ML20062F628

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Forwards Corrected Pages to 8th Startup Rept Incl Module Main Steam Temp Trim Control,Load Change Response,Feedwater Flow Control & Deaerator Level Control
ML20062F628
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/15/1978
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-78202, NUDOCS 7812200164
Download: ML20062F628 (8)


Text

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$O~ W pubue service company *e concede P P. O. Box 361, Platteville, Colorado 80651 I

December 15, 1978 Fort St. VraAn - .

Unit No.1 -

P-78202 t Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 REF: Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find corrected pages to the eighth Startup Report for Fort St. Vrado. Nuclear Generating Station, Unit No.1.

Very truly yours, am. Don Warembourg Manager, Nuclear Production DW/alk cc: Director, I and E Director, MIPC O

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78122001gdY

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Part 16D - Th,rottle Pressure Control -

  • Data collected furing perforrmice of Part 16D is shown on Figures B-7.16D.1 through B-7.16D.S.

Part 17D - Module Main S team Ter:cerature Trim Control Data collected during performance of Part 17D is shown on Figures B-7.17D.1 through B-7.17D.S.

Parr 20F - Load Change Resoonse Data collected during performance of the load change under automatic control is shown in Figures B-7.20F.1 through F-7.20F.12

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i Startuo Test B-7. Plant Auto =atic Control Svs tem Perfor=ance Tes ts  !

Con:pftrison of Predicated and Measured Data  !

r Part 2D - Feedwater Flow Control '

Tuning of the high range feedwater controllers consisted of making 30K '

~

lb/hr step changes in setpoint. Loop II prcportional band required adjustment i i

to meet quarter amplitude damping. Loop I was left unchanged. l I

k Final gain settings ark, proportional band (PB) 200% and reset of 0.25 ,

t minutes for FC-2205 , PB 150% and reset of 0.25 minutes for FC-2206. The  !

l differential pressure across FV-2205 and FV-2206 is sent through a low select {

t which is then used as the demand input to the feedpump controls. Since Loop 2 l l

1s the low loop this causes a coupling with the feed pump control and is the j reason for the higher gain requirements in Loop 2.

Part 3D - Deaerator Level Control f!

The deaarator 1.evel etning consisted of tuning LIC-2175 and FIC-3175, LIC-3175  ;

t was tuned first with FIC-3175 bypassed. Then FIC-3175 was tuned with both controllet f in operation. Qutzter amplitude damping was achieved.  !

t  !

s ,

, The level controller LIC-3175 ces tuned first, even though it was not the t i

1 l

inner loop controller, because 15 can be used to control the deaerator level with FIC-3175 bypassed.

Figure B-7.3D.1 shows the response of deaerator level (LT-3175) and condensate I flow (FM-3151-2) to an increase of 2 inches in LIC-3175 setpoinc , with the gains as '

l found, PB of 50% and reset of 1J minutes. Figure B-7.3D.1 also shows the re-l sponse to a decrease of 2 inenes in setpoint with tne PB of LIC-3175 changed to 100%. !

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F Part 20F- (continued) l 6

The reheat steam t.amperature was about 1000*F at the start of the load f

change and decreased to 940*F at 30 load. The main steam temperature was about 990*F at the start of the load change and decreased to about 890*F at 30%  !

l load. The steam temperatures drooped the right amount but they did not follow a ramp function down. The main steam temperature started to droop first and >

then reheat steam temperature started to droop. This reheat steam temperature droop caused the mein steam, temperature to droop even more. It is possible that the main steam and reheat steam temperature control systems were interacting to e

, cause the resulting steam temperature droops. The hold portion of the up ramp l

(

caused a larger perturbation in the steam temperature than the load change itself. I i

Both main steam temperature controls went to zero during the main steam ,

temperature droop and the reheat steam temperature control decreased to 30,. ,

during the reheat steam temperature droop.-If this condition exists during steady I state operations, the circulator speed and reactor power characterizers could be

  • reprogrammed to better match the steady state circulator speed and reactor power ,

requirements. This will be monitored during future automatic operation at low ,

t

, power.

The feedvater flow experienced some oscillations on the down ramp and up ramp. The feedwater flow oscillations appear to be caused by the oscillation I

l on the extraction steam pressure to 'BFP-1A' and 'BFP-lC' . l t

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94 -

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( Reactivity Coefficient Measurements (3-8) .

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f This test was not scheduled during the report period. I i

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97 -

TABLE B-9.1 i

SLTfARY OF ROD GROUP 4A DIFFERENTIAL WORTH MEASURE:ENTS (

l Rod # Avg. Pos.. Ap/ Inch l I

t s l 20 87.0 0.161x10"* [

~

, i 20 79.0 0.150x10 ' ,

l 26 86.9 0.259x10 '

~

26 77.0 0.206x10 '

32 87.1 0.153x10 f 4 ( 32 77.0

~

0.136x10 ' I l

20+26+32 81.6 0.501x10 ' ,

' ~

20 92.2 0.180x10 '

-4 20 81.6 0.146x10 f

~

26 91.4 0.29'1x10 '

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26 81.6 ~4 0.239x10 f

t

~

32 91.8 0.189x10 '  !

~

32 81.5 0.156x10  ;

( 20 145.0 -4 r 0.167x10 20 136.0 0.184x10 f

26 145.0 ~4 0.298x10 26 135.0 0.334x10 b 32 145.1 0.244x10

~

32 135.0 0.282x10 '

~

20 131.1 0.205x10 '

~

20 121.0 0.185x10 '

~

26 131.0 0.335x10 '

26 121.0 0.302x10 eeo e

TAB 1E B-9.1 (continued)

Rod # Avg. Pos. Ap/ Inch i

32 131.0 0.285x10

32 120.8 0.259x10 '

~

20+26+32 145.0 0.714x10 '

20 176.2 0.076x10 '

~

20 164.2 0.103x10 '

~

I[ 26 176.0 0.153x10 '

26 164.0 0.216x10 '

~

32 176.1 0.121x10 '

32 163.4 0.167x10

~

20 157.0 0.140x10 '

20 146.2 -4 0.165x10 26 156.0 -0 0.288x10

~

26 146.0 0.259x10 '

-4

( 32 155.8 0.214x10 32 146.0 0.248x10

-4 O

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_ 99 _

COMPARISON OF ACTUAL AND PREDIC'IED PERFORhdCE Table B-9.2 shows a comparison of the measured and predicted integral rod worths for the rod groups measured through the startup test program so far. The acceptance criteria limits are also shown.

Figure B-9.1 shows the measured differential rod worth points and the least squares fitted curves from which the integral worth is obtained for rod 3roup 4A. The integral worth curve for this rod group is shown in

(- .

Figure B-9.2.

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