ML20009C866

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Forwards Monthly Operating Rept for June 1981
ML20009C866
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 07/14/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-81185, NUDOCS 8107220065
Download: ML20009C866 (2)
v • d • e


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Director 4

Office of Inspection and Enforcemer' U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Fort St. Vrain Nuclear Generating Station Public Service Company of Colot do Docket No. 50-267 Operating License DPR-34

Dear Sir:

Attached ple-e find the June, 1981, Monthly Operating Information for the Fort St. Vrain Nuclear Generath g Stat 3on.

Very truly yours,

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$ ff N'l V Don Warem u Manager, Nuclear Product.iort DW/lsb Attachment cc:

Mr. Karl V. Seyfrit Office of "IPC

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.s I $

9107220065 LIO714 yDRADOCK 05000267 PDR

4 M1NTHLY OPERATIN". ?NEURMATION DISTRIBtTTION Number of Copies O

Di t e cto r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - (10j (Oriainal of P Letter)

Of fice of Inspectior and Enforcement U. S. Nuclear Regulatory Comission Washington, D.C 20555 Karl V. Seyfrit, Directo r 1

(P Letter)

Regie-IV Of fi.. of Inspection and Enforcer +tt Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Di r e c t o r + - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 (P Latter) s ifice of Management Information and Progre.' Control U. S. Nuclear Regulatory Comission Washington, D.C.

20555 T,e Cintula 1

(P Letter)

O S. Nuclear Regulatory Commission 12105 National Maryland Bank Building Washington, D.C.

20555 Mr. Richard Phelps --- ----------------------------

1 (P Letter)

FSV, GA, Site Rep resentative General Atomic Company P. O. Box 426 Platteville, Colorado <.551 NRC Resident Site Inspector --------------------------- 1 (P letter)

Senior Vice President, Room 770 1

(P Letter)

Vice President. Electrical Engineering -nd Plannir s, 39th Avenue - - - - - - - - (P Letter)

" ice President P roduction Divis ion, Belleview - - -- - - - - - - - - - - - - - 1 (P Letter)

Quality Assurance Manager 1

(P Letter)

Si te Enginee ring Coo rdinato r - - - - - - - - - - - - - - - - - - - -

1 (P Let i

Nuclear Proj ect Manager, Montbello - - - - - - - - - - - - - - - - - - - - - - - - 1 (P '

3 Cary Reeves Public Relations Room 950 - ---------

1 (C

.,)

.1 o ' Memo)

Bill Shinkle, Property Accounting. Holly Service Center 1

(Ot n-o Memo)

Supe rvisor, Licensing and Administrative Services.

Nuclear Projec t Departcent, Monthallo r--ev---

1 (P Let t Supe rvisor Project Engineering, Nuclear Project Department, Mont5ello - - - - - - 1 (P Lette

('

recuments Contr:1 Technician, Montbello

2 (2 P Lett s)

c. crespondence Loordinator Nuclear Project Department, Montbello 1

(P Letter)

Nuc le a r P roduc tion Man a ger - ~- - - - - - - - -

- - - - - - - - - - - - - - - 1 (P Latter)

Op e ra t ior t Mana g er - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Admir* strative Services Manager 1

(P Letter)

c--

"0RC Committee - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter) i _ V N FS C S ecre t a ry * - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

P Files 1

(P Letter)

4 Re co rd 9 to ra ge - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

- 2 (P Letter)

Technical Services Review ---------------------------- 1 (P Letter)

Technical Services Supervisor -------------------------- 1 (P Letter)

C rey Book No t ebook - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 Monthly Opera

  • ions Folder ---------------------------- 1 Monthly Operating Information Folde r - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letterl Monthly Operating Information File - - - - - - - - - - - - - - - - - - - - - - - - 0 (Original of Report and 1 Copy of P Letter) -

Gas Cooled Reactor Associates -------------------------- 1 (P Letter)

Attention:

Mr. R. A. Evans 3344 North Torrey Pines Court Suite 300 LaJolla, California 92037 Electric Power Research Institute -- --------- -------------

1

(? Letter)

Attention! Mr. halvin E. Lapides 3412 Hillview Avenue P. O, Box 10412-Palo Alto, California 94303

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.___z._.

OPERATING DATA REPORT DOCKET NO.

50-267 DATE J 10701 Coh/LETED BT L. M. McBride TELEPHONE (101) 7R5-2224 OPERATING STATUS NOTES 1.

Unit Name:

Fort St. Vrain 2.

Reporting Period:

R1Q501 N nn c,h RinMO 3.

Licensed nerzl Power OWt):

842 4

Nameplate Rating (Gross We):

342 5.

Design Electrical Rating (Net We):

330 6.

