUCLEAR PLANT

!!ONTHLY OPERATING REPORT SEPTE!!BER 1, 1980 - SEPTE?!BER 30, 1980 l

l DOCKET NL?!BER 50-327 LICENSE nut!BER DPR-77 f

(

)

I Submitted By:

\

CPlant h Ch Q Qhnute

[

7 flanager 8010150 33D

{

1 TABLE OF CONTENTS l Operations Sununary . . . . . . . . . . . . . . . . . . . . . . . .1 Significant Operational Events . . . . . . . . . . . . . . . . . . . .2 l Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . .3 1

l Operating Data Report . . . . . . . . . . . . . . . . . . . .4 Unit Shutdown and Power Reduction . . . . . . . . . . . . . . .5 t

Plant Maintenance Summary . . . . . . . . . . . . . . .6 Outage Maintenance Summary . . . . . . . . . . . . . . . 7 i

l l

I 1

.m.. _ _ _. _

l l

l Operations Summary September 1980 The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.

There were eight Licensee Event Reports and two Special Reports, 80-4, ECCS injection to RCS (mode 3) and 80-5, fire protection system inoperable, mechanical equipment room, EL-732.

There were no scrams during September.

NRC approved full power license on September 17, 1980 for Unit 1. Unit I went into mode 4 on September 26, 1980 in preparation for full power opera-tional testing. Unit I was critical at 0450 September 30, 1980. At the end of September the reactor was in mode 2.

I l

I l l

t I

l t

l I

i l

I I

l l l

1 l

1 i

1

Significant Operational Events Date Time Event i 9/01/80 0001 Unit 1 in mode 5.

9/13/80 0415 Water was found in the annulus as a result of vent valves67-688 A & C being found open. The vent valves were isolated and VIV-67-531 was found open when it should have been closed. The water was drained to the passive sump.

9/15/80 0830 Began pressurizer heat-up.

9/23/80 2325 Tripped control bank D in from 5 steps for STEAR 18.

9/23/80 2330 Reconnected shutdown oanks A, B, C, and D and control banks A, B, and C.

9/24/80 1648 Decreased RCS temperature and pressure to work on a pressure transmitter on top of the pressurizer.

9/26/80 1327 Entered mode 4.

9/29/80 1020 Entered mode 3.

9/29/80 1305 Began withdrawal of shutdown banks.

9'29/30 1321 Withdrawal of shutdown banks complete.

9/30/80 0407 Began pulling control rods.

9/30/80 0450 Reactor critical.

9/30/80 0510 Tavg = 546 F 9/30/80 0621 Entered mode 2; Tavg = 547 F @ 2235 psi 2

l

. l i

AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO. 50-327 UNIT 1 DATE 9-30-80 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 MONTH September l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) 1 1 0 77 0 2 0 18 0 3 0 19 0 l

l 4 0 20 0 5 0 21 0 l

l 6 . 0 22 0 7 0 0 23 8 0 24 0 9 0 0 25 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0

(

14 0 30 0 15 0 31 N/A 16 0 l INSTRUCTIONS l

l l

On this format, list the average daily unit power level in MWe-Net for each day 2.n the reporting month. Compute to the nearest whole megawatt.

(9/77) 3

O OPERATING DATA REPORT DOCKET N0. 50-327 DATE Septer.ber, 1980 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 OPERATING STATUS

1. Unit Name: Sequoyah 1 Notes
2. Reporting Period: September, 1980
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Ratind (Gross MWe): 1220.5
5. Design Electrical Rating (Net MWe): 1145
6. Maximum Dependable Capacity (Gross MWe): lib)
7. Maximum Dependable Capacity (New MWe): 1148
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (New MWe):

l

10. Reasons For Restrictions, If Any:

This Month Yr-to-Date Cumulative l

l 11. Hours in Reporting Period 720 5136 5136

12. Number of Hours Reactor Was Critical 19.1o 34Z 3-4
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generatcr On-Line 0 15.33 1c.33 l 15. Unit Reserve Shutdown Hours 0 0 0 l 16. Gross Thermal Energy Generated (MWH) 10517.249 39359.509 39359.3u9 l 17. Gross Electrical Energy Generated (MWH) 0 230 230 l
18. Net Electrical Energy Generated (MWF.) N/A N/A N/A
19. Unit Service Factor N/A N/A N/A l 20. Unit Availability Factor N/A N/A N/A l 21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A ,

i 22. Unit Capacity Factor (Using DER Net) N/A N/A N/A i

23. Unit Forced Outage Rate N/A N/A N/A l 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

l l

l 25. If Shut Do,a At End Of Report Period, Estimated Date of Startup:

