ML20134F880
| ML20134F880 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/31/1985 |
| From: | Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| P-85287, NUDOCS 8508210298 | |
| Download: ML20134F880 (8) | |
Text
-
l PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 138 July, 1985 5
8500210298 850731
/p3 PDR ADOCK 05000267 R
PDR ll
o
. This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is for the month of July,1985.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The first part of the month was spent preparing the systems and procedures for start-up.
All interimproceduresforAppendixRareinplace,andtraining has been completed. New interim control rod drive Technica Specifications and surveillances are in the place.
The reactor was taken critical on July 20, 1985, at about 4:00 a.m. and remained there until approximately 12:00 midnight on July 23, 1985, when a high moisture scram occurred while trying to establish a shutdown seal on "A" circulator.
Both steam driven boiler feed pumps were placed in service and operated smoothly.
A system 46 chillerwasestablishe[on"A"heliumpurification train, and enhanced moisture removal in the front end cooler was accomplished.
This system will be established on "B" train once it is placed in service.
The digital valve installed on "1A" main drain experienced leakage problems.
The original valve was reinstalled, and Engineering will conduct further testing on the digital valves for future use.
2.0 SINGLE RELEASES OF RADI0 ACTIVITY 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 DATA REPORT Attached t
Til )
l
'lI i-i
i tsp-3 Att achen t-O team 2 onume mTA anon Docart so.
50-267 Auaust 8, 1985 dan Frank Novachek caseurtD T (303) 785-2224 tzz.puous OptaATINc STATUS sors:
Fort St. Vrain 1.
ooit name:
850701 throuah 850731 2.
Reporting Period:
842 3.
Licensed Thermal Power Otit):
4 Nameplete Rating (cross We):
342 330 3.
Duten nectrical natins (Mt **)*
6.
nazimus Dependable cepetity (crees me):
342 7.
>--- Dependable cepetity (met we):
330 8.
If chanses occur is cepeetty notinse (Items ur 3 threust 7) stace teet ampers, case sensees None
[
9.. Power Level te whte nastricted, It Amy (met me):
280 Per commitment to NRC. lona term oDeration above 10... aseeems ter a trtette, tr Amy:
85% power pending completion of B-0 startup Testing.
This Meath fear to Bote C a lative 744 5.087 53,352
- 11. moore in aspertins period
- 12. Number of me.re anseur vu critisal 67.7 67.7 27,219.1 0.0 0.0 0.0
- 13. seec ar neeerve shutaeve neer.
0.0 0.0 18,468
- 14. news cenereur oe-uu 0.0 0.0 0.0
- 13. omit nuerve mte news.
- 16. Crees k ruel Enerp Generated (WE) 109.5 109.5 9,861,823.9
- 17. cree nutrial re.rp c.eereted (mm) 0.0 0.0 3.248,594 is not nutrical meersy courated (wn)
-2,973.0
-15,255.0 2,912.703 0.0 0.0 34.6
- 19. Unis s'ervice rester 0.0 0.0 34.6
- 20. unit Anitatury ruter 0.0 0.0 16.6 _
- 21. unit caputty recur (teins MDc ht) 0.0 0.0 16.6
- 22.. onts caputty ruter (uetes Den ht) 100.0 100.0 58.2
- 23. tait rerced oviese mate
- 24. Shutdowns 8theduled over Nest 4 baths (Type Dete, and Duration of Each):
Nono SoDtenher 1,1985 0
- 23. If Shut Down et End of Report Period. Entiested Date of f urtup
- 26. Units In Test Status (Prior to Cee orstel Operation):
Forecast Achieved Intta cutscAuft N/A N/A s
N/A N/A Inna tucTuctn N/A N/A comsmetn ortuttos
TSP-3 Attcchment-3A un 2 AVERAGE MILY WIT POWER LEVEL 7
g gg Docket No.
50-267 Unit Fort St. Vrain Date August 8. 1985 Completed my Frank Novachek Yalephone (303)7852224 Month Julv. 1985 MY AVERAGE MILY POWR LEVEL MY AVERAGE MILY POWER LEVEL (We-Net)
(We-Net) 1 0.0 17 0.0 2
6.0 18 0.0 3
0.0 19 0.0 4
0.0 20 0.0 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 nn 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 0.0 30 0.0 15 0.0 31 0.0 16 0.0
- Generator on line but no not generation.