  • H==

Dependable Capacity (Grose We):

342 7.

Maximus 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 khch Restricted If Any (Net We):

231 10.

Reasons for Rastrictions, If Any:

NRC restriction 70% nanrfincr ras.si n H nn nf l

temperature fluctuations

{

t This Month -

Year to Date Cumlative

11. Hours in Reporting Period 720 4.343 17.544
12. Number of Hours Reactor Was critical 0.0 2.667.5 11.800.7
13. Reactor Reserve Shutuvn Bours 0.0 0.0 0.0 14.

nours cenerator On-Linc 0.0 2.131.5 7.824.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. cross normal Energy ceneraad (Ws>

0.0 1.102.586.8 3,810.679.6

17. cross Electrical Energy Generated (W E) 0.0 400.445 1.272.239 l
18. Net Electrical Energy Cecerated (WR) 0.0 369.305 1.168.606

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19.

Unit Service Facter 0.0 49.1%

44.6%

20. Unit Availability bactor 0.0 49.Q 44.6%
21. Unit Capacity Factor (Using MDC Net) 0.0 25.8%

20.2%

22. Ur.i Capacity Factor (Using DER Net) 0.0 25.8%

20.2%

23. Unic Forced t,utage Race 0.0 15.8%

36.9%

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

Wintennnee/

modification shutdown September 1. 1981 lasting 4 months.

I

23. If Caut Down at End of Report Period, *.sticated Date of Startup-July 20. 1981 f%its In Test Status (Pr u r to Commercial Operation):

Forecast Achiewd 26.

INITIAL CRITICALITT N/A N/A N/A N/A INITIAL ELECTRICITT l

IffERCIAL OPEIATION N/A N/A

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UNIT SHtfTIL.lNS AND POWER REDUCTONS

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DocxET No.

50-267 UNIT NAME Pnrr Rr_ tunin DATE 810701 Cowl.ETED BY I.. M. McBride REPORT HONTil June. 1981 TeternoNE (303) 785-2224 l

NE11tOD OF

+

SifUTTINC DOWN SYSTEM C00f0NENT No.

DATE TYPE DURATION REASON REACTOR LER #

CODE 00DE CAUSE AND CORRECTIVE ACTION TD <REVENT RFfURRENCE l

81-17 1110520 S

720 C

N/A N/A N/A N/A Continued refueling outage begiln May 20, 1981.

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Summary: Upon completion of refueling, and post c"ueling testing plan to continue Fort St. Vrain's power ascension program.

AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-267 Unit Fort St. Vrain Date 810701 Completed By, L. M. McBride Telephone

{303) 785-2224 Month June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(rWe-Net) 1 0.0 17 0.0 2

0.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 5

0.0 21 0.0 6

0.0 22 0.0 7

0.0 23 0.0 8

0.0 24 0.0 9

0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 j

13 0.0 29 0.0 14 0.n 30 0.0 15 n_n 31 N/A 16 0.0 I

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we&m REFUELING INFORMATIOJ 1.

Name of Facility.

Fort St. Vrain Unit No. 1 2.

Scheduled data ror next refueling shutdown.

May 20. 1981 (Tn nroeresM 3.

Scheduled date for restart following refueling.

July 20. 1981 l

4.

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

No l

l l

If answer is yes, what, in l

__ general. will these be?

i l

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Connaittee to deter-mine whether any unreviewed safety questions are associaccd

.tich the core reload (Reference 10CFR Section 50.59)?

Yes If no such re>:?4w has taken place, when is it scheduled?

5.

Scheduld date(r,) for submitting proposed licansing actica and supporting in'.ormation.

6.

Important licensing considera-Peripheral fuel elements changed f.rom cious associated with refueling, thin thorium buffer to thick thorium e.g., new or different fuel de-buffer.

sign or supn11er, unreviswed design or performancas analysis methods, significant changes in fuel design, nen operating pro-cedures.

7.

The number of fuel ascomblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in b) 178 sp nt HTGR fuel elements.

the spene fuel storate pool.

8.

The present 11cena :4 spent fuel Capacity is limitad in size to about one-p ci storage capacity and the third of core (approximately 500 HTGR nas of any increase in licensed elements). No change is planned.

storage capacity that has been f

requested or is planned, in 4

number of fuel assemblies.

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.m 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), ed pool assuming the present General Atomic Company.*

licensed capacity.

  • The 1986 date is based on the understanding that spent fuel discharged during l

the term of the Three Party Agreement will *ue shipped to the Idaho Naticual Engineering Laboratory for storage by DOE at the Idaho Chemical Processing i

Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to bs. discharged during the eight year period covered l

by the Three Party Agreement.

