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TSP- 3 Acaachmant-38 | |||
* IaJun 2 Page 1 of L O?!PATUG DA A RE?CRT 00C:"I? 240. 50-267 3An December 7, 1982 cc:r_:n3 3Y L. hi: McBride | |||
= trucNr a n o 79c;_???d , | |||
OPERATI"G STA M i iOTT.S f | |||
, 1. Uni: Name: Fnr* 9t- 'frain | |||
: 2. Reporting Period: A71101 thenugh A71110 | |||
: 3. Licensed Thernal Power (Wt): Ad7 4 Nameplate Racin6 (Croes We): 1d7 | |||
: 3. Design nec:ri:a1 Racing (Net tue): '41 0 | |||
: 6. I Mazin.m Ospendaale Capacity (cross .*ie): 7A? | |||
* l | |||
: 7. 72x =um :ependahie Capaci:v (Nec :;e): 330 ! l | |||
: 3. Of Changes Cccur in CapacP:7 Ratings (!: ems Nuncer 3 Througn 7) Since *.as: Raport, cive Raasons: | |||
None | |||
: 7. ?:wer | |||
* evel To ~4hich Restricted, If Any (Not :*i e): 231 | |||
: 10. Reasons for Rescriccions. If Any: Restr(etion to 70% pending resolution of contractual matters. | |||
This 21onth Year es Caca C,;nulative | |||
: u. sours in Re,or:ing rerio4 720 8016 29977 j ... xuemer se sours Reaccar m Cri:1 cal 538.8 4745.0 19323.4 j 13. Reactor Reser re Shutdown Hours 0 0 0 1 | |||
: u. sours ceneraese en-une 0 3266.2 13174.5 | |||
: u. cai: Reser.re Shutdown :<ours 0 0 0 | |||
;6. cras. Th.: ; rnergy cesera:ed oux) 6541.9 1849177.5 6783122.3 | |||
: 17. crass nect-temt tuergy ceneraced (:ss) 0 635548 2326904 | |||
: u. Nec necerical energy ceneraced csu) -5330 573085 2127344 | |||
! 19. Unit Service Factor 0 40.7 43.9 | |||
; :a. eni: Avanabut:7 rae:ar 0 40.7 43.9 | |||
*1. Onic Capaci:7 Tactor (esing :CC Nec) 0 21,7 21,5 | |||
: n. unie capac::y rac:=r (: sing et2 :et) 0 21.7 21.5 IJ. "ni Forced oi. cage Rate 1nn_O 16,3 3d,6 | |||
: 24. Shutdowns 3cheduled Over Nex: 6 5:ts (Type. Data, and Ouration of Iaca): Plant recovei / e21201 through 830115-1104.0 hours. Surveillance testing 830823 through 830422-744.0 hrs.. | |||
:5. : shac :c.n ic :nd or aepor: 7.ried. r,:inated : ace er s:2r:u,: Reactor is critical at low power. | |||
: 25. Units in Tes: 3:a:aa (?rier :J Oen=e r:ial Opera n en) : Tcreess: Achieved | |||
; :nnx. CR: na:.:n N/A N/A | |||
:nnA:. ::.:: 2:n= N/A N/A 8301100084 821207 :PI2An:2 1/A N/A PDR ADOCK 05000267 R pop | |||
ASP-3 | |||
- Att ach;wnt-3A AVERAGE DAILY CNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date noenmher 7. lor 2 Completed By L. M. McBride Telephone (303) 785-2224 Month November DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.. - | |||
(NMa-Net) (Mge-Nee) 1 0.0 17 0.0 2 0.0 13 0.0 3 n_n 19 0.0 4 nn 20 0.0 3 nn 21 n.n 6 n_n 22 nn 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 23 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 23 0.0 13 n_n 29 0.0 12 0.0 30 0.0 13 0.0 31 N/A 16 0.0 | |||
* Generator on line but no net generation. | |||
TSI'- 1 A t t eas tems'es t -[C | |||
* Imaise 2 t | |||
I'dr.e 3 ** I I UNIT SiltlilmWNS AND 11Mut kl3st1C114tS t, NIT ,unE fort St. Vrain nAtE December 7, 1982 corrmin .T L. M. McBride amiuT emmni November 1982 num>NE (303)785-2224 HEntoD 0F SillfTTING | |||
~ ~ ~ ~ ~ ~~ l lxWN SYSTP}l 0440't BNENT I th ) . DATE IT PE latlRATioN MEASON REACTOR I.EH I O t!)E EUl>E CAllSE AND tDRKECTIVE ACTION To l'Rt.VEN r net:llRNENt:E B2-014821101 F 720.0 H 3 N/A IDH INSTRU Loop 1 Shutdown followed by reactor scram and turbine-generator trip on 820930. Outage continued due to primary coolant chemistry impurities. | |||
1 i | |||
G t | |||
L 9 | |||
4 0 | |||
. - - _~ . - _- . | |||
4 REFUELING INFORMATION | |||
: l. Name of Facility. Fort St. Vrain Unit No. 1 4 | |||
