ML19344B527

From kanterella
Revision as of 06:59, 31 January 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Monthly Operating Rept for Sept 1980
ML19344B527
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 10/10/1980
From: Underwood P
GEORGIA POWER CO.
To:
Shared Package
ML19344B526 List:
References
NUDOCS 8010210414
Download: ML19344B527 (7)


Text

- _ _ _ _ - - . _ _ _ _ ________

EO -

OPERATING DATA REPORT .

DOCKET NO. 50-366 DATE 10-1C-80 CO3tPLETED BY P. R. l nderwood TELEPHONZ 912-367- 7781 .

OPERATING STATUS

~

1. Unit Name: Hatch 2 Note 5
2. Reporting Period: 9-80
3. Licensed Thermal Power (5 twt): 2436
4. Nameplate Rating (Gross Athel: 817.0
5. Design Electrical Rating (Net StWe): 784.0 ,
6. Staximum Dependable Capacity (Gross 31We): - 805.7
7. 31aximum Dependab!e Capacity (Net StWe): 772.7
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
9. Power Lesel To Which Restricted. If Any (Net 31We): j
10. Reasons For Restrictions. If Any: g i

This Sionth Yr. to.Date Cumulatise 4 1

Ja '

!!. Hours In Reporting Period 720 6575 94.08 ,

12. Number Of Hours R- 3r Was Critical 660.2 4850.1 7513.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On.Line 636.0 4573.3 6987.9  !
15. Umt Reserve Shutdown Hours 0.0 0.0 0.0 4 16. Gross Thermal Energy Generated (SIWH) 1467666 10106760 15600822
17. Gross Electrical Energy Generated (31WHI 480630 _ _ ,

3347360 5183450 '

18. Net Electrical Energy Generated (StWH) 458908 3189477 4946614
19. Unit Service Factor 88.3 69.6 74.3
20. Unit Availability Factor 88.3 69:6 74.3
21. Unit Capacity Factor (Using 3tDC Net) 82.5 62.8 68.0
22. Unit Capacity FactorIUsing DER Net) 81.3 61.9 67.1 .
23. Unit Forced Ourage Rate 11.7 13.2 12.3
24. Shutdowns Scheduled Oser Next 6 StonthsIType. Date,and Duration of Eacht: ,

conmling and torus work.11-1-80.13 wks.

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

' 26. Units in Test Status (Prior to Commercial Operationi: Forecast Achiesed INITIA L CRITICALITY 1 INITIAL ELECTRICITY

. C0115tERCIA L OPER ATION i

.. . gof7 7 3

2. ,

8010310 Yl4

i e i'

I t

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-366 UNIT 1 Hatch 2 DATE 10-80 .

COMPLETED BY. P. R. Underwood TELEPHONE 912-367-7781 k2 -MONTH Q-Rn -

l l DAY  : AVERAGE DAILY POWER LEVEL DAY *

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

I 768 17 765 2- 767 18 762 3 763 .l9 757 4 760 20 750 5 760 21 749 6 757 755 l 22 7 757 754 23 8 393 ~ 24 760 j 9 -15 25 757 10 707 26- 748 11 577 27 - 746 l*' 12 709 28 708 _

13 738 29- -2 14 . 663 30 -7

, 15 759 3g 16 762-l-

INSTRUCTIONS On this format. list the aserage daily umt power level in MWe-Net for each day in the reporting month. Compute to

'.the nearest whole megawatt.

eu;;i L.

~

I ' .. (

.s

'~ A.

p_ ._

DOCKET NO.

50-366 UNIT SilUTDOWNS AND POWER REDUC 110NS UNIT NAME . Hatch 2

  • DATE 10-10-80 COMPLETED BY P. R. Undensood REPORT MONT11 9-80 TELEPil0NE 91P-367-7781

- i 5 Cause & Corrective

- ,$E ' g' *Y3 Licensee Eg gn.

Action to No. Date h 78 il 4

3s& Event U mu Q g Prevent Recurrence H

$$ j ;ji E Report #

f +

l CD VALV0P Rx auto scram due to MSIV not fully l l 80-34 800908 F 40.3 A 3 NA open i.

' 1 Unit on startup ramp from above shut- }

5 NA CD VALV0P 80-35 800909 F 38.0 A down, #80-34  !

3 2 l

llE TURBIN Reduced load in order to perform f 800913 7.0 8 5 NA

.; 80-36 S weekly turbine test

'l Reduced load due to high cot:.ductivity j 80-37 800928 F 4.5 A 5 80-135 HC llTEXCH 43.7 A 3 NA ilC llTEXCil Rx scramdue to low condenser vacuum ,

80-38 800929 F 5 NA ilC HTEXCil Unit on startup ramp from ab3ve shut- 1 80-39 800930 F 2.3 A down #80-38 {

-l

i 3 4 g I 2 Exhibit G - Instructions Renon Method:

F: Forced 1 Manual for Pseparation of Data s A. Equi ment Failure (Explain)

S: Scheduled 2-Manual Scram. Entry Sheels for Licensee B. Maintenance of Test Event ReposI (LERI File (NUREG-C Refueling 3 Automatic Scram.

