ML19281A362

Monthly Operating Rept for Feb 1979

ML19281A362
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19281A360	List: ML19281A359 ML19281A362
References
NUDOCS 7903120189
Download: ML19281A362 (5)

Text

L OPERATING DATA REPORT DOCKIT No. 50-267 ein 790301 J. W. Cahm g COMPLETED BY n:.EPHONE (303) 785-2253 OPERATING STATUS 3 NOTES

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

2. Reporting Period: 790201 to 790228

3. Licensed Thermal Power ()Mt): 842

4. Nameplace Racing (Cross We): 342

5. Design Electrical Rating Olet We): 330

5. Maximum Dependable Capacity (Gross We): 342

7. Maximum Dependable Capacity (Net We): 330

8. If Changes Occur in Capacity Ratings (Items Numoer 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 Regulatorv Commission restriction (70%) pending -

resolution of certain Final Safety Analysis Report and Technical Specification bases discrepancies. This unit is in the power ascension phase of startup tes ting program.

This Month Year to Date Cumulative

11. Hotsrs in Reporting Period 672 1416

12. Nu=cer of acurs Reactor Was Critical 52.0 789.4 14,263.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. sours cenerator on-Line 6.9 665.3 8,507.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Ther=al Energy Generated (s'd) 2,481 313,069 3,516,067

17. cross Electrical Energy canerated (s a) 546 109,852 1,058,122

13. Net Electrical Energy canerated (s a) 0 101,177 952,628

19. Unit Service Factor N/A N/A N/A

20. Unic Availability Factor N/A N/A N/A

21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A

22. Cait Capacity Factor (Using DEE Net) N/A N/A N/A

23. Unic "orced Outage Race N/A N/A N/A

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

Re f uelin g, 2-1-79, 4 Months

25. If Shut Down at End of Report Period. Istimated :: ate of Startup: 6-1-79

06. Uries In Test Status (Prior es Cc=ercial Operation): Fo r ecas t Achieved inn:AL cRn:C.u.:n 740201 740131 79031201M InnAt n. CruC:n 7612 76121, C0;tMERCIAL CPERATICN

UNIT SturHMNHS AND_ ((ME4_REDUCTONS alCKET NO. _

50-267 ._

UNIT NAME Fo rt S t . Vrain, Unit No. 1 DATE 790301 __

Corni.ErcD ny J. W. Gahm HEPORT HONTH February _

TEi.EPHONE (303) 785-2253 NElllOD OF SiluTTING IMMN SYSTEH COfG'ONENT No. DATE TYPE DilRATION REASON REAC10R I.ER f CODE CobE CAUSE AND CORRECTIVE ACTION TO l'REVENT RECURRENCE 79-04 790201 F 665.1 A 4 79-0 3/03-L-0 till PUMPXX "B" boiler feed pump developed ex-cessive gland seal leakage and was declared inoperable. "C" boiler feed pump had been inoperable since January 5, 1978. LCO 4.3.2 requires two boiler feed pumps to be operable during power ope ra tion. Controlled shutdown was begun followed by a manual scram at 2% reactor power.

Repairs to the feed pumps are in progress.

sum!ARY: Plant shutdown for refueling and turbine generator overhaul entire month.

_J

AVERAGE DAILY UNIT POWER LEVEL Do cke t No. 50-267 Unit Fort S t. Vrain, Unit No. 1 Date 790301 Completed By J. W. Cahm Telephone (303) 785-2253 Month February, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 17 17 0 2 0 18 0 3 0 19 0 4 0 20 0 ,

5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 1.? O 28 0 13 0 29 N/A 14 0 30 N/A 15 0 31 N/A 16 0

• Generator on line but no net 3aneration.

REFUELING INFORMATION

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

2. Scheduled date for next refueling Februa ry 1, 19 79 shutdown.

3. Scheduled date for restar: June 1, 1979 following refueling.

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amend =ent? Yes*

If answer is yes, what, in To facilitate insertion of eight fuel test general, will these be? elemen ts.

If answer is no, has the reload

• NOTE: If Technical Specification change fuel design and core configura- appre val is no t received from NRC in time tion been reviewed by your Plant for refueling, then the answer to #4 is Safety Review Committee to deter- NO and the reload fuel and graphite design mine whether any unreviewed have been reviewed, safety questions are associated with the core reload (Reference i l 10CFR Section 50.59)? l 1

If no such review has taken olace, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action and supoorting information. January 9, 1978

6. Important licensing considera- Eight test fuel elements to allow:

tions associated with refueling, e.g., new or different fuel de- 1) Different fuel particle design.

sign or supplier, unreviewed design or perfor=ance analysis 2) To qualify near isotropic graphite.

methods, significant changes in fuel design, new operating pro-cedures.

7. The nu=ber of fuel asse=blies a) 1482 HTGR elements.

(a) in the core and (b) in the scent fuel storage pool. b) 0 in fuel storage wells.

8. The present licensed spent fuel Capacity is limited by size only to about pool storage capacity and the l one third of core (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.

REFUELING INFORMATION (CONTI FrD)

9. The projected date of the 1986 under the Three Party Agreement last refueling that can be (Contract AT (04-3)-633) between DOE, discharged to the spent fuel Public Service Company of Colorado (PS Co) ,

cool assuming the present and 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.

.