I i

CPERATING DATA RDO E DOCEET NO.

50-267 DATE 810701 C0h?LETED BY L. M. McBride TELEPHONE (30 3) 785 7774 OPERATING SfATUS NOTES 1.

Unit Name:

Fort St. Train 2 Reporting Periods R10601 th*nncrh R10MO 3.

Licensed Thermal Power Out):

842 4 Naasplate Rating (Croes We):

342 5.

Design Electrical Rating Oset We):

330 6.

Mad== Dependable Capacity (Crose We):

342 7.

Mad== Dependable Capacity (Net We):

330 L

b.

If Changes occur in Capacity Ratings (Items Nder 3 Through 7) Since Last Report, Cive Reasons:

None 9.

Power Level To Which Restrictu. If Any (Net We):

231 t

13. Raasons for Restrictions, If Any:

NRC restrictidn 70% nondincr raun1nrinn nf temperature fluctuations This Month --

Year to Date Cumulative

11. Bours in Reporting Period 720 4.343 17.544
12. Number of Hours Reactor Was Critical O_O 2.665.5_

11.800.7

13. teactor Reserve Shutdown Hours O_O O_O O
14. sours Generator on-Line 0.0 2.131.5,

7.824.8

15. Unit Reserve Shutdown Bours 0.0 0.0 0.0
16. Cross Thermal Energy Janerated (WE) 0.0 1.102.586.8

_ ),810.679.6

17. Cross Electrical Energy Generated (W E) 0.0 400.445 1.272.239
18. Net Eiectrical Energy Generated OWE) 0.0 369.305 1.168.606
19. Unit Service factor 0.0 49.1%

44.6%

20. Unit Availability Factor 0.0 49.1%

44.6%

21. Unit Capacity Factor (Using MDC Net) 0.0 25.8%

20.2%

22. Lbit Capacity Factor (Using DER Net) 0.0 25.8%

20.2%

23. Unit Forced Outage Rate 0.0 15.8%

36.9%

l 24.

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

Win t ennnce /

modification shutdown September 1. 1981 lasting 4 months.

25.

If Shet Down at End of Report Period. Eatinated Date of Startup:

July 20. 1981

26. Units In Test Status (Prior to Comunercial Operation):

Forecast Achieved l

INITIAL CRITIC.ITT N/A N/A INITIAL ELECTRICITY N/A N/A COMtERCIAL OPERATION N/A N/A

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AERAGE DAILY UNIT POWER LEVEL Docket No.

50-267 Unii Fort St. Vrain Date 810701 Completed By L. M. McBride Telephone

{303) 785-2224 _

Month June l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE "AILY POWER LEVEL (We-Ne t)

(We-Net) 1 0.0 17 0.0 2

0.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 5

0.0 21 0.0 6

0.0 22 a.0 7

0.0 23 0.0 8

0.0 24 0.0 9

0.0 25 0.0 10 0.0~

26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 on 30 0.0 15 nn 31 N/A 16 0.0

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  • Generator on line but no net generation,

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REFUELING INF0FliATION 1.

Name cf Facility.

Fort St. Vrain Undt No. 1 2.

Scheduled date for next refueling shutdown.

May 20. IL1 (In nrneresM 3.

Scheduled date for restart followins refueling.

July 20. 1981 4.

Will refueling or resumption of operation thereafter require a cachnical specification change or other license amendmene.?

No If answer is yes, what, in J aneral, will the a be?

If answer is no, has the reloed fuel design and core configura-tion been reviewed by your Plant i

Safety Review Committee to deter-mine whether any unreviewed l

safety questic,.as are associated with the cr.re reload (Reference Yes 10CFR Seetion 50.59)?

If ce such review has taken pl.ce, when is it scheduled?

5.

Schedulac' date(s) for submitting proposed licensing action and supporting iuformation.

l l

6.

Impartant licensing considera-Peripheral fuel elements changed from tions associated with terueling, thin thorium bufrer to thick thorium e.g., new or different fuel de-buffer.

sign or supplier, unreviewed design or performance analysis l

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

7.

The number of fuel assemblies a) 1482 HTGR ft.el elements.

(a) in the core and (b) in M 178 spent HTGR fuel element ~..

the spent fuel storane pool.

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 regrested or is plann=d, in number of fuel asssemblies.

. -. - _., ___.,.__._::~____._____._.____~__._.___.~ _ _ __.- _ _ _

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)-653) between DOE, Public discharged to the spent fuel Service Company of Colorado (PS0o), and pool assuming the prerent Geteral Atomic Company.e licensed capacirv.

  • The 1986 date is based on ;he 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 u:comodate

'2el which is expected to be diraharged durin6 the eight year period covered by the Three Party Agreement.

~

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