1 ljli
'!i)jlll l
1l I
l l'
o p
unae gl s
nc a
i tt n
5 k
4 r
i 8
e 2
e l n a
9 h
2 m
oa s
Bl r
1 c
2 s
V a
e o
v 5
r ro 8
o 8
oC p
t N
7 a
t u
7 S
t ay n
s l r a
6 s
k
)
e 2
t u
n 3
s ua e
r o
a 0
u cm l
0 o
c r
3 c
ri C
a ir 5
F A
F
(
w CP t
n su fd a
c on l
s t r
e s
a o
ie m am n
o
_ ua m wem s
ot C
e i u
._ t w m m
a a
o to y
t m
ee r
e n a
l g a
a m
s pn m
e e
ma i
m oh r
a CC P
re X
m X
m O
X D
ees L
X a
B X
mem X
!4f
>i s
ess 8
8 su uo A
A ss_
?,
I*
..!i:
5 i ji,,
5 8
9 1
2 2
0 1
0 0
t s
5 5
u 8
8 g
/
/
u 7
7 A
6 6
e 2
2 e
s 0
0 m
a m
n 5
5 a
s r
r es u
n s mssa e
e e
v s o
rme 3
3 m
e om n
ss e
A G
ne s
=
3 e
4 2
m 3
9 er 4
1 nese s
F F
o n
1 0
0 2
w 6
7 0
0 na 4
5 B
8 6
6 1
40 50 m
80 80 1}
i ii i-i>
O e
- REFUELING INFORMATION I
I I
l 1.
Name of Facility l Fort St. Vrain Unit No. 1 l
l l
l l 2.
Scheduled date for next l
l l
refueling shutdown.
I January 1, 1987 l
l l
l l 3.
Scheduled date for restart l February 1, 1987 l
l following refueling.
l l
l l
l l 4.
Will refueling or resumption ofl No l
- l operation thereafter require a l l
l technical specification change l l
l or other license amendment?
l l
l l
l If answer is yes, what, in l ----------------
l general, will these be?
l l
l l
l If answer is no, has the reload l l
fuel design and core configura-l l
l tion been reviewed by your l
l ll Plant Safety Review Committee l No l
l to determine whether any unre-l l
viewed safety questions are l
- I
!l associated with the core reload l il l
(Reference 10 CFR Section 1.
l 50.59)?
If no such review has taken 1985
'l place, when is it scheduled?
I 5.
Scheduleddate(s)forsubmit-l l
ting proposed licensing action l ----------------
and supporting information.
6.
Important licensing considera- ;I tions associated with refuel- :l ing, e.g., new or different I
fuel design or supplier, unre-viewed design or performance l
analysis methods, significant II l
changes in fuel design, new l
l operatina procedures.
- l l
l 7.
The number of fuel assemblies (a) in the core and (b) in the la)1482HTGRfuelelements spent fuel storace pool, b) 137 spent fuel elements I
REFUELING INFORMATION (CONTINUED) r I
I l
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 to l
l licensed storage capacity that l about one-third of core l
l has been requested or is l (approximately 500 HTGR elements).I l
l planned, in number of fuel l No change is planned.
l l
assemblies.
l l
1 1
I l 9.
The projected date of the last i 1992 under Agreements AT(04-3)-633l l
refueling that can be dis-l and DE-SC07-791001370 between l
l charged to the spent fuel pool l Public Service Company of l
l assuming the present licensed l Colorado, and General Atomic l
l capacity.
I Company, and 00E.*
l The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE at the Idaho Chemical Processing Plant.
The storage capacity has evidently been sized to accommodate eight fuel segments.
It is estimated that the eighth fuel segment will be discharged in 1992.
O i
s I
h##Public Service mii.......
Company of Coloratio 16805 WCR 19 1/2, Platteville, Colorado 80651 August 15, 1985 Fort St. Vrain Unit No. 1 P-85287 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
Monthly Operations Report For July,1985
REFERENCE:
Facility Operating License No. DPR-34 t
Dear Sir:
Enclosed, please find the Monthly Operations Report for the month of July, 1985.
Sincerely,
)
/&M/A J. W. Gahm g
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. Robert D. Martin, NRC JWG:djm IE24 9i
)