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TSP-3
TSP-3 Atttchment=3B Iccua 2 v orrunuc un arronT DoCxrt no.
* Atttchment=3B Iccua 2 v orrunuc un arronT                                                                               DoCxrt no.       50-267
50-267 May 9, 1985 myE Frank Novachek Court.rTzD sf (303) 785-2224 Tztzenowr OPERATING STATUS soTzs Fort St. Vrain 1.
                        -                                                                                                    myE        May 9, 1985 Court.rTzD sf     Frank Novachek Tztzenowr        (303) 785-2224 OPERATING STATUS soTzs
unit na.e:
: 1. unit na.e:                 Fort St. Vrain                                                                                                      ,
850401 through 850430 2.
: 2. Reporting Period           850401 through 850430
Reporting Period 3.
: 3. Licensed Themal Power ()6TC):                                   842 4 Nameplate Rating (Groes 3Gie):                                   342
Licensed Themal Power ()6TC):
: 3. Design Electrical Rating (Met IGle):                           330
842 4 Nameplate Rating (Groes 3Gie):
: 6. Mad == Dependable Capacity (Gross leie):                       342-
342 3.
: 7. Nad- Dependable Capacity Olet late):                           330
Design Electrical Rating (Met IGle):
: 8. If Changes occur in capacity Ratings (Items Number 3 Through 7) Since tast Report, Cive Reasons:
330 6.
None
Mad== Dependable Capacity (Gross leie):
: 9. Power Level To Which Restricted If Any (Not pale),                                         280 lo. naasons for mastricts es, If any: Per commitment to the NRC, lona term operation above 85% power is pending completion of B-0 startup testing.
342-7.
T21s Month                           Year to Date     C M ative
Nad-Dependable Capacity Olet late):
: 11. nova in n porting period                                                         719                         2,879               51,144
330 8.
: 12. number of a.ua n etor v s Critte.1                                                     0.0                         0.0           27,151.4               l
If Changes occur in capacity Ratings (Items Number 3 Through 7) Since tast Report, Cive Reasons:
: 13. manctor meserve shutdown nones                                                         0.0                         0.0                   0.0
None 280 9.
: 14. news ca ator on-I,ine                                                                   0.0                         0.0           18,468.0
Power Level To Which Restricted If Any (Not pale),
: 15. Unit Reserve Shutdown Bours                                                            0.0                         0.0                   0.0
lo. naasons for mastricts es, If any: Per commitment to the NRC, lona term operation above 85% power is pending completion of B-0 startup testing.
: 16. Cross Themal Energy Generated OSfa)                                                     0.0                         0.0       9,861,714.4
T21s Month Year to Date C M ative
            .17. Cross Electrical Energy Generated Osin)                                                   0                           0         3,248,594 la. set necerical Energy cenerated (isra)                                   -1,966                             -8,048           2,919,910 l
: 11. nova in n porting period 719 2,879 51,144
i
: 12. number of a.ua n etor v s Critte.1 0.0 0.0 27,151.4 l
: 19. Unit S'ervice Factor                                                                   0.0                         0.0                 36.1
: 13. manctor meserve shutdown nones 0.0 0.0 0.0
: 20. unit Availability Factor                                                               0.0                         0.0                 36.1
: 14. news ca ator on-I,ine 0.0 0.0 18,468.0 0.0 0.0 0.0
: 21. Unit capacity Factor (Using MDC Net)                                                   0.0                         0.0                 17.3 h     22. Unit Capacity rector (using der set)                                                   0.0                         0.0                 17.3
: 15. Unit Reserve Shutdown Bours
: 23. Unit rorced outage mate                                                           100.0                          100.0                  50.9
: 16. Cross Themal Energy Generated OSfa) 0.0 0.0 9,861,714.4
,g            24. Shutdowns Scheduled over Neat 6 lbaths (Type. Date, and Duration of Each): 850501 through 850615 l9                       1.104 hours, control rod drive refurbishment and circulator bolting changeout.                                                                              .
.17.
, 0 ac 850616                                          4
Cross Electrical Energy Generated Osin) 0 0
  .            25. If Shut Down at End of Report Period. Estimated Date of Startup:
3,248,594 l
26.' 12its In Test Status (Prior to Commercial operation):                                                     Forecast         Achieved a                                                                                                                              N/A             N/A or                                          n:IUAL CRIUCALITT                                                                                                          .
la. set necerical Energy cenerated (isra)
co
-1,966
, ME .                                           I InAL ELECTRICITT                                                                 N/A             N/A I.                                                                                                                                                                     't l
-8,048 2,919,910 i
: l.                                               ConesaCut orsmATIos                                                               N/A             N/A
: 19. Unit S'ervice Factor 0.0 0.0 36.1 0.0 0.0 36.1
: 20. unit Availability Factor 0.0 0.0 17.3
: 21. Unit capacity Factor (Using MDC Net) 0.0 0.0 17.3 h
: 22. Unit Capacity rector (using der set) 100.0 100.0 50.9
: 23. Unit rorced outage mate
: 24. Shutdowns Scheduled over Neat 6 lbaths (Type. Date, and Duration of Each): 850501 through 850615
,g l9 1.104 hours, control rod drive refurbishment and circulator bolting changeout.
, 0 ac
: 25. If Shut Down at End of Report Period. Estimated Date of Startup:
850616 4
26.' 12its In Test Status (Prior to Commercial operation):
Forecast Achieved aor n:IUAL CRIUCALITT N/A N/A co
, ME.
I InAL ELECTRICITT N/A N/A I.
't l
l.
ConesaCut orsmATIos N/A N/A


