ML20092H255: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[RC-95-0057, Annual Operating Rept for 1994 for VC Summer Nuclear Station Unit 1]]
| number = ML20092H255
| issue date = 12/31/1994
| title = Annual Operating Rept for 1994 for VC Summer Nuclear Station Unit 1
| author name = Taylor G
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
| addressee name = Ebneter S
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000395
| license number =
| contact person =
| document report number = RC-95-0057, RC-95-57, NUDOCS 9509200327
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 9
}}
 
=Text=
{{#Wiki_filter:-
      ;r    p.' 4.
So th Car fina Electric & Gas Company        G        J.T                      ;
Jenkinsville, SC 29065                        Nua. lear Operations -
                    ,                                    (803) 345-4344                                                      *      '
Ascamaxroeny SS MAR      '
EPZ Askuary      27, 1995 Refer to: RC-95-0057
                      - Mr. S. D. Ebneter .
Regional Administrator l                      U. 5. Nuclear Regulatory Commission l-                      Region ll, Suite 2900 101 Marietta Street, N. W.
                      " Atlanta, Georgia 30323
 
==Dear Mr. Ebneter:==
 
i
 
==Subject:==
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12
                                      . ANNUALOPERATING REPORT Attached is the 1994 Annual Operating Report for the South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Unit No.1. This report is being submitted in accordance with Technical Specifications 6.9.1.4,6.9.1.5, and Regulatory Guide 1.16.
if there are any questions, please call at your convenience.
Very truly yours, Ggy . aylor      .
Gar RAM /GJT/nkk Attachment c:      O. W. Dixon R. R. Mahan (w/o attachments) e                              R. J. White f                              G. F. Wunder.
J. B. Knottr Jr.
NRC Resident inspector l'                          ?NSRC-RTS (ANN 2800)
File (818.02-10)-
Central File System s
g
                          .@i nuctexa txctttence - a suxxen-ranorrioni 950920o327 941231                        "                                  /61:
W  d
 
.i 4
w,<
I
 
==1.0      INTRODUCTION==
 
The -Virgil' C. Summer Nuclear Station    (VCSNS)  utilizes a pressurized . water reactor rated at 2775 MWT. The unit has produced a maximum dependable capacity (MWe-Net) ' of 885 MWe.
                      . The - plant is located approximately 26 miles northwest of        ,
Columbia, South Carolina.
i 2.O      OPERATIONAL DATA.
For the reporting period of January 1 through December 31, 1994, the plant operated at a capacity factor of 57.3 percent
                      . (using maximum dependable capacity) and a unit availability of 68.8 percent. The reactor was critical for a total of 6090.5 hours, the generator remained on line 6023.1 huurs, and the total gross electrical energy generated for 1994 was 4,701,600 MWH.
3.0        OPERATING StDe4ARY
                      .The Virgil C. Summer Nuclear Station Unit No. 1 operated at 300 percent power for the entire month of January and until February  9,  when power was reduced to 65%          for  fuel conservation. The plant operated at 65% power for the rest of      I the month. As of the end of February the plant had been on          l line continuously for 302 days. This is a new plant record, surpassing the previous record of 279 days.
The plant was taken off line at 1524 hours on March 1, 1994, to repair hydrogen leaks in the main generator. During this outage the "B" reactor coolant pump seal was replaced and work was performed on the reactor building polar crane to support the upcoming refueling 8 outage activities.
On March 18, at 1223 hours, the main generator breaker was        l closed. Power was maintained at 30% for secondary water chemistry cleanup. On March 21, power was increased to 65% and maintained    at    that  level  until  April    14,  for  fuel conservation. On April 14, power was increased to 72% and remained at 72% until May 7, for fuel conservation. On May 7,      4 power was increased to 100%.                                        I On' June 17, power was reduced to 90% to repair an air leak on a high - load steam supply valve to the moisture separator reheater. The plant was returned to. full power ori June 18. As a result of . the power transient, the plant experienced an
: increased steam generator leakage rate (primary to secondary) from the "B" steam generator. (See Attachment II for a graph of.the leak.)
                                                                                          .i
 
