ML20234C375

Monthly Operating Rept for Aug 1987

ML20234C375
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/31/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87320, NUDOCS 8709210262
Download: ML20234C375 (8)

Text

_ - - _ _ _ - - - - _ _ _ _ _ _

/

\

i 1

i ,. ..

l '

l i

l PUBLIC SERVICE COMPANY OF COLORADO

)

t FORT ST. VRAIN NUCLEAR GENERATING STATION  !

.i i

l 1

! i i i

.i 1

(t MONTHLY OPERATIONS REPORT NO. 163 i

l August, 1987 l

l 3

j e709210262 870831 ADOCK 050 g 7

[M ij gDR

I

This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulato.f Commission Operating License DPR-34. This report is for j the month o' August, 1987.

4 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of August while "D" helium circulator (C-2101) was replaced.

The spare helium circulator (C-2104) was received from GA

Technologies on August 7, 1987. C-2101 was removed from "0" j helium circulator penetration on August 8, 1987, approximately

! six days ahead of schedule. Circulator C-2101 was shipped to San-Diego, California, on ' August 12, 1987, for inspection and analysis by GA Technologies. Replacement circulator C-2104 was

. installed in "D" penetration and successfully rolled with condensate to the pelton wheel on August 29, 1987.

t The annual NRC/ FEMA observed Radiological Emergency Response Plan (RERP) exercise was conducted on August 5, 1987. Preliminary results indicate only minor deficiencies were observed.

Station batteries "A" and "C" passed the service discharge test during the month of August, 1987.

Spent reflector element shipping commenced during the month of August, 1987.

Repressurization of the Prestressed Concrete Reactor Vessel (PCRV) commenced August 31, 1987.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING OATA REPORT Attached e

2 E

1 1

(_--___. _ __ __

- 1, w : 1 DoCut xa, _50-267 ormrme eATA trror dan September 15. 1987 i

! Court.ru D :T F. J. Novachek r:1.Ermour (303) 620-1007 OPERATINC STAT'JS NOTES

-1. Unit mann's Fort St. Vrain. Unit No. 1 ,.

2. maporting Period: 870801 throuah 870831

3. Licensed Thermal Power' (WC): 842

4. ' Nameplate natins (Gross W.): 342

5. Design Electrical Rating (Not We): 330'

6. Maximum Dependable Capacity (Gross 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 Re.stricted, If Any (Net We): 270.6  !

10. anasons for nestriccions, If Any: Reanalvsis of safe shutdown coolina followina a 90 minuto interruption of forced coolina.

l This hanth year to Date Cumulktive

11. Bours in Raporting Period 744 5.831 71.616

12. Number of Bours Reactor Was Critical 0.0 2.392.4 32.930.2 l A3. neactor asserve Shutdown sours 0.0 0.0 0.0

24. Bours cenerator on-i.ine 0.0 1.811.7 21.366.8. 1 0.0 0.0 0.0 AS. . Unit Reserve Shutdown Bours

16. Cross Thermal Energy Generated (WH) 0.0 576.546.1 10.841.945.9 I

it. cross Electrical Energy cenerated (wH) 0.0 189.789.0 3.523.785.0

18. Het Electrical Energy Generated (WH) 0.0 161.071.0 3.109.351.0

19. Unit Service Factor 0.0 31.1 29.8

-\

20. Unit Availability Factor 0.0 31.1 29.8

21. Unit Capacity Factor (Using HDC Net) 0.0 8.4 13.2

22. Unit Capacity Factor (using DER Net) 0.0 8.4 13.2

23. Unit Forced outage Rata 100'0 68.9 63.2

34. Shutdowns Scheduled over Next 6 M)nths (Type. Date, and Duration of Each): Replace D helium circulatnr. A70401. ??4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

23. If Shut Down at End of Report Period. Esti=ated Date of Startup: September 10. 1987

26. Units In Test Status (Prior to Commercial operation): Forecast Achieved Inna Cxinenity N/A N/A Inna ELEC r.icm N/A N/A Comrxcin ormnes N/A N/A

AVERAGE DAILY UNIT POWER LEVEL-Docket No. 50-267 ,

Unit Fort St. Vrain Unit No. 1~

Date September 15, 1987 __

Completed By F. J. Novachek Telephone (303) 620-1007 Month AUGUST ,

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.0 17 0.0 4

2 0.0 18 0.0 J 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 56 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 4

14 0.0 30 0.0 15 0.0 31 0.0 16 0.0

• Generator on line but no net generation.

' ------_-_-_._.___._._m_..m_.__

T N 1

t t n f' i 7' e o n 8 k m2 . U 9 e h 1 1 h 3ce n c 7

- aue i . e 0 Ptsg a 5 v 0 Stsa r 1 o 1 TAiP V r N -

r 0 N o

e O 2

7 S m

..t . b J 6 I T

t a

6 e k 1 C l 2 t t n 3 A u

- r p a 0 E cr 0 o e r 3 .EC 5 F S F f i IVN E c

. E E Y E TR OM T B N CR m N A A O EU u N D D H RC i T E P RE l E T T E OR e K I E L C h C N L E T O U P T DN D D M NE O AV e C E c

. E'R a SP l U p AO e S CT R N ,Ii1l1 O

I liIIi ,lii .IIlII I T T N C E P U 7 N M D 8 O O E 9 PE C R 1 MD OO R CC llIliIl E T l I ,lI1i ll W S M O U E P C TE C U SD A D A YO .

N SC II1Ill1i1iIi A IlIlIIIi1iIIIIIIIli l

S N

W # 8 O H 1 D T R 0 T N E -

U O L 7 H M 8 S

T T R iII1 O .II ,iI I , .I u1lIIIliII' N P F U E OG R N R DI O OT T 1 HTNC TUWA EHOE MSOR IIII 'li iII ,IIIlI1 llllI IIiiIIIIIIIl N

O S

A A E

R

,IiI lIilIlII1IlIIIIIIl II1IIIIiIII1 N r O h I

T A O.

R ts U 14 D 7

.ilIiIIIii lIiII I lIlII1IiIIIIIIIIIII1 l I E

P F Y

T IIIlI111tI!IIIIIIIIIIIiiIiIiIIIIiI1IIiI1 9

E 2 T 7 A 0 D 7 8

1IIlI111lIiIIIIIIIIIIII1IiIiIiIIll1IiiIi 0

1 O. -

- N 7 8 -

1IllI1 lIiIIII1IIIIIIIIIiIIIl1iii1IlIII l

f , q

j. 3 ,

- /*

' 4

/ REFUELING INFORMATION

/

l l

. [. f 5 # l i- l 1. No.me of Facility l Fort St. Vrain Unit No. 1- l l l 3 l ..

v

2. Schl.duled date for next l 1 October 15, 1988 l

/ refuedi_nj shutdown. l-I l l It J . 3. Scheduled date for restart l December 15, 1988 l following refueling. I l 1

l l l .

l 4. Will refueling or resumption ofl No l l operatjon thereafter require a l l l technical specification change l l

,,,' l or other license amendment?' I l 1 I l

.l If answer is yes, what, in l ---------------- 1 0 gene'ral, will: these be? l l 1

I

. l- 1 If answer is no, has the reloadl t"/ll/ -

fuel design and core configura-l 1

l

, :I tion been reviewed by your l l .l

'l Plant Safety Review Committee l No l

l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reloadl l i

l (Reference 10 CFR Section l l

-l 50.59)? I l

'7 I l l

' l If no such review has taken l 1987' l

> l - place, when is it scheduled? l l , .I 't l 5. Scheduled date(s) for submit- l l

,L '

l ting proposed licensing action 1 ---------------- l .

, j and supporting information. l l "

i l l l l 6. Important licensing consideta- l l '

l tions associated with refuel- l l  ;

l ing, e.g., new or different l l 1 l fuel design or supplier, unre- l ---------------- l f l viewed design or performance l l l l analysis methods, significant l l l

., I changes in fuel design, new l l {

/

l operating procedures, i l -]

l l l l '

l 7. The number of fuel assemblies l . l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l

l spent fuel storage pool. I b) O spent fuel elements l

.j

/

(

r .

WI REFUELING INFORMATION (CONTINUED)

^l l l lY l i l 8. The present licensed spent fuell. , l.

l pool storage capacity and the l l' l size of any increase in l Capacity is limited in size tb l licensed storage capacity that l about one-third of. core 9 l l l

l has been requested or is l(approximately500HTGRelements).l l l planned, in number of fuel l No change is planned. . l l

l assemblies._

i l

l ..<- l l 9. The pro,1ceted dato of the last l 1996 under Agreements AT(04-3)-633l' I refueling that can be dis- l and DE-SC07-79ID01370 between '- l l charged to the spent fuel pool l Public Service Company of r'l l assuming the present licensed l Colorado, and General Atomic l l capacity. I Company, and DOE.* l 7,

• The 1996 estimated date is based on the understanding that spent ide] , l discharged during the term of the Agreements will be stored by DOE'at; '

, *j the Idaho Chemical Processing Plant. The storage capacity has l evidently been sized to accommodate eight fuel segments. It is i estimated that the eighth fuel segment will be discharged in 1996. ' '

, l f f

/

1 4

li i

'a o

1 l

Com ny f olorado -

1 16805 WCR 19 1/2, Platteville, Colorado 80651 ll < v, q

, . September 15, 1987 I Fort St. Vrain f

~

Unit No. 1

,/ t, P-87320

l'

'< !. p U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D.C. 20555 Docket No. 50-267

-l

SUBJECT:

AUGUST, 1987 MONTHLY r OPERATIONS REPORT

REFERENCE:

Facility Operating (

License No. DPR-34 1

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of August, 1987, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

. If, you have any questions, please contact Mr. M. H. Holmes at l g (303) 460-6960.

, ; ,f Sincerely, j

hhillh $$WI$2mu

, R. O. Williams, Jr.

Vice President, Nuclear Operations Enclosure .

cc: Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch l

Mr. RobeH Farrell Senior Resident Inspector Fort St. Vrain R0W:djm g

l 4l