(.                                                                                                                                                                         TSP-3 Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL                                                                                     hm 2 '
(.
Page 1 of 1 Docket No.                       50-267 Unit                 Fort St. Vrain Date                 May 9, 1985 Completed By                               Frank Novachek Telephone                     (303) 785-2224 l
TSP-3 Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL hm 2 '
Month         Aoril .1985                                                                                                     ,
Page 1 of 1 Docket No.
DAY AVERAGE DAILY POWER LEVEL                                                               DAY AVERAGE DAILY POWER LEVEL (Nie-Net)                                                                                             (NWe-Net) 1                                   0.0                                                       17                                   0.0 2                                   .0                                                       18                                   0.0 3                                   0.0                                                         19                                   0.0 4                                   0.0                                                       20                                   0.0 5                                    0.0                                                         21                                  0.0 6
50-267 Unit Fort St. Vrain Date May 9, 1985 Completed By Frank Novachek Telephone (303) 785-2224 l
0.0                                                         22 0.0 7                                   0.0                                                         23                                   0.0 8                                   0.0                                                       24                                   0.0 9                                   0.0                                                         25                                   0.0                                                                       '
Month Aoril.1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Nie-Net)
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                                   N/A 16                                   0.0
(NWe-Net) 1 0.0 17 0.0 2
.0 18 0.0 3
0.0 19 0.0 4
0.0 20 0.0 0.0 0.0 5
21 0.0 0.0 6
22 7
0.0 23 0.0 8
0.0 24 0.0 9
0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 0.0 28 0.0 0.0 13, 29 14 0.0 30 0.0 15 0.0 31 N/A 16 0.0
* Generator on line but no net generation.
* Generator on line but no net generation.
w         -.+--..m.     . _ , . _ . - - . .    . . _ _ . - - - - _- , . _ . . _ _ . . ~ _ . . , _ . . _ . . . _ - , - - - - - _ _ _         , . . - _ . - _ _ _ _ ~ . . _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ . _ -
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,.. - _. - _ _ _ _ ~.. _ _ _ _ _. _ _ _ _ _ _.. _ _ _ _. _ -