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

Forecast Achieved INITIAL CRITICALITY 07-05-50 INITIAL ELECTRICITY v/-zz-e0 COMMERCIAL OPERATION 11-vo-cU (9/77) 4

_.m. .._.._m . ._ _m. . _ _ . . _ . _ . _ . _. . - _ _ _ . _ . _ . . __ ,

l C C/: M '

  • I N . . I Z 8

C '

( N N th !* e i 8

! v c C '

m i

C h '

OC ' '

O L I C ' O 8

4 L ,

t e I

C I

I t l M 8' Z. iOMMOOW>%

e i i e i e C l i

' Type 1 '

oO>c===Mc 8 r *: at C C O .: m '

"C 5 3 Oc m-C C C 9 M O C O == 0 ' I 9 C

- er*s'*: =

0 -C f

& -- e0 ' Duration r 8

m=. m C e -= C MC e 9 C = c=

x m M 00 = r*

8

' (Hours) i 8

  • G C -4 '< n b

~ = r* m C m t b w- L x e i 2

-m<-O -- ' Reason

,C - i

= mC =.

v, - r- e = i 0

5 *2. p2 i Method of  !

- 3 '. m l Shutting

? E p l Down Reactor 3

  • -= *:.- a e

- e L C L i .z.

l g y ai e c -

v C v g - gn 2 tn

' X < r M =

" .(.'; 4 m M ' C

x. . i rt - ". v .o ..i E

I e r N C C

C -

3,

= ' a :d 6 . O V.

<* =

C y *4

=

Z System

= p e Code 4

(* --

l

  • C W

j  % C bi .W N.i -2 C , , M

c

{

C > 2 2 c- g 5

." r* .E. h O7 Component 5- *C r

g C (;

N =E: G .E - * *c-i Code 5 .

, gg w

g L - g C

^ *

  • e Q M

M - to , e w

  • xnd , m O "O

- th L N g g

o :2:

C O E  : Ch

w. m . g O k g f

v5

  • g  !

I i e

O t

O "

,e 5 (") 3 V d M e

L

=

HT Cb zO m M :-

x .emmmm

< 0 C x s

C C

"' M MH

    • 3'
  • i M

=* CS C f* 9 =" g

-- - = *1 w. g O > 't M af O' v r 54 *" C" g f* O Ch =CCZ

-- m -- , f* C > gZ r- :c to C t- , :C O ZtrH O C ::- *: g C C C M *< MMe w 'O f: c O g a 9 i O C 9 4 g C 9 th R t'* C me g *1 r* C I G e we g R C n

  • 2 w- V C f*

C A **t C f*

g g O "* '

r- C m e o <

Ch MM C e O O ^ C C  % C o e

  • Ch L V F M r** * . e .O* O M g V C* D V n m "n O c C e v = "osc o C -C e eto a "D f'* M 3 CD C NM W C V M g & C t D N C e M% @ 7 N

^ C s *1 C 2 g O C .d I C g N C

'C e %C M e V O I 8 e ,

t 8 e

Plant Maintenance Summary The following significant maintenance items were completed during the month of September,1980:

1. Reactor Coolant Pump i/4 runner seal replaced.
2. Fire Pump 1A-A motor replaced.
3. Replaced gaskets on RHR pumps IA-A and IB-B.
4. Repaired safety injection system check valve 1-63-635. Valve failed local leak rate test SI-166.6.
5. Repaired the interlocks on both the EL-690' and EL-734' airlock doors - Unit 1.
6. Balanced reactor coolant pump #4 after repairs.

I' I

i 6

Outage Maintenance Summary Continued to work on pipe hangers on safety related systems in accordance with IE Bulletin 79-14.

Work continued on the installation of addition of fire protection spray nozzels to the auxiliary building.

Completed the installation of the controlled hydrogen ignition system.

Two new ignitors were installed and four re-located.

__ . - - .

Retrieved from "https://kanterella.com/w/index.php?title=ML19347B553&oldid=2480114"