4 -Continuations 0161)

D-Regulatory Restriction E Operator Training & License Examination 5-Ioad Ibcluction 5 F-Administrative 9-Other (Explain) Exhibit 1 Same Source G-Operational Error (Emplain) -

I 11Other (Emplain)

(9/77)

'i -

)

a ,

e, 4 ,

NARRATIVE REPORT UNIT 2 Sept. 8th Rx. auto scram at 12:55 due to a MSIV being not

' fully open; inboard MSIV "D" was found to have a blown slave vlinder gasket Sept. 9th Startup from.above shutdown, #80-34; Rx critical at 21:00-and generator on line at 05:13 on Sept.

10th; unit returned to 80% conditions at 19:15 on Sept. lith Sept 13th Reduced load in order to perform weekly turbine tests; unit returned to 80% conditions at 05:45 on Sept. 14th Sept. 28th Reduced load due'to high c ,r. e u c t i v i t y ; conducti-vity due to a tube failure in watertrap "D" Sept. 29th' Rx auto scram at 01:59 due to law. condenser vacuum; low vacuum due to reduction of load stated above, #80-37 Sept. 30th Startup from above shutdown, #80-38; Rx. critical at 05:40 and generator on line at 21:43; unit ,

had not returned to 80% conditions as of 24:00 r ,

There was no single release of radioactivity or single radiation exposure which accounts for more than 10% of the allowable annual values during August of 1980.

- *9 i

l l

E s .

j

=  !

l

[E _ :1 h-a- A- a - - -e

c L

I

  • HATCH ~2 SAFETY - RELATED MAINTENANCE REQUESTS TO BE REPORTED.FOR SEPTEMBER 1980 l

NUMBER DATE COMPLETED DESCRIPTION E730 d - 2 Fo 6~~ CRD HCU Ele t needle valve was i

out of-adjustment; adjusted valve l and verified operation 80-3306 8-25-80 LPRM channel "B" low ' voltage l_ power supply failed to function properly; replaced power supply

, g with new I and calibrated 80-3336 8-25-80 Condensate flush valve for WSPs "B" mix pump stroke was too long causing valve to stick closed; repaired by shortening. valve stroke 80-3387 8-31-80 Found loose wire on starter in breaker controlling RHR/SW heat exch disch "B" loop valve; reconnected wire

80-2538 7-23-80. Replaced pipe between isolation l

valve 2Pil-F025B and mating flange for bellows

( 80-3361 8-28-80 Drywell torus temp indicator recorder step advance was not working; replaced logic switch board and reset clock

80-3285 8-29-80 RWCU "A" holding pump was leaking

' M around seal; replaced bearing and mech seal 80-3353 8-27-80 Replaced internal parts of

reactor vessel level recorder because of sticking; recalibrated' l

recorder after repairing it l

80-3391 .8-29-80 HPCI booster pump and main- pump seal water- line's were leaking; replaced 4 nipples on seal water lines

'80-3183 8-29-80 Replace _d - fuel filter on 2C diesel because of high d/p 80-3439 9-3-80 Replaced . post 'and gear assembly in Rx vessel temperature recorder because they were stack

-- t e ,

________N.

80-3392 8-30-80 Replaced point card alarm in decon sul conc 'Gil-D069 hi conductivity alarm because unit did not function properly 80-3427 9-3-80 Adjusted snap switches on recombiner temp-hi/ low alarm ,

80-3537- 9-10-80 INBD MSIV 4-way air operator valve- gasket was found blown; replaced gasket and DC coil on pilot solenoid y'

80-3544 9-9-80 Removed strongbacks on drywell airlock doors 80-3521 9-14-80 Replaced log outpu. module on turb bldg "B: equip drain sump pump; replaced logic module because pump had failed t o_ start properly 80-1873 9-10-80 Control rod notch position switch 18 failed; replaced RPIS probe 80-3588 9-12-80 CRD HCU accum pressure switch was found out of tolerance; adjusted setpoint for proper tolerance

.80-3524 9-12-80 WSPS "A" upper and lower s u c t iern s valves were not functioning '

properly; replaced faulty manual override relay 80-3438 9-11-80 Replaced fuel line check valve on n D/G 2C 80-3033 .8-20-80 Checked level switch operation on 2C11-N013A and 2Cll-N013D; found their floats were crushed; later replaced by MRs 3055 and 3056 80-3136 8-12-80 Replaced logic board in TIP machine B because bottom limit index and core bottom l imi t incore switch were not consistent 80-3523- 9-9-80 Filter precoat flow indicator was not functioning properly; replaced pointer assembly and calibrated indicator

80-2309 9-18-80 CRD_ cooling water pressure control vave was found leaking around 'the packing; valve packing was tightened to stop leak g

.5 l f[__- 4.. w . + u . A - w. i - - ~ -- - - -

V er 80-3624 '9-17-80 Repaired 3. inverter legs and 2 firing gates of- the security

, inverter

~

80-3610 9-18-80 RCIC inlet drain pot isolation valve was found leaking around the packing; adjusted packing to stop leaking 80-3546 9-19-80 PSW A0V to- see cooler was not operating properly; cleaned sol valve to correct q- 80-2817- 9-18-80 Calibrated shutdown flooding Rx H2 level' indies. tor 80-2249 9-18-80 Replaced strain 8 auge which is connected to the post accident.

monitoring system recorders i

4 B

9 4

S i.

F 4 i '.h :

M . a .x . . . - . - -