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7
7
            ..~
..~
REFUELING INFORMATION I~       -      -
REFUELING INFORMATION I~
l                           l
l l
                .l 1.       Name of Facility                 'l Fort St.-Vrain Unit No. 1 l l                                           l                           l l 2. Scheduled date for next               l 4th Refueling:             l
.l 1.
                  -l         refueling shutdown.               l February 1,1986 '         l
Name of Facility
                  -l     .            .
'l Fort St.-Vrain Unit No. 1 l
l                            l ll~3.     Scheduled date'for restart.       l May 1, 1986               l
l l
                  'l -       following refueling.               l                           l
l l 2.
                .I                                             l                           l
Scheduled date for next l 4th Refueling:
                ..l   4. Will refueling or resumption ofl No                             l l         operation thereafter require.a l                               l
l
: l.       technical' specification change l                               l
-l refueling shutdown.
_l         or other license amendment?       l                           l l                             .
l February 1,1986 '
l                           l l        _If answer. is yes, what, in       l ----------------           l l       -general, will these be?           l                           l 1           -                        .
l
l                            l-l         If-answer is no, has the reload l-                             l l         fuel design and core configura-l                               l
-l l
                -l         tion been-reviewed by your.       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 ll~3.
                  .l         associated with the core reloadj                               l l       .(Reference 10 CFR Section         l                           l
Scheduled date'for restart.
                  -l         50.59)?                           I                           l l-                                 .        l                           l l         If no such review has taken       l 1985                       l l       ' place, when is it scheduled?     l                           l l-                   ~
l May 1, 1986 l
l                           l l 5. Scheduled date(s) for submit- l                                     l l         ting proposed licensing action-l ----------------               l l       'and supporting information.                                     l 1                                                                         l l . 6.  - Important licensing considera- l                               l l         tions associated with refuel- l                                 l l         ing, e.g., new or different       l                           l l         fuel. design or supplier, unre l ----------------               l l         viewed design or performance       l                           l l         analysis methods, significant l                                 l l         changes in fuel design, new       l                           l l         operating procedures.             l                           l l                           .
'l -
l                            l l 7. The number of fuel assemblies l                                     l l         (a) in the core and (b) in the l a) 1482 HTGR fuel elements     l l         spent fuel storage pool.           I b) 137 spent fuel elements l Y
following refueling.
l l
.I 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 l
_If answer. is yes, what, in l ----------------
l l
-general, will these be?
l l
1 l
l-l If-answer is no, has the reload l-l l
fuel design and core configura-l l
-l tion been-reviewed by your.
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 reloadj l
l
.(Reference 10 CFR Section l
l
-l 50.59)?
I l
l-l l
l If no such review has taken l 1985 l
l
' place, when is it scheduled?
l l
l-
~
l l
l 5.
Scheduled date(s) for submit-l l
l ting proposed licensing action-l ----------------
l l
'and supporting information.
l 1
- Important licensing considera-l l
l l. 6.
l tions associated with refuel-l l
l ing, e.g., new or different l
l l
fuel. design or supplier, unre l ----------------
l l
viewed design or performance l
l l
analysis methods, significant l l
l changes in fuel design, new l
l l
operating procedures.
l l
l l
l l 7.
The number of fuel assemblies l l
l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l
l spent fuel storage pool.
I b) 137 spent fuel elements l
Y


