ML19273B708

Monthly Operating Rept for May 1979

ML19273B708
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19273B703	List: ML19273B702 ML19273B708
References
NUDOCS 7906120161
Download: ML19273B708 (6)

Text

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OPERATING DATA REPORT DOCZET NO. 50-267 DATE 790601 COMPLETED BT J. W. Gahm TELEPHONE (303) 785-2753 OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain, Unit No. 1

2. Reporting Period: 790501 to 790531

3. Licensed Thermal Power (WC): 842 4 Nameplate Rating (Gross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Gress We): 342

7. Maximum 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 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 testine.

This Month Year to Date Cumulative

11. Hours in Reporting Period 74 4 3,623

12. Number of Bours Reactor Was Critical 28.3 817.7 14,291.4

13. Re'.ctor Reserve Shutdown Hours 0. 0 0.0 0.0

14. Hours Generator On-Line 0. 0 665.3 8,507.9

15. Unit Reserve Shutdown Hours 0.0 0. 0 0.0

16. cross Thermal Energy Generated (%3) 23 313,092 3,516,090

17. Cross Electrical Energy Generated (ST) 0 109,852 1,058,122

18. Net Electrical Energy cenerated (sa) 0 101,177 952,628

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

20. Unit Availability Factor N/A N/A N/A

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

22. Unit Capacity Factor (Using DER Net) N/A N/A N/A

23. Unic Forced Outage Rate N/A N/A N/A

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

Shutdown for Refueling on 2-1-79 23bU 306

25. If Shut Down at End of Report Period. Esti=ated Date of Startup: 6-15-79

26. Units In Test Status (Prior to Con:nercial Operation): Forecast Achieved IN m AL CRITICALITY 740201 740131 790612016 INITIAL ELECTRICm 7612 761211 m ., or ., . ______

UNtr sutrnxw1ANo rowtR REnocyyNS i,3Cxrr r,>. 50-267 __ -__

UNIT NAME Fort S t. Vrain, Unit No. 1 nATE 790601 _

coffrl,ETEI) BY J. W. Gahm _

HEPORT Pk1NTil h _979 Ehl 1 TEi.EriiONE _(303L785-2253

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HEWOD OF SilDTTING DOWN SYSTEt! COMPONENT NO. DATE TYFE DURATION REASON REACTOR I,ER I CODE CODE CAUSE AND CURRECTIVE ACTION TO PREVENT RECURRENCE 79- 04 790201 F 744 A 4 79-03/ 03-L-0 1111 PUMPXX Excessive gland leakage on "B" boiler feed purrp concurrent with inoperable "C" boiler feed pump necessitated controlled reactor shutdown on Feb-ruary 1,1979, per LCO 4. 3.2.

Scheduled reactor shutdown for re-fueling was changed f rom March 1, 1979, to February 1, 1979. Thus shutdown number 79-04 has extended through February, March, April, and May, 1979.

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SUMMARY

Plant shutdown for scheduled refueling and turbine generator overhaul entire month.

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort S t. Vrain, Unit No. 1 Date 790601 Completed By J. W. Gahm Telephone (303) 785-2253 Month May, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 0 21 6 0 0 22 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 0 28 13 0 29 0 14 0 30 0 15 0 31 0 16 0 2350 308

• Generator on line but no net generation.

REFUELING INFORMATION l

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

2. Scheduled date for next refueling shutdown. February 1,1979

3. Scheduled date for restart followine refueline. June 1,1979

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

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

If answer is no, has the reload

• NOTE: If Technical Specification change fuel design and core configura- approval if not received from Nuclear tion been reviewed by your Plant Regulatory Commission in time for re-Safety Review Committee to deter- fueling, then the answer to #4 is N0, and mine whether any unreviewed the reload fuel and graphite design have safety questions are associated been reviewed.

with the core reload (Reference i 10CFR Section 50.59)? I If no such review has taken place,whenf(itscheduled?

5. Scheduled date(s) for submitting.

proposed licensing action and supportins information.

Januarv 9. 1978

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

tions associated aith 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 ir-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 spent fuel storace pool. b) 245 spent HTGR fuel elements.

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

REFUELING INFORMATION (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 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 Thiee Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP) . The storar,e capacit.y has evidently been sized to accomodate fuel which is ecpected to be discharged during the eight year period covered by the Three Pa rty Agreement.

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