ML20067D201

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Monthly Operating Rept for Dec 1990 for Jm Farley Nuclear Plant Unit 2
ML20067D201
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 12/31/1990
From: Dennis Morey
ALABAMA POWER CO.
To:
Shared Package
ML20067D189 List:
References
NUDOCS 9102120384
Download: ML20067D201 (4)


Text

'

JOSEPH H. FARLEY NUCLEAR PLANT UNIT 2 NARRATIVE

SUMMARY

OF OPERATIONS December, 1990 The cycle 7 - 8 refueling outage continued through the month of December.

On 12-31-90, during plant heat-up and pressurization in Mode 3, pressurizer power operated relief valve (PORV) 445A opened. Reactor coolant system (RCS) pressure was increasing slowly in a controlled manner and RCS pressure and temperature vere in the normal range. The RCS pressure vas approximately 1730 psig vhen the PORV opened, The PORV block valve vas closed immediately, isolating the PORV, and the RCS pressure was quickly restored. Normal setpoint for opening the PORV is 2335 psig. The cause of this event was improper setup of the air operated actuator. The PORV vas repaired and returned to service on 1-2-91.

The following major safety-related maintenance was performed in the month of December:

1. The 120V vital AC inverters were replaced.
2. Replaced some of the carbon steel service water piping with stainless steel.
3. Replaced the positioner on motor driven auxiliary feedvater flow control valves.
4. Hiscellaneous corrective and preventive maintenance was performed on numerous safety related valves.
5. 303 previously plugged steam generator tubes were unplugged and 574 additional tubes vere plugged.

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,' OPERATING DATA REPORT 9

DOCKET No. 50-364 DATE January 8, 1991 COMPLETED BY D. N. Morey TELEPHONE (205)899-5156 OPERATING STATUS Notes

1. Unit Name Joseph H. Farley - Unit 2 1) Cumulative data since

'2. Reporting Period: December 1990 7-30-81, date of

3. Licensed Thermal Power (HVt): 2,652 commercial operation.
4. Nameplate Rating (Gross HVe): 860
5. Design Electrical Rating (Net HVe): 829
6. Maximum Dependable Capacity (Gross HVe): 868.6
7. Maximum Dependable Capacity (Net HVe): 828.2
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A
9. Fbver Level To Vhich Restricted, If Any (Net HVe): N/A
10. Reasons For Restrictions, If Any: N/A This Month Tr-to-Date Cumulative
11. Hours In Reporting Period 744 8,760 82,609
12. Number Of Hours Reactor Vas Critical 0.0 6,55TTI 70,384.2
3. Reactor Reserve Shutdovn Hours 0.0 0.0 ~

138.0

14. Hours Generator On-Line 0.0 6,479.2 --- 69,551.2
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (HVH) 0.0 ~

16,947,682 177,203,949

17. Gross Electrical Er.ergy Generated (MVH) 50 5,539,414- 58,205,956
18. Net Electrical Energy Gsnerated (HVH) -9,388 5,250,732 55,194,122
19. Unit 9ervice Factor 0.0 74.0 84.2
20. Unit Availability Factor 0.0 74.0 84.2
21. Unit Capacity Factor (Using HDC Net) N/A 72.4 81.6
22. Unit Capacity Factor (Using DER Nat) N/A 72.3 80.6-
23. Unit Forced Outage Rate 0.0 1.4 4.2
24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):

N/A

25. If Shut Down At End Of Repor't Period, Estimated Date of Startup: January 6, 1991
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY 05/06/81 05/08/81 INITIAL ELECTRICITY 05/24/81 05/25/81 C0HMERCIAL OPERATION 08/01/81 07/30/81 Form 2/30

n DOCKET NO. 50-364-

"1 UNIT 2 i DATE January 8, 1991 COMPLETED BY D. N. Morey

. TELEPHONE (205)899'-5156 MONTH December DAY ~ AVERAGE DAILY POVER LEVEL DAY AVERAGE DAILY POWER LEVEL

(

._HWe-Net)- -(MVe-Net) i

'l -O' 17- 0

-2' O 18 0 ,

3. "0: 19 0  !

4 -O- 20 0 l 5 0= 21 0 6' O 22 JO l

MO- 23 -O- ,

81 -O 24 0 ,

e

9- 0 25 0 j 10-0 26: 0 11 0 ,

27 0-t

12: 0 28 _,

LO-13- 0i 29 0 14 0- 30 0

.15 - 0- 31 0 l-.-

16- 0 INSTRUCTIONS- <

[

p On this format, list the average daily unit power-level'in HVe-Net for each day in the:reportinc r: nth. Compute to the nearest whole megawatt.

p ' Form 13/21

=

1 , , - , ,----.

' tEf!T SNtF1130RGIS AIED FOIER EEDUCTICEIS DOCIET 3D. .. '50-364' -

tat!T IWWE J. C. FAEf2Y - F - ~2 Ilfttt Jesunary 8, '1991 ' *; - -

COMPL2TED 57 D. N. St]EtET .

EEFORT ftETT1E IIECIPERER TE12FIIOUIE (295)S99-5156 I I I I I- I ser== or - l::cEnsEE 1  ! I oosE s' co ecrrvE l-I I I 2

InumATrom i 2

I snurrrm l Evorr I srs= 1 awa=wr . I

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5 xTron io 1 Im. IDm- ITrrs .!(munS) I mEAson - 1 ix== mrum' ImErowre I cair* l c=E i r Emr mEcissena l l004 l901201 l s l144 l c l' 1 l N/A l.N/A l N/A- l The cycle 7-8 refueling cutage ' continued from - l l 1 1 I I -l 1 1 -l l*01012. 1 I I I' I I I .I l- 1 I I I I I l- 1 I I I I I I I i l. I I I I l' I I I I .I I I I I I I I I I I I I I I I I I I I i i i  ! -1 1 I 'l I i i i l I 'l i I I I I ~

I I I I I I I I I I I l l I I I I I I I I I i

, I I I I I I I I :l l l l 1 l l l l I I I I I I I I I I I I i 1. I I I i 1 I l- 1 I I I t i I I I I i l 1 1 I I i i I I I I I I I I I I I I l I .I' I I I i I I I I i i l' I I I I I I I I I i l 1 1 I I I I i i i I i l l I I I I i 8 l l i I I I I I I

F: Forced Reasott: Method; Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual. for Preparation of Data IHtaintenance or Test 2-flanual scram. Entry sheets for I.icensee C-Re*ueling- 3-Automatic Scram. Event Report (125t) File (IEUREG-tHtegulatory Restriction ' 4-other (Emplain) 0161)

Examrator Training & 1.icense Examination F-Administrative Exhibit 2 -Same Source G-operational Error (tzplaint H-other (Explsin)

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