Y?$4                                     _
Y?$4
                                                                                                                            ]
]
    , j .1--                 ,
, j.1--
2 REFUELING INFORMATION (CONTINUED)'
2 REFUELING INFORMATION (CONTINUED)'
                                    -l                                           .
- l
                                                                                    -l                                    l l 8. -- The pre'sent-licensed spent fuell                                         l lL     pool storage _ capacity-and the ~ l     .
-- The pre'sent-licensed spent fuell l
-l l
l 8.
lL pool storage _ capacity-and the ~ l l
- l.
isize of any increase in l Capacity is-limited in size to l-l-
;1icensed: storage capacity-that l about:one-third of core-l
=
-l.
- has been requested or. is _
l (approximately 500 HTGR elements).1
. l'
; planned,.in number of fuel;.
l No change.is planned.
~
l
l
                                    - l. isize of any increase in        .
- l-
l Capacity is-limited in size to    l-
' assemblies.
                =
1 l
                    .'                  l-    ;1icensed: storage capacity-that l about:one-third of core- -
l
l
                                      -l.    - has been requested or. is _        l (approximately 500 HTGR elements).1
-l I
                                              ; planned,.in number of fuel;.
l 9.
                                                                                                                      ~
The' projected date'of-the last.l 1992 under Agreements-AT(04-3)-633l'
l No change.is planned.
. l refueling.that'can be dis-l and-DE-SC07-79ID01370 between-l_
                                    . l'                                                                                l
' l
                                    - l-    ' assemblies.                          1                                    l l              ..  .            _
-charged to the spent fuel pool;l Public Service Company of _
                                                                                .  -l                                    I l 9. The' projected date'of-the last.l 1992 under Agreements-AT(04-3)-633l'
l l
                                    .l         refueling.that'can be dis-           l and-DE-SC07-79ID01370 between-     l_
assuming the~present licensed l Colorado, and General Atomic l-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.                           l Company,-and DOE.*                 l-A 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
capacity.
                                            -the Idahor. Chemical Processing . Plant.
l Company,-and DOE.*
The storage capacity has evidently been' sized to accomodate ;eight fuel           segments. It -is H
l-A 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 Idahor. Chemical Processing. Plant.
The storage capacity has evidently been' sized to accomodate ;eight fuel segments.
It -is H
Jestimated that.the~ eighth fuel segment will be discharged iri 1992.
Jestimated that.the~ eighth fuel segment will be discharged iri 1992.
  +-
+-
4 4
4 4
4
4


e                     .
e 0
0 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION c.
: c. .
MONTHLY OPERATIONS REPORT N0. 135 APRIL, 1985
MONTHLY OPERATIONS REPORT N0. 135 APRIL, 1985
                ' t
' t.
:        :O ;
:O ;
2.
2.


                                                                                                                                                                                                                    ^
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~ ~ i;\\ q
w ys                                                                             .,                      '-                      ~                     .                -
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syg                                                                         .;This s report icontainsf the. highlights s of; ;the Fort St. Vrain, Unit W Noici,Jactivities doperated under the provisions of; the :Nuclea'r D' ' '
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                                                                      ' _ Regulatoryh Coinmiss' ion 10perating License DPR-34. JThis report 'is for
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.;This s report icontainsf the. highlights s of; ;the Fort St. Vrain, Unit W Noici,Jactivities doperated under the provisions of; the :Nuclea'r
' _ Regulatoryh Coinmiss' ion 10perating License DPR-34. JThis report 'is for D' ' '
~
the month offApri.1,:1985.x
the month offApri.1,:1985.x
            ,.                ~
~
7
7
                        'e                       L                         il'.0 NARRATIVE":  
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il'.0 NARRATIVE":  


