ML20071H210

Monthly Operating Rept for Apr 1981

ML20071H210
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/05/1981
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20008F895	List: ML20071H210
References
NUDOCS 8105120277
Download: ML20071H210 (5)

Text

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Or RAnNC DATA REPORT DOCKET NO. 50-267

-* DATt 810505 C0HrttTED sY J. W. Cahm TELrra0Nr (303) 785-2224 OPERATINC STATt'S NOTES

1. Unit Names Fort St. Vrain

2. Reporting Period: 810401 through 810430

3. Licensed Thernal Power Osit): 842

4. Nameplate Rating (Gross We): 342

5. Design tiectrical Rating Clet We): 330

6. Maximum Dependable Capacity (Gross We): 342

7. Maximus Dependable Capacity (Net We): 330

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

N

) None

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4. Power LewI To Which Restricted. If Any (Net We): 231 1c. Raasons for Restrietto.a. If any: Nuclear Regulatory Co mission restriction 70% pending resolution of temperature flue: xtions.

This Morth Year to Date Cawiative ,

11. m es in Reportsng P.:fod 719 2,879 ,

16,000

12. Nu@r of Bours Emaccor Wu Critical 668.2 2,363.7 11,498.9

13. iea r,e Reserve shu:down sours ___

0.0 0. 0 0.0

14. bure cenerator on-:.in. 373.2 1,845.6 h338.9 0.0 0.0 0.0 f] Unit ' Reserve Shutdovu sours

\s,./ cross Thermal Energy Generated (WR) 197,337.4 931,677.5 3,6391 770.3

17. Cross Electrical EnergF Cenerated 0s38) 69.848 335.739 C: 1.207.533

18. Het Electrical Energy cenarated Os.'s) 63.549 310.213 1.109.514

19. Unit Service Factor 51.9 1 64.1! 46.9 ,

20. Unit Availability Factor a;1. 9 % 64.1% 46.9%

21. Cait Capacity Factor (Using MDC Fet) 26.8% 32.7Y 20.9%

22. Unit Capacity Factor (Using DER Net) 26.8% 32.7% 20.9% )

23. Unit Forced Cutage Rete 48.1% 35.9T 37.0%

24. Shutdovna Scheduled over Next 6 Montha (Type. Date, and Duration of Each): Refueline. startine June ? .1981 for approximatelv 8 weeks.

23. If Shut Down at tad of Report Period. Eatinated Date of Startup NA

26. Units In Test States (Frior to commercial operation): Forecast Achieved

~ INITIAL CRInCALin NA NA INIn AL ELECTRICIn NA NA

• \OCl2 U O277 c)MMERCIAL OPERAn0N NA NA

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. UNIT SHUT!XANS AND PtNER REDUCR)NS ~

50-267 recxEr No. .

untT wit Fo rt S t . Vrain nATE 810505 coerLETEn av J. W. Cahm f neront noNTn April. 1981 TELErHoNE (303) 785-2224 METHOD OF l SHUTTING DOWN SYSTEM COMPONENT NO. DATE TYPE DURATION REASON REACTOR lek # , CODE (X)DE CAUSE AND (X)RRECTIVE ACTION 1D PREVENT RECURRENCE 81-11 810401 F 232.5 A 2 80-030 /0.1-X-1 IIB llTEXCll Unit taken off line and reactor shutdown due to excessive loop 2 steam generator penetration interspace pressurization helium leakage.

Continuation of shutdown f rom March,15 81 81-12 810413 F 23.8 A 3 NA ED CKTBRK When "A" Reactor Building exhaust fan was started a bad connection caused the breaker to fail and resulted in a hot reheat scram. ,

81-13 810419 F 23.2 A 3 NA IB INSTRU A faulty speed cable on ID helium circulator caused the circulator to - ,

trip and subsequently resulted in a hot reheat scram.

I 81-14 810420 F 24.3 A NA NA IB INSTRU A faulty integrated circuit and a failed relay caused both loop II

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circulators to trip. The turbine generator was taken off line to recover the loop.

81-15 810425 F 42.0 B 3 NA IB INSTRU During calibration of 1A helium circ-ulator main drain valve a buffer-mid-buffer trip occurred which resulted in a hot reheat scram.

Sunenary : Plan to continue operation at 70% power until refueling shutdown.

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~ AVERAGE DAILY UNIT POWFR LEVEL

- Docket No. 50-267 Unit Fort St. Vrain l

\

• Date 810505

{ Completed By J. W. Gahm lf Telephone (303) 785-2224

' Month April, 1981 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I 1 0.0 17 242.6 i

2 '.0 O 18 250.2 l

! 3 0.0 19 7.0 l 4 0.0 20 78.0 1

5 ,0.0 21 __

- 0.0

• 5 0.0 22 170.3 3 7 0. 0 ' 23 215.1 1

t j 8 0.0 24 255.3

l, 1 9 0.0 25 11.5 i.

. 10 10.l' 26 0.8

}- 11 67.6 27 M*

86.1 i 12 103.0 28 209.5 1

13 118.2 -29 213.6 i

i 14 27.7 .30 216.9 15 197.4 31 NA

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l 16 220.8

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• Generator on line' but no ' net' generation.

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REFUELING INFOR.M TION 4

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1. Name of Fseiliev. Fort St. Vrsin. Unit No. 1 l

l 2. Scheduled date for next refueling shutdown. June 1,1981

3. Scheduled date for restart

following refueling. August 1, 1981 j 4. '4111 refueling or resumption of i operation thereafter require a j technical specification change

or other license amendment? No If answer is yes, what, in general, will these be?

If answer is no, has the reload Yes fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questiens are associated with the core reload (Reference 10CFR Section 50.59)?

j If no such review has taken - - - - - - - -

1 place. when is it scheduled?

j l 3. Scheduled date(s) for submitting ----- ---

} proposed licensing action and l supporting information.

, 6. Important licensing considera- Peripheral fuel elements changed from thin I

tions associated with refueling, thorium buffer to thick thorium buffer.

e.g., new or different fuel de-sign or supplier, unreviewed design or performance analysis i methods, significant changes in j fuel design, new operating pro-i

, cedures.

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

(a) in the core and (b) in the spent fuel storage pool. b) 10 soent MTGR 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 $00 HTGR ele-

size of any increase in licensed ments). No change is planned.

storageC eapacity that has been 4

requested or is planned, in number of fuel assemblies.

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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 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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