ML19208A375

Monthly Operating Rept for Aug 1979

ML19208A375
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19208A374	List: ML19208A373 ML19208A375
References
NUDOCS 7909130489
Download: ML19208A375 (5)

Text

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CPERACNC OATA REPORT DCCKt! NO. 50-267 OA:t 790901 Cox?Lr:ID sT 3. b' . Caht' Tz:.zrscNt (303) 785-2253 cPrn n sc sTarrs NOTIS

1. cait Name: Fort S t. Vrain, Unit No. 1 l

. Reporting Period: 790801 thru 790831 .

D OO l D

3. Licensed Thernal Power (,Wt): 842 I

4 Nameplate Racing (Gross 5'e): 342 OO i O ~

j i 330 0

5. Destgn Elec:rical Rating (Net We):

0 f ,

6. Maximum Dependable Capacity (Cross We): 342 O -* - Q  ;

e I

7. Ma *-n- Dependable Capacity (Ne t We) : 330 S. If Changes occur in Capacity Ratings (Ite:s Number 3 "hrough 7) Since Last Report, Give Reasons:

None

9. Power Level To *"hi:n Restricted, If Any (Net We): 231

10. Reasons for Rast:1 tions, If Any: Nuclear Regulatorv Cor=ission res triction (70%) cending resolution of ter:cerature fluctuations.

This Month Tear to Oate C M ative

11. Hours in Reporting Period 744 5,831 1,488

12. Number of sours Reactor was Critica 712.7 2,556.0 16,029.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

c. sours cenerator on-Line 542.5 1,293.4 9.136.0

15. cnit Reserve Shutdovu Bours 0.0 0.0 0.0

16. cross Thermal Energy cenerated (5FI) 253,407 628,291' 3,831,289

17. cross ne:trical Energv senerated (s a) 88,079 202,453 1,150,723

13. Net tie:trical Energ7 Generated (5 a) 81,868 183,045 1,034.496

13.  ; cit service raet:r 72 . 9 *: 42.2" 42.2*

0. : nit Availabi: tty ractor 72.9* 42. 2*: 42.2*

1. ::it Capacity ractor (csing MDC Net) 3 3. 3*: 16.7% 16. 7*.

. Unit Capacitv ractor (csing :ta Net) 33.3* 16. 7*: 16 . 7*:

3. Unit Forted Dutage Rate 27.1* 57.7* 57. 7*:

26. Shutdevns Scaeduled Over Ner: 6 Macchs (Type, Date, and Duration of tach)- Maintenance Shutdown.

October 20, 19 79, 30 Davs

25. If 3 hut Down at End :f Repcrt Pe-tod. Istimated Date of Startuo: N/A O1Qi

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$.  : s In :est S ta t :.s 'P-1er to ::=nercial Deeration): Foretas: Ac nieve:

r.- .e nnCA:.:n 740201 740131

r. :A:. e -

7612 761211 7 900130 Y8  ;;M r3;.  ;,s, n;y 79g701 79g 701

U,NI T SHH_ilE MNS. .AN_D l'.t _W ER. p t DUC.TU. N'i 50-267 ruirFFT NO. . _ . - _________ __._..__.

UNIT NAME Fo r t _S t .,_V ra l_ n , Uni t No. 1 Darr 790901 neta trien mY J. W. Gahm Rt t' ORT nONfil Atigus t t 1979 t t i.rrisoNE J30_ L 785__2_25_3 _ _ _ _ _

HEnioD of Saltil11NG In WN SYSitH COHI'ON FN f NO. DAIE TYPE DURATION REASON R FACTOR lFR I OlDE osDE CAtlSr ANil CORHECTI VE ACTIO 4 10 l'REVENT NErtlRPf.NCE 79-08 790731 F 63.1 11 3 N/A N/A N/A While transferring to partial arc on the main turbine generator, throttle pressure dropped arid load decreased 20 FM. During recovery, three circu-lators tripped, I.oop 2 shutdown, reactor scrammed, and turbine tripped.

79-09 790811 F 24.1 11 3 N/A N/A N/A While reducing power to recover a tripped circulator, hot reheat reac-tor scram and turbine trip occurred.

79-10 790817 F 68.4 11 3 79-028/01-T ED ZZZZZ An instrument panel was shorted to ground and tripped, resulting in reactor scram and turbine trip.

79-11 790824 F 45.9 11 N/A N/A N/A N/A Turbine generator taken off line as reactor power was reduced in an at-tempt to isolate cause of high pri-mary coolant moisture. Reactor not shutdown.

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.C ix

[ S UMMARY : plan to continue operation for electric production and fluctuation testing until release to continue power ascension testing above 707. rece ived f rom Nuc lea r Regulatory Commiss ion.

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain, Unit No. 1 Date 790901 Completed By J. W. Gahm Telephone (303) 785-2251 Month Au g us t . 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEV':

(MWe-Net) (MWe-Net) 1 17 93 2 18 3 21 19 4 '116 20 37 5 129 21 158 6 153 22 211 7 197 23 205 8 200 24 120 9 206 25 10 208 26 39 11 156 27 120 12 5 23 110 13 136 29 109 14 188 30 105 15 196 31 98 16 128

• Generator on line but no net generation.

9)U ['] O d.

REFELING INFORMATION

1. Name of Facilitv. Fo r t S t . Vrain, Unit No. 1

2. Scheduled date for next refueling shutdown. September 1, 1980

3. Scheduled date for restar:

following ref ueling. Nove=ber 1, 1930 4 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No If answer is yes, what, in eeneral, will these be?

If answer is no, has the reload The Plan Operations Review Committee fuel design and core configura- l will review any questions associated tion been reviewed by your Plant i with the core reload.

Safety Review Co=mittee to deter-mine whether any unreviewed safety questions are associated I -

with the core reload (Reference I 10CFR Section 50.59)?  !

I If no such review has taken i place, when is it scheduled? l March 1, 1980

5. Scheduled da:e(s) for sub=itting -- --

proposed licensing action and suoporting information. i

6. I=portant licensing considera- - - - - - -

tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed '

design or perfor=ance analysis I methods, significant changes in fuel design, new operating pro-cedures. l t'

7. The number of fuel asse:blies a) 1482 HTGR f uel elemen ts. '

(a) in the core and (b) in l the scent fuel storare cool, b) 244 scent HTGR fuel elements.

• I '

l S. The present licensed spent fuel Capaci:v is limited in size to about one '

l l pool storage capaci:y and the i third of core (approximately 500 HIGR l l size of any increase in licensed l elemen ts) . No change is planned. l

, storage capacity that has been i '

reques:ed or is planned, in l nu=cer of fuel asse blies. '

ti h

REFUELING INFOPP.ATION (CONTINUED)

9. The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company o f Colorado (PSCc) , an d pool assu=ing the present General Atode Company.

• licensed capacity. ,

• The 1986 date is based on the understanding that spent fuel discharged during the ter= of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP) . The storage capacity has e ndently been sized to accotodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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