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE' AND MAJOR ' SAFETY
OF OPERATING EXPERIENCE' AND MAJOR ' SAFETY xYi RELATED MAINTENANCE 4
        =
=
xYi                        -
g
4 RELATED MAINTENANCE g                                                               ;
~The-reheatfstopcheckvalvex-rayingisessentially.completeand
                                                                                ,            ~The-reheatfstopcheckvalvex-rayingisessentially.completeand                                                             '
?,
                    ?,                           X                         ,              ithe': extent of weld repairing: required has beenE determined.                                         The ~'
X ithe': extent of weld repairing: required has beenE determined.
                                                                                    ,          weldGre'pairsJare in progress and.~.will'take!several weeksito
The ~'
              ~")
weldGre'pairsJare in progress and.~.will'take!several weeksito
~
~ ~")
complete. 4Thefvalves.will then.be reassembled and t'ested.
complete. 4Thefvalves.will then.be reassembled and t'ested.
      @',                                                                                  ;TheJControl' Rod / Drive Refurbishment' Program continues. As of 1~                                               ~ fAprill30,<1985,' twenty-five (25) Control-Rod Drives are either in_
;TheJControl' Rod / Drive Refurbishment' Program continues. As of 1~
s < g.                             .- -
~ fAprill30,<1985,' twenty-five (25) Control-Rod Drives are either in_
s < g.
rework or.have been reworked and returned to the core.
rework or.have been reworked and returned to the core.
_f                   .
_f
:                                      *                                .The.J'1A'.:and '1B'' Station Battery' electrolytes'have been changed eand.the batteries-have been'. recharged. .Several dischargeiand                                                           ,
.The.J'1A'.:and '1B'' Station Battery' electrolytes'have been changed eand.the batteries-have been'. recharged.
d,                                    Y                                                     -loa'd ytests: were performed to, test.the batteries' capacity. The
.Several dischargeiand d,
~-:
Y
                                                                                            , batteries were then recharged and are. now being monitored for, specific = gravityNand charge maintenance capability. Both '1A'
-loa'd ytests: were performed to, test.the batteries' capacity. The
                                                                                                                                                                          ~
~ - :
p                                        1 and7-'1B' batteries are operational.
, batteries were then recharged and are. now being monitored for,
                                                                                  ~
~
d .,            -        - -
p 1
                      ,;                                                                      Progress? continues. on' the I-01/I-02 modification for. Human-It is presently-.65% complete.
specific = gravityNand charge maintenance capability. Both '1A' d.,
                                                                                                          ~
~
and '1B' batteries are operational.
7-Progress? continues. on' the I-01/I-02 modification for. Human-4,
: Factors considerations.
: Factors considerations.
4,
It is presently-.65% complete.
                                                                                            .TheKair. compressors continue ' to cause. maintenance problems.
~
                  .y                                         ;        ,                    .Several changes to-the maintenance' rebuild procedure are being
.TheKair. compressors continue ' to cause. maintenance problems.
,            y                                                                          . ; implemented. The results will be evaluated after the' compressors                                                         .
.y
                                                                                              -are returned to service.
.Several changes to-the maintenance' rebuild procedure are being y
Helium > Circulator- '1A'                                   has been replaced in the PCRV, and the aK                                                                                             circulator was returned to service on, April 25,-1985.                                             This circulator had been
. ; implemented. The results will be evaluated after the' compressors
                      -            n                                                                                                                    sent to GA Technologies for ' repair of-a l                  1
-are returned to service.
                                                                                              -bearing waterfinterspace leak. It also had experienced. chloride                                             '
Helium > Circulator-
sm~' :                                                         ,
'1A' has been replaced in the PCRV, and the aK circulator was returned to service on, April 25,-1985.
stress problems 'on some bolting'which has since'been replaced; 1                                                       .          The '.1A' Circulator Main Drain Valve! has been' removed and p                                                                         replaced. with ;a digital valve and electronic controls. This
This n
: l.                                   ,
circulator had been sent to GA Technologies for ' repair of-a
: system 'will be used as a pilot' project to determine the similar' valves
-bearing waterfinterspace leak. It also had experienced. chloride l
                                                                                            -feasibility'                             o f. -   installing                                 on the other
1 sm :
                                                        .                                  ' circulators;
stress problems 'on some bolting'which has since'been replaced;
      ,,                                    ,'                                          '(Helium ' Circulator '18.' has been removed from the PCRV to replace
~'
        ~...                                                                                   interna 1Lbolts. The. circulator ' bolts were replaced and the 1_'t*
1 The '.1A' Circulator Main Drain Valve! has been' removed and p
circulator- was reassembled. The circulator is'now installed in the PCRV,'and leak checked.                                       External piping, assembly is in Mi                                                                  - progress.- ; Helium Circulator                                         '10' piping is being removed in I~fj                                                                             fpreparation'~for Helium' Circulator '10' removal ~ and bolt
replaced. with ;a digital valve and electronic controls. This l.
          .c           .f 1. .-             ,
: system 'will be used as a pilot' project to determine the
                                                                                            'changeout.
-feasibility' o f. -
:,                            e o,78 g                             ,
installing similar' valves on the other
                                                                                                                                                                                                                  ~
' circulators;
                                                                  ..;        ,g           x 7, e: .                                   v va ' -                              -
'(Helium ' Circulator '18.' has been removed from the PCRV to replace
~...
interna 1Lbolts. The. circulator ' bolts were replaced and the 1_'t -
circulator-was reassembled. The circulator is'now installed in Mi the PCRV,'and leak checked.
External piping, assembly is in
- progress.- ; Helium Circulator
'10' piping is being removed in I~fj fpreparation'~for Helium' Circulator
'10' removal ~
and bolt
.c
.f 1. -
'changeout.
e o,78 g
,g x 7,
~
e:.
v va ' -


    -- -                  =,
=,
i._J -                                                                                     -: The . annual . Requalification examinations are in progress. The
i._J - -: The. annual. Requalification examinations are in progress. The
              .                    ~ Nuclear Regulatory Commission .will be on site in ~May         to
~ Nuclear Regulatory Commission.will be on site in ~May to
                                    -administer. -oral, 'and   written examinations to the Nuclear Regulatory Commission selected license holders.
-administer. -oral, 'and written examinations to the Nuclear Regulatory Commission selected license holders.
                                    -Numerous 1 plant design changes are being installed and tested.
-Numerous 1 plant design changes are being installed and tested.
These include but are not limited to, changes on, the purified helium header, circulator auxiliary system monitoring capability p      and human factors control board modifications.
These include but are not limited to, changes on, the purified helium header, circulator auxiliary system monitoring capability and human factors control board modifications.
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 DATA REPORT
p 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 DATA REPORT
          , , .                    : Attached 1[                     '
: Attached 1[
        ' x_-
' (~')
(~') ..                                                                                    ,
x_-
m
m


O PublicService                                                   . ,..
O PublicService Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 May 13, 1985 Fort St. Vrain Unit No. 1 P-85167 Office of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 May 13, 1985 Fort St. Vrain Unit No. 1 P-85167 Office of Inspection and Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267
20555 Docket No. 50-267


==SUBJECT:==
==SUBJECT:==
Monthly Operations Report - April, 1985 l-                                            
Monthly Operations Report - April, 1985 l -


==REFERENCE:==
==REFERENCE:==
Line 270: Line 460:


==Dear Sir:==
==Dear Sir:==
Enclosed pletse find our Monthly Operations Report for the month of April, 1985. -
Enclosed pletse find our Monthly Operations Report for the month of April, 1985. -
Sincerely, J.
Sincerely, J.
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:dr Enclosure cc: Mr. John T. Collins
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:dr Enclosure cc: Mr. John T. Collins
                                                                                %#*     d'd p4   -
* d'd p4 4 a 1
4a 1}}
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Latest revision as of 14:38, 12 December 2024

Monthly Operating Rept for Apr 1985
ML20128C067
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 04/30/1985
From: Gahm J, Novachek F
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85167, NUDOCS 8505280169
Download: ML20128C067 (9)
v • d • e


Text

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TSP-3 Atttchment=3B Iccua 2 v orrunuc un arronT DoCxrt no.

50-267 May 9, 1985 myE Frank Novachek Court.rTzD sf (303) 785-2224 Tztzenowr OPERATING STATUS soTzs Fort St. Vrain 1.

unit na.e:

850401 through 850430 2.

Reporting Period 3.

Licensed Themal Power ()6TC):

842 4 Nameplate Rating (Groes 3Gie):

342 3.

Design Electrical Rating (Met IGle):

330 6.

Mad== Dependable Capacity (Gross leie):

342-7.

Nad-Dependable Capacity Olet late):

330 8.

If Changes occur in capacity Ratings (Items Number 3 Through 7) Since tast Report, Cive Reasons:

None 280 9.

Power Level To Which Restricted If Any (Not pale),

lo. naasons for mastricts es, If any: Per commitment to the NRC, lona term operation above 85% power is pending completion of B-0 startup testing.

T21s Month Year to Date C M ative

11. nova in n porting period 719 2,879 51,144
12. number of a.ua n etor v s Critte.1 0.0 0.0 27,151.4 l
13. manctor meserve shutdown nones 0.0 0.0 0.0
14. news ca ator on-I,ine 0.0 0.0 18,468.0 0.0 0.0 0.0
15. Unit Reserve Shutdown Bours
16. Cross Themal Energy Generated OSfa) 0.0 0.0 9,861,714.4

.17.

Cross Electrical Energy Generated Osin) 0 0

3,248,594 l

la. set necerical Energy cenerated (isra)

-1,966

-8,048 2,919,910 i

19. Unit S'ervice Factor 0.0 0.0 36.1 0.0 0.0 36.1
20. unit Availability Factor 0.0 0.0 17.3
21. Unit capacity Factor (Using MDC Net) 0.0 0.0 17.3 h
22. Unit Capacity rector (using der set) 100.0 100.0 50.9
23. Unit rorced outage mate
24. Shutdowns Scheduled over Neat 6 lbaths (Type. Date, and Duration of Each): 850501 through 850615

,g l9 1.104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, control rod drive refurbishment and circulator bolting changeout.

, 0 ac

25. If Shut Down at End of Report Period. Estimated Date of Startup:

850616 4

26.' 12its In Test Status (Prior to Commercial operation):

Forecast Achieved aor n:IUAL CRIUCALITT N/A N/A co

, ME.

I InAL ELECTRICITT N/A N/A I.

't l

l.

ConesaCut orsmATIos N/A N/A

(.

TSP-3 Attcchment-3A AVERAGE DAILY UNIT POWER LEVEL hm 2 '

Page 1 of 1 Docket No.

50-267 Unit Fort St. Vrain Date May 9, 1985 Completed By Frank Novachek Telephone (303) 785-2224 l

Month Aoril.1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Nie-Net)

(NWe-Net) 1 0.0 17 0.0 2

.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 0.0 0.0 5

21 0.0 0.0 6

22 7

0.0 23 0.0 8

0.0 24 0.0 9

0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 0.0 28 0.0 0.0 13, 29 14 0.0 30 0.0 15 0.0 31 N/A 16 0.0

  • Generator on line but no net generation.

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REFUELING INFORMATION I~

l l

.l 1.

Name of Facility

'l Fort St.-Vrain Unit No. 1 l

l l

l l 2.

Scheduled date for next l 4th Refueling:

l

-l refueling shutdown.

l February 1,1986 '

l

-l l

l ll~3.

Scheduled date'for restart.

l May 1, 1986 l

'l -

following refueling.

l l

.I 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 l

_If answer. is yes, what, in l ----------------

l l

-general, will these be?

l l

1 l

l-l If-answer is no, has the reload l-l l

fuel design and core configura-l l

-l tion been-reviewed by your.

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 reloadj l

l

.(Reference 10 CFR Section l

l

-l 50.59)?

I l

l-l l

l If no such review has taken l 1985 l

l

' place, when is it scheduled?

l l

l-

~

l l

l 5.

Scheduled date(s) for submit-l l

l ting proposed licensing action-l ----------------

l l

'and supporting information.

l 1

- Important licensing considera-l l

l l. 6.

l tions associated with refuel-l l

l ing, e.g., new or different l

l l

fuel. design or supplier, unre l ----------------

l l

viewed design or performance l

l l

analysis methods, significant l l

l changes in fuel design, new l

l l

operating procedures.

l l

l l

l l 7.

The number of fuel assemblies l l

l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l

l spent fuel storage pool.

I b) 137 spent fuel elements l

Y

Y?$4

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, j.1--

2 REFUELING INFORMATION (CONTINUED)'

- l

-- The pre'sent-licensed spent fuell l

-l l

l 8.

lL pool storage _ capacity-and the ~ l l

- l.

isize of any increase in l Capacity is-limited in size to l-l-

1icensed
storage capacity-that l about:one-third of core-l

=

-l.

- has been requested or. is _

l (approximately 500 HTGR elements).1

. l'

planned,.in number of fuel;.

l No change.is planned.

~

l

- l-

' assemblies.

1 l

l

-l I

l 9.

The' projected date'of-the last.l 1992 under Agreements-AT(04-3)-633l'

. l refueling.that'can be dis-l and-DE-SC07-79ID01370 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.

l Company,-and DOE.*

l-A 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 Idahor. Chemical Processing. Plant.

