ML19347D045
| ML19347D045 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/01/1981 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19347D044 | List: |
| References | |
| NUDOCS 8103100606 | |
| Download: ML19347D045 (5) | |
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50-267 ATE 310301
=x?L:n: n J. U t'ahn Ett?ncNE (3031 785-2224 crtnnsc s:Ars x Es 1.
- sit Name Fort St. Vrain 4
2.
Reporting Period:
910201 th rou ch 910229 l
3.
Lt:ensed nerral Power (st):
842 4
Nameplate Rating (.Gress We):
347_
5.
Oesign Electrical Fating (Net We):
330 5.
Maximum Oependasla Capacity (Or:ss We):
342 7.
Max 1=um ependable Capacity (Net 5'e):
330 S.
If Changes cccur in capatity Fati:3s (Items Number 3 3 rough 7) $1sco Last Report. 01ve Reasons:
None 9.
? wer Level To Wica Restritted, If Any (Net We):
231 13, Reasons for Restrictions, If Any: Nuclear Re2ulatorv CC ".19sion restriatten 70T 909 84 resolution of te:Derature fluc tuations.
31a Monta Year to Oate C.=ulative
- 11. Hours in Raso: ting Peried 672 1,416 14.A17 1.
Nu :er of Hours Raa: tor "Jas Oritica 657.8 1,176 10.311.2
- 13. Reactor Reserve Shutdevu Ecurs -
0.0 0.0 0.0
- 1. 7.oes cenerator on.tise 628.3 1,021.8 6.715.1
- u. : nit Reserve shutteva amurs 0.0 0.0 0.0
- n. Orssa ner=al hergy Generated (sit) 334,669.7' 513,708.5 3.221.301,3
- 17. :r:ss nectrica tsergy Generated (s a) 123.393 186,959 1.053.753
- s. set riectrical !=ergy :ecerated (sit) 116,438 173,856 973.157
- u. : sit servi:e ractor 93.5%
72.2%
45 oi
- o. : sit Av.14oility raetor 93.5%
7 2. 2':
15.oi
- 1. : sit capacity raetor ( sing Mac yet) 32.5%
37.2i 20.25
- 22. " sit Capacity Tactor Gsist OE1 5et) 52.5%
3 7. 2':
20.27
- 3.
- it For:ed Outage Rate 6.5%
27.3%
36.li 24.
Shutdev.s 3cheduled Over Next 6 Montas (Ty;e Oate, and Ouration of Zaca): Re fue li-a. 2 - Acril 3 for accroxi atelv 3 Jeeks.
11
- ! Shut town at hd af Report Per134, Isti=ated Oate of Start as:
- S.
' rnits Is Test stasus (Frier ts :::mercial 0;ersti:n)
Forecast-Acr.ieved IN:*:AL CI:n'"A*.:n
/ A N/A 8
m 2 m:nt:
N/A
'T ' A
-03200$Of ewe.2, y :.,
- s., 3 3f1
AVERACE DAILY L3!T PC'4ER LEVEL Decke: No.
50-267 Uni: Fort 5:. Vrain Date 810301 Cc~;1.:ed By J. '4.
Gah Telephone (303) 785-2224 Man:h, Februarv. 1991 DAY AVERAGE DAILY P0k'IR LEVEL DAY AVERAGE DAILY PC'4ER LEV
(&*e-Ne:)
(%*e-Net) 1 101.4 17 206.8 2
13'7.0 13 210.0 3
167.0 19 209.5 1
4 136.0 20 211.3 4
5 195.1 21 213.5 6
206.5 22 213.5 7
210.5 23 152.2 3
210.1 24 0.0 l
9 212.9 23 42.0 10 io9.s' 26 121.2 11 146.n 27 117.6 12 212.2 23 123.1 13 212.4 29 14 210.3 20 15 209.0 31.
16 205.9
- Centra:or en line bu: no 'ne: 3enera:icn.
tmj r, pugisseas, Ann r!*o* ?t!'"G*1 inirn r rei.
50-267_.
im a Nang Fort St. Vrain i,a n 1110301 0,,,in n, n
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{A,L,PSE, AND OIRNFC1_lW A_ cit uN,10_ l'flFV) Mi kfi"Il84 BI,0 Nif _
li l - O 'l 1110131 F
0.0 11 N/A til-009 /fA 3-l.-0 0 11 N/A Power reiluction alue to high level of prinury coqint oxidants.
111- 0 4 810210 F
O.0 E
N/A N/A l it lustru Power reduction due to loop trip ilur.g scheduleil Survei llant1 Test.
111- 0 5 810211 F
O.0 11 N/A 111-015/03-I.-0 Cil N/A Power reduction due to high level of prinary coolant oxlilant s, 111- 0 6 1510223 F
43.7 C
C N/A I ll N/A System freiguency upset causeil rapid toad swfig and hot re he.i t scram.
111- 0 7 1110226 F
0.0 11 N/A til-020/0 3-1.-0
- Cit, N/A Power rediaction due to high level of p ri nwi ry _ coo l an t o x i ela n t s.
SillitlA RY : Cont inne operat ion unti I refue1 inn.
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REFUELI::C INFCPECIO::
1 1.
- tane of Facility.
Fo rt S t. " rain. Unit No. 1 2.
Scheduled date for next refueling shutdown.
Aoril 3. 1981 3.
Scheduled date for restart following refueling.
Sme 3. 1901 4.
Will~ refueling or resunption of operation thereafter require a technical specifica: ion change or other license anendnent?
No J
If answer is yes, what, in general, will these be?
i 4.
I If answer is to, has the reload Yes fuel design and core configura-
- ion becc reviewed by your Plant Safety Review Conmittee to deter-4 nine whe:her any unreviewed safety questions are associated with :he core reload (Reference l
__10CFR See:1on 30.591?
l 1'
If no such review has taken-place. when is it scheduled?
5.
Scheduled da:e(s) for submit:ing proposed licensing action and supporting infernation.
6.
Inportan: licensing considera_
Peripheral fuel ele =ents changed fro: thin tions associa:ed with refueling,
- horian buffer to : thick choriun buffer.
e.g., new or different fuel de-sign or supplier, unreviewed design or perf arnance analysis nethods, significant changes in fuel design, new cperacing pro-cedures.
y 7.
The number of fuel assenblies a). 1432 ETGR fuel elenents.
(a) in the core and (b)'in the spen: fuel storare pool.
-kT 10 seent HTcR fuel eierents.
.3.
The present licensed spen: fuel
~ Capaci:y-is linited in si:e :o about one-pool-storage capaci:7 and :he size of any increase-in licensed.
- hird of core (approx 1=ately 500 RTGR ele-nen:s)..tio change is planned.
storage capacity : hat has been'
. reques:ed or is planned, in number of fuel' assenblies.
l
4 RETUELING INTOPS.ATION (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 Cocpany 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 Agree:nent will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plar.; (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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