          -      -_ -      .    -.    . .~ - - --    . -.          - - . _ . .  . -        - . . _ . .-
} , . '-
The plant operated at 100% power until July 24, when power was reduced to 90% as part of a strategy to manage the "B" steam generator tube leak and to maintain the circulating water
;                        discharge temperature below the maximum allowable temperature.
;                          The reduced power level also helped to conserve fuel until the
;                          scheduled refueling outage. The "B" steam generator leak rate
;                          was the major plant operational restraint and continued to be
;                        monitored very closely for the rest of the operating cycle.
:                        Contingency plans were developed to address actions to_be taken if the leakage rate was to significantly increase.
The plant continued to operate at 90% power until August 5, when a gradual power reduction was initiated and on August 11, a power level of 80% was established. The power reduction was made in order to further conserve fuel for the remainder of
;                          the operating cycle and to minimize the "B" steam generator tube leak rate.
l                          On September 9,1994, power was reduced and the main generator taken off line to commence Refueling Outage 8.
Cycle 9 initial criticality was achieved at 1012 hours on
;                          December 14th. Physics testing was ' ampleted at 1047 hours on
;                          the 15th and MODE 1 entered at 2350 hours. The generator 4
breaker was closed at 0215 on the 16th. Additional testing was
;                          pe::ormed during the power ascension due to the steam i                          ;r* c rator replacement. 100% power was reached on December 29.
At the end of December the plant was operating at 100 percent l
power.
MAINTENANCE l
l During this reporting period 5168 maintenance work requests
;                          (MWR) were completed requiring 183,260 manhours. There were l                          10,165 preventive maintenance tasks and 7186 surveillance tests performed.
3 i
REFUEL 8
 
==SUMMARY==
 
This was a planned refueling outage with a scheduled duration of 98 days and 4 hours,          with expectation that the main generator breaker would be closed on or before December 17.
During this outage all three Westinghouse model D-3 steam generators were replaced with Westinghouse model Delta 75 steam generators. This required rerouting of the feedwater system piping to the upper portion of the new steam generators
,                          and removal of the feedwater prewarming system. Changing from a variable water level to a single water level in the new i                          steam generators resulted in extensive changes to the plant
!                          instrumentation.
i
                                                                                          = ,,
 
The combined refueling and steam generator replacement outage  !
was completed in 97 days and 3 hours, breaker to breaker. This  I included eight days at the end of the outage to repair a leak on the seal injection line to "C" reactor coolant pump which was discovered on December 13 (LER 940006) during the heatup for plant startup.
The steam generator critical path replacement activities were accomplished.in 38 days. This established a new record for steam generator replacement in the United States. The steam generator replacement activities were accomplished with a total man-rem dose of 224, which also set a new United States record.
In addition to refueling and steam generator replacement the following major work items were completed during the refueling 8 outage:
* Reactor Building Polar Crane Upgrade Rebuilt the crane's mechanical brake, replaced the main and aux. hoist wire ropes, and performed a required structural modification to resolve a Whiting Corporation 10CFR21 notification.
* Motor Operated Valve Testing The requirements of Generic Letter 89-10 initial commitments were completed. 48 motor operated valves were refurbished, 56 were  dp  tested,  and  84  were  statically  tested. This ,
established a new ITI Movats record for the number of valves    I worked in a single outage.
* Snubber Reduction Removed 275 mechanical snubbers of which most were class 1      i snubbers inside containment, 9 hydraulic snubbers from the      I steam generators, and some associated whip restraints based on NRC generic letter 87-11, " Snubber Reduction".
l
* On site rewind of the Main Electrical Generator              I This was the first on site main generator rewind for a 4 pole unit performed by General Electric. It was also the first time induction heating was used for brazing stator bars in the field.
* Installed spare main transformer The main transformer was replaced with a spare main transformer which had been purchased during original plant construction. This required a new extension to the bus bar cooling system.
* Reactor Coolant Pump Motor replacement A spare reactor coolant pump motor was installed thus allowing  i the rotation of reactor coolant pump motors for refurbishment.
.                                                                                l
 
4:-
3 ;,;                    := -
l
                                  *[Replacemen+ of.two-' Reactor' Coolant Pump Seals                          ;
                          < ._ Replaced;the mechanical. seals on'"A" and'"C": reactor coolant
                                                            ~
t' pumps.s The se'al on        "B", . reactor: coolant pump ? was :-replaced
                                'during.the' plant mini-outage in March.
      <          4;O'.- EXPOSURES E Attachment J I consists of tables .which list:the number of station, utility,        and ;other - personnel      (including contract-  :
personnel) ' receiving exposures greater than 100 mrem / year and _
their associated man-ren' exposure accorcing to. work'and: job function.                                                                  .
E
                ~5 . 0'-        FAILED FUEL                                                                l
                                ,Following core offload, 'two fuel rods were identified as                  l
                                ' defective! by., ultrasonic testing and' visual inspection. The
                                .. defects were . debris - induced. One ' rod in assembly K-46, was          :'
from its' initial cycle in the core and the other in assembly-J-64 was from> its second core cycle. - Assembly K-46 was reconstituted and' loaded for cycle 9 and assembly J-64 was.                -
                                = discharged.
The reactor coolant system specific activity did not exceed the 1.0 uCi/ml dose equivalent iodine-131 specific activity              .i
                                            ~
                                  ' limit for this reporting period.                                          ;
i i
i i
f 8
l
          ~
l --
t
  'i a
f s:                                    -
#      E y        q-
 
e t
4 9
e r
ATTACHMENT I TO 1994 N AL REPORT 1
l I
l l
l r
l l
l l
,                                                                                                                                                      i 1
 
e
      .-      .                                                                                            l SOUTH CAROLINA ELECTRