ML19224D421

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Monthly Operating Rept for June 1979
ML19224D421
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 07/01/1979
From: Gahm J
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19224D419 List:
References
MOR-790630, NUDOCS 7907120106
Download: ML19224D421 (6)


Text

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OPERATING OATA RIPORT DOCKr! No. 50-267 DAT: 790701 COMP;rna n J. W. Cahm r:.truCNE (303) 785-2253 CPERATING STAIRS NOTES

1.  ; nit Nane: Fo rt St. Vrain. Unit No. 1
. Feporting Pe riod: 790601 to 790630
3. Li:ensed Ther .a1 Fower (MJt): 842
e. Na=eplate Rating (Cress We): 342
5. Design Electrical Rating (Net We): 330
6. . Maxi =u:n Dependat.le Capacity (Gross We): 342 7 Maxi =ur:i Dependable Capacity (Net We): 330
6. :f Changes occur in Capacity Ratings (Irers Nu=' er e 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level To '.thich 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 t e s tin g.

This Month Year to Date Cu=tlative

11. nours in raportirg Petiod 720 4343 - - - - - - -

1:. :.usber of sours Reactor teas Critt:a1 328.7 1146.4 14620.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 la. Hours Generator on-Line 0.0 665.3 8,507.9
15. Unit Reserve shutdown acurs 0.0 0.0 0.0
16. cross Ther=al Energy cenerated (Wa) 2653 315,745 3,518,743 1: cross Electrical Energy Generated (Wu) 0 109,852 1,058,122 1s. set Eleurical Energy cenerated ($n) 0 101,177 952,628
19. ':ni t setcice Factor N/A N/A N/A 20- Unit Availability Ta: tor N/A N/A N/A
21. Unit Capacit, rac tor (Using MDC Net) N/A N/A N/A
. Unit Capacitf Factor (Using OER Net) N/A MA N/A
23. Cait Forced outage Rate N/A N/A N/A
. Shatdewns Scheduled Over Next 6 mnths (Wpe. Date, and Durat. ion of Each): Maintenance Shutdown, October 20. 1979, 30 davs
25. :f Shut Dcwn at End of Fepert Period, Esti:ated Oate of Startuo: N/A 7907120/of
t Units in Test st a us (Prio r to Cc=e rcial op era tion) : Fere-ast A:nieved
nu:. su:Cn.:r;_ 740101 740131
rn ix. ELECTR::1 f ',) 7612 761211 cm2Rct.c cr EaAT:. ------ ----

cut T, Spyna SFS. At4D _riup R R rinc_ TONS

>rr si. 50- 2 f> 7_

rNiT tanE _

Fort S t.

_ Vrain, Unit No. I ra:E 790701 conrt.rtr D BY .I_ . W . Gahm RrroaT tenNrn .1 tin e , 1979 TrrrenonE (30 3) 785-2253 tmnion or SituTTING IN VN SYSTEM CottroNr.NT Na. DATE TYPE DtiRATION R FASON REACTOR IIR I Co'iE CODE rAtlSE AND CoRRECTIVF ACTION To FREVENI R HTR RI PT 79-04 790201 F 720 A 4 79-03/03-L-0 till PUMPXX Excessive gland leakay,e on "B" bot .c feed pump concurrent with inoperable "C" boiler feed pump necessitated controlled reactor shutdown on Fe b r u-ary 1, 19 79, pe r LCO 4. 3. 2. Scheduled

'v reactor shutdown for refueling was C"' changed from Marco 1, 1979 to Febru-

^ ary 1, 1979. Thus shutdown number 79-04 has extended through February, pg March, April, May, and . lune, 1979.

r-, Although the reactor was critical for ca 328.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> In the reporting period, the turbine-F.enerator rem ined o f f-line S U h'1A RY . Plant at less than 2% rated power to allow cleanup of secondary coolant chemistry.

J

AVERAGE DAILY C;IT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain, Unit No. 1 Date 790701 Completed By J. W. Gahm Telephone (303) 785-2253

>bnth June, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(%'e-Ne t ) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 0 19 _

4 0 20 0 5 0 21. 0 6 0 22 0 7 0 23 0 S 0 24 0 9 0 25 0 16 0 26 0 11 0 27 0 12 0 23 0 13 0 29 0 14 0 30 0 15 0 31 N/A 16 0

  • Generator on line but no net generation.

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REFUELING INFORMATION

1. Name of Facility. Fort St. Vrain. Unit No. 1 l
2. Scheduled date for ne): refueling shutdown. September 1, 1980
3. Scheduled date for estart following refueling. November 1, 1980
4. Will refueling or resu=ption of operation thereafter require a technical specification change or other license atendment? No If answer is yes, what, in general will these be?

If answer is no, has the reload The Plant Operations Review Committee fuel design and core configura- will review any questions associated with tion been reviewed by your Plant the core reload Safety Review Committee to deter-line whether any unreviewed safety questions are associated I with the core reload (Reference  !

j 10CFR Section 50.59)? }

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

5. Scheduled date(s) for submitting - ------

proposed licensing action and supporting information. i

6. Important licensing corsidera- -- --

l tioas associnted with refueling, 1, e.g., new or different fuel de-

{ sign or supplier, unreviewed l design or performance analysis l methods, significant changes in t

fuel design, new operating pro-cedures.

I

7. The nu=ber of fael assemblies a) 1482 HTGR fuel elements. l (a) in the cort and (b) in the scent fuel storace cool. b) 245 spent HTGR fuel elementr.

i

8. The present licensed spent fuel Capacity is limited in size to about one l pool storage capacity and the third of core (approximately 500 HTCR l' size of any increase in licensed elements). No change is planned.

storage capacity that has been

! requested or is planned, in

! number of fuel asse=blies. I J7cA J'

L / c.o'

PlFUELING INFORMATION (CONTINUED)

9. The proj e. .ed da te 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 Ser ice Company of Colorado (PSco), and pool assuming the present General Atomic Company.*

licensed cacacity.

  • Th e 1986 data 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 iischarged during the eight year period covered by the Three Party Agreement.

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