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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.
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          . - -            _~                      .    -                                  _-                                          .
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
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Latest revision as of 14:50, 6 January 2021

Monthly Operating Rept for Nov 1982
ML20064J467
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
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

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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.

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