ML19242D102

Monthly Operating Rept for Jul 1979

ML19242D102
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19242D096	List: ML19242D095 ML19242D102
References
NUDOCS 7908140504
Download: ML19242D102 (6)

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OPERATING dan REPORT DOCEIT NO. 50-267 DATI 790801 c0MPLIIID BY J. W. Cahm Tz:.EPHONE (303) 785-2253 OPERATING STATUS NoIzs

1. Unit Names Fort St. Vrain, Unit No. 1

2. Reporting Period: 790701 to 790731

3. Licensed Thermal Power Out): 842

4. Nameplate Rating (. Gross We): 342

5. Design F.lectrical Racing (Net We): 330

6.  %=4== Dependable Capacity (Gross We): 342

7. Mar 1== Dependable Capacity (Net We): 330

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted, If Any (Net We): 231

10. Reasons for Restrictions, If Any: Nuclear Regulatory Coc: mission restriction (70%) pending resolution of certain Final Safety Analysis Report and Technical Specification bases dis crep an cies. This unit is in startup phase following refueling and turbine generator overhaul.

This Month Year to Data Cumulative

11. Bours in Reporting Period 744 5,087 744

12. Number of sours Reactor was critical 696.9 1,843.3 15,317.0

13. Reac' r Reserve Shutdown Hours 0.0 0.0 0.0

14. sou . cenerator on-Line 85.6 750.9 8,593.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. cross Thernal Energy cenerated (Wa) 59,139 374,834 3,577,882

17. cross Electrical Energy cenerated (W a) 4,522 114,374 1,062,644

18. Net Electrical Energy cenerated (Wa) 0 101.177 952,628

19. Unit Service ractor 11.5% 11.5% 11.5%

20. ecie Avat14'o 111ty ractor 11.5% 11.5% 11.5%

1. cnic capacity ractor (tsing Mac Net) 0.0% 0.0% 0.0%

2. unit capacity ractor (using prR N :) 0.0% 0.0% 0.0%

23. Unit Forced Outage Rate 88.5% 88.5% 88.5%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Ouration of Each):

Maintenance Shutdown, October 20, 1979, 30 days

25. If shut Down at End of Report Period, tatimated cate of Startup: 8-3-79

$. Units In Test Status (Prior to Cc==arcial Operation): Torecast Acnieved

NICA:. CRIUCA:.:n 740201 740131

'::nA:. r:.Icnicir 7612 761211 cmc:x. cPERAUCN 790701 790701 r 7 90814 o s&( (c M

UNIT SHlfTIXMNS AND POWER~ REIAJCTUNS

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nocxET No. 50-267 UNIT NAME Fort S t. Vrain, Uni t No. 1 DATE 790801 COMPLETED B'/ J. W. Oahm REPORT PKWnt July, 1979 TELEPuoNE (303) 785-2253

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HETHOD OF SillfTTING Im MN SYSTEH COMPONENT No. DATE TYPE DUHATION REASON REACTLR I.ER I U1DE (DDE CAUSE AND CORRECTIVE ACTION To PD: VENT PP:URREPCE 79-04 790201 F 542.3 A 4 79-03/03-L- 0 till PUMP XX Excessive gland leakage on "B" boiler feed pump concurrent with inoperable "C" boiler feed pump necessitated con". rolled reactor shutdown on Febru-

, ary 1,19 79, per LCO 4.3.2. Scheduled reactor shutdown for refueling was -

changed from March 1, 1979, to Febru-ary 1, 1979. Thus shutdown number 79-04 has extended through February, March, April, Hay, and June, 1979.

Upon completion of turbine generator overhaul and achievement of suf fi-cient reactor power, first genera-tioli following shutdown 79-04 oc-curred on 7-23-79.

79-05 790724 F 47.5 11 N/A N/A N/A N/A Turbine generater taken off 11ne due to field ground relay pauolems. Reac-tor was not shutdown.

79-06 790720 S 1.9 B N/A N/A N/A N/A Turbine generator taken off line in

!, order to perform overspeed tests.

Reactor not shutdown.

79-07 79072t F 53.0 11 N/A N/A N/A N/A Turbine tripped from high vibration.

g Loop 2 shutdown occurred. Reactor

,a power reduced to approximately 2% j v' _ _ ___

for Looy 2 recovery.

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s ugSuunxvis ann rWER,Rgu,CB),N1 toCKET NO. 50-267 _

UNIT NAttE Fo r t S t. Vrain, Unit No. 1 oats 790801 courtETto eT J. W. Gahm RErORT PR44Til July, 1979 (continued) TELEriioNE (303) 785-2253

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MET 110D OF SilVTf]NG lx1WN SYSTEH CotD'ONENT NO. DATE TYPE DURATION REASON REACTOR LER I CODE otDE CAUSE AND (11RRECTIVE ACTION TV rREVENT RECURRENCE 79-08 790731 F 13.7 11 3 N/A N/A N/A While transferring to partial arc on the main turbine generator, throttle ,

pressure dropped and load decreased 20 PM. During recovery, three circu- ,

lators tripped, Loop 2 shutdown, reactor scrammed, and turbine tripped.

Generator remained off line for balance of repo_rting period.

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S UtDIARY : Plan to continue operation for electric production and fluctuation testing until release to continue power ascension testing above 70% received f rom Nuclear Regulatory Commission.

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort S t. Vrain, Lbit No. 1 Date 790801 Completed By J. W. Gahm Telephone (303) 785-2253 Month July, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Ne t), (We-Ne t) 1 0 17 0 2 0 .8 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 60 8 0 24 0*

9 0 25 0 10 0 26 661 11 0 27 1,095 12 0 28 292 13 0 0 29 14 0 30 385 15 0 31 563 16 0

• Generator on line but no net generation.

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REF*lELING INFORMATION

1. Name of Facilitv. Fort S t. Vrain, Unit No. 1

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

3. Scheduled date for restart following refueling. November 1, 1980

4. Will refueling or resumption of operation thereaf ter require a techni:al specification change or other license amendment? No If answer is yes, what, in general, vill these be?

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

Saf ety Review Committee to deter-nine whether any unreviewed safety questions are associated with the core reload (Reference i 10CFR Section 50.59)? I If no such review has taken March 1, 1980 olace, when is it scheduled?

5. Scheduled date(s) for submitting --

proposed licensing action and succorting information.

6. Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the scent fuel storage pool, b) 244 spent HTGR fuel elements.

8. The present licensed spent fuel Capacity is limited in size to about one pool storage capacity and the third o f co re (approximately 500 HTGR l size of any increase in licensed elements). No change is planned. I storage capacity that has been requested or is planned, in number of fuel assemblies.

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REFUELING INFORMATION (CONTINUED)

9. The projected date of the l'i86 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 of Colorado (PSCo), and pool assuming the present General Atomic Company.

• licensed capacity.

• The 1986 date is based on the understanding that spent fuel discharged during the term 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 evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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