The storage capacity has evidently been' sized to accomodate ;eight fuel segments.

It -is H

Jestimated that.the~ eighth fuel segment will be discharged iri 1992.

+-

4 4

4

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION c.

MONTHLY OPERATIONS REPORT N0. 135 APRIL, 1985

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.;This s report icontainsf the. highlights s of; ;the Fort St. Vrain, Unit W Noici,Jactivities doperated under the provisions of; the :Nuclea'r

' _ Regulatoryh Coinmiss' ion 10perating License DPR-34. JThis report 'is for D' ' '

~

the month offApri.1,:1985.x

~

7

'e L

il'.0 NARRATIVE":

SUMMARY

OF OPERATING EXPERIENCE' AND MAJOR ' SAFETY xYi RELATED MAINTENANCE 4

=

g

~The-reheatfstopcheckvalvex-rayingisessentially.completeand

?,

X ithe': extent of weld repairing: required has beenE determined.

The ~'

weldGre'pairsJare in progress and.~.will'take!several weeksito

~ ~")

complete. 4Thefvalves.will then.be reassembled and t'ested.

TheJControl' Rod / Drive Refurbishment' Program continues. As of 1~

~ fAprill30,<1985,' twenty-five (25) Control-Rod Drives are either in_

s < g.

rework or.have been reworked and returned to the core.

_f

.The.J'1A'.:and '1B Station Battery' electrolytes'have been changed eand.the batteries-have been'. recharged.

.Several dischargeiand d,

Y

-loa'd ytests: were performed to, test.the batteries' capacity. The

~ - :

, batteries were then recharged and are. now being monitored for,

~

p 1

specific = gravityNand charge maintenance capability. Both '1A' d.,

~

and '1B' batteries are operational.

7-Progress? continues. on' the I-01/I-02 modification for. Human-4,

Factors considerations.

It is presently-.65% complete.

~

.TheKair. compressors continue ' to cause. maintenance problems.

.y

.Several changes to-the maintenance' rebuild procedure are being y

. ; implemented. The results will be evaluated after the' compressors

-are returned to service.

Helium > Circulator-

'1A' has been replaced in the PCRV, and the aK circulator was returned to service on, April 25,-1985.

This n

circulator had been sent to GA Technologies for ' repair of-a

-bearing waterfinterspace leak. It also had experienced. chloride l

1 sm :

stress problems 'on some bolting'which has since'been replaced;

~'

1 The '.1A' Circulator Main Drain Valve! has been' removed and p

replaced. with ;a digital valve and electronic controls. This l.

system 'will be used as a pilot' project to determine the

-feasibility' o f. -

installing similar' valves on the other

' circulators;

'(Helium ' Circulator '18.' has been removed from the PCRV to replace

~...

interna 1Lbolts. The. circulator ' bolts were replaced and the 1_'t -

circulator-was reassembled. The circulator is'now installed in Mi the PCRV,'and leak checked.

External piping, assembly is in

- progress.- ; Helium Circulator

'10' piping is being removed in I~fj fpreparation'~for Helium' Circulator

'10' removal ~

and bolt

.c

.f 1. -

'changeout.

e o,78 g

,g x 7,

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e:.

v va ' -

=,

i._J - -: The. annual. Requalification examinations are in progress. The

~ Nuclear Regulatory Commission.will be on site in ~May to

-administer. -oral, 'and written examinations to the Nuclear Regulatory Commission selected license holders.

-Numerous 1 plant design changes are being installed and tested.

These include but are not limited to, changes on, the purified helium header, circulator auxiliary system monitoring capability and human factors control board modifications.

p 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 DATA REPORT

Attached 1[

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x_-

m

O PublicService Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 May 13, 1985 Fort St. Vrain Unit No. 1 P-85167 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 - April, 1985 l -

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed pletse find our Monthly Operations Report for the month of April, 1985. -

Sincerely, J.

Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:dr Enclosure cc: Mr. John T. Collins

  • d'd p4 4 a 1

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