: 2. Scheduled date for next refueling ' | |||
shutdown. September 1, 1983 | |||
: 3. Scheduled date for restart following refueling. November 1, 1983 1 | |||
: 4. ' | |||
Will refueling or resumption of operation thereafter require a , | |||
technical specification change or other license amendment? Yes If answer is yes, what, in general, vill these be? Use of type H-451 graphite. | |||
If answer is no, has the reload l | |||
fuel design and core configura-tion been reviewed by your Plant i i Safety Review Consittee to deter- l | |||
? mine whether any unreviewed I | |||
l safety questions are associated i with the core reload (Reference ' | |||
l 10CFR Section 50.59)? l i | |||
l If no such review has taken l __ _ | |||
olace, when is it scheduled? I - | |||
! 5. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; succorting information. to be determined. | |||
~ | |||
{6. Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed -- | |||
design or performance analysis methods, significant changes in | |||
; fuel design, new operating pro- | |||
! cedures. | |||
: 7. The number cf fuel assemblies 1482 HTGR fuel elements. | |||
(a) in the core and (b) in - | |||
the scent fuel storage pool. 11 spent HTGR fuel elements | |||
: 8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-si:e of any increase in licensed storage capacity that has ,seen third of core (approximately 500 HTGR - | |||
requested or is planned, in leleents). No change is planned. ! | |||
j nu=ber of fuel asse=blies. i e i | |||
,n - , _ , - - . - . , , . , - . n. . , . . _ , - - , . . - . . - , . - . - - . . , _ . - . . . | |||
REFUELING I:! FORMATION (CONTINTIED) | |||
: 9. The projected dat ' of the 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-79ID01370 between Public Service discharged to the spent fuel i Company of Colorado, General Atomic pool assuming the present l Company,andDOE.* | |||
licensed capacity. i | |||
* 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 accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992. | |||
2 7 | |||
l 2 | |||
l i | |||
i i | |||
l i | |||
i i .- | |||
t l | |||
l}} |
Latest revision as of 14:50, 6 January 2021
ML20064J467 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 12/07/1982 |
From: | Mcbride L PUBLIC SERVICE CO. OF COLORADO |
To: | |
Shared Package | |
ML20064J455 | List: |
References | |
NUDOCS 8301180084 | |
Download: ML20064J467 (5) | |
Text
i J .
TSP- 3 Acaachmant-38
- IaJun 2 Page 1 of L O?!PATUG DA A RE?CRT 00C:"I? 240. 50-267 3An December 7, 1982 cc:r_:n3 3Y L. hi: McBride
= trucNr a n o 79c;_???d ,
OPERATI"G STA M i iOTT.S f
, 1. Uni: Name: Fnr* 9t- 'frain
- 2. Reporting Period: A71101 thenugh A71110
- 3. Licensed Thernal Power (Wt): Ad7 4 Nameplate Racin6 (Croes We): 1d7
- 3. Design nec:ri:a1 Racing (Net tue): '41 0
- 6. I Mazin.m Ospendaale Capacity (cross .*ie): 7A?
- l
- 7. 72x =um :ependahie Capaci:v (Nec :;e): 330 ! l
- 3. Of Changes Cccur in CapacP:7 Ratings (!: ems Nuncer 3 Througn 7) Since *.as: Raport, cive Raasons:
None
- 7. ?:wer
- evel To ~4hich Restricted, If Any (Not :*i e): 231
- 10. Reasons for Rescriccions. If Any: Restr(etion to 70% pending resolution of contractual matters.
This 21onth Year es Caca C,;nulative
- u. sours in Re,or:ing rerio4 720 8016 29977 j ... xuemer se sours Reaccar m Cri:1 cal 538.8 4745.0 19323.4 j 13. Reactor Reser re Shutdown Hours 0 0 0 1
- u. sours ceneraese en-une 0 3266.2 13174.5
- u. cai: Reser.re Shutdown :<ours 0 0 0
- 6. cras. Th.
- ; rnergy cesera:ed oux) 6541.9 1849177.5 6783122.3
- 17. crass nect-temt tuergy ceneraced (:ss) 0 635548 2326904
- u. Nec necerical energy ceneraced csu) -5330 573085 2127344
! 19. Unit Service Factor 0 40.7 43.9
- a. eni: Avanabut:7 rae:ar 0 40.7 43.9
- 1. Onic Capaci:7 Tactor (esing :CC Nec) 0 21,7 21,5
- n. unie capac::y rac:=r (: sing et2 :et) 0 21.7 21.5 IJ. "ni Forced oi. cage Rate 1nn_O 16,3 3d,6
- 24. Shutdowns 3cheduled Over Nex: 6 5:ts (Type. Data, and Ouration of Iaca): Plant recovei / e21201 through 830115-1104.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Surveillance testing 830823 through 830422-744.0 hrs..
- 5. : shac :c.n ic :nd or aepor: 7.ried. r,:inated : ace er s:2r:u,: Reactor is critical at low power.
- 25. Units in Tes: 3:a:aa (?rier :J Oen=e r:ial Opera n en) : Tcreess: Achieved
- nnx. CR: na:.:n N/A N/A
- nnA:. ::.:: 2:n= N/A N/A 8301100084 821207 :PI2An:2 1/A N/A PDR ADOCK 05000267 R pop
ASP-3
- Att ach;wnt-3A AVERAGE DAILY CNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date noenmher 7. lor 2 Completed By L. M. McBride Telephone (303) 785-2224 Month November DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.. -
(NMa-Net) (Mge-Nee) 1 0.0 17 0.0 2 0.0 13 0.0 3 n_n 19 0.0 4 nn 20 0.0 3 nn 21 n.n 6 n_n 22 nn 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 23 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 23 0.0 13 n_n 29 0.0 12 0.0 30 0.0 13 0.0 31 N/A 16 0.0
- Generator on line but no net generation.
TSI'- 1 A t t eas tems'es t -[C
- Imaise 2 t
I'dr.e 3 ** I I UNIT SiltlilmWNS AND 11Mut kl3st1C114tS t, NIT ,unE fort St. Vrain nAtE December 7, 1982 corrmin .T L. M. McBride amiuT emmni November 1982 num>NE (303)785-2224 HEntoD 0F SillfTTING
~ ~ ~ ~ ~ ~~ l lxWN SYSTP}l 0440't BNENT I th ) . DATE IT PE latlRATioN MEASON REACTOR I.EH I O t!)E EUl>E CAllSE AND tDRKECTIVE ACTION To l'Rt.VEN r net:llRNENt:E B2-014821101 F 720.0 H 3 N/A IDH INSTRU Loop 1 Shutdown followed by reactor scram and turbine-generator trip on 820930. Outage continued due to primary coolant chemistry impurities.
1 i
G t
L 9
4 0
. - - _~ . - _- .
4 REFUELING INFORMATION
- l. Name of Facility. Fort St. Vrain Unit No. 1 4
- 2. Scheduled date for next refueling '
shutdown. September 1, 1983
- 3. Scheduled date for restart following refueling. November 1, 1983 1
- 4. '
Will refueling or resumption of operation thereafter require a ,
technical specification change or other license amendment? Yes If answer is yes, what, in general, vill these be? Use of type H-451 graphite.
If answer is no, has the reload l
fuel design and core configura-tion been reviewed by your Plant i i Safety Review Consittee to deter- l
? mine whether any unreviewed I
l safety questions are associated i with the core reload (Reference '
l 10CFR Section 50.59)? l i
l If no such review has taken l __ _
olace, when is it scheduled? I -
! 5. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; succorting information. to be determined.
~
{6. Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed --
design or performance analysis methods, significant changes in
- fuel design, new operating pro-
! cedures.
- 7. The number cf fuel assemblies 1482 HTGR fuel elements.
(a) in the core and (b) in -
the scent fuel storage pool. 11 spent HTGR fuel elements
- 8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-si:e of any increase in licensed storage capacity that has ,seen third of core (approximately 500 HTGR -
requested or is planned, in leleents). No change is planned. !
j nu=ber of fuel asse=blies. i e i
,n - , _ , - - . - . , , . , - . n. . , . . _ , - - , . . - . . - , . - . - - . . , _ . - . . .
REFUELING I:! FORMATION (CONTINTIED)
- 9. The projected dat ' of the 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-79ID01370 between Public Service discharged to the spent fuel i Company of Colorado, General Atomic pool assuming the present l Company,andDOE.*
licensed capacity. i
- 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 accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.
2 7
l 2
l i
i i
l i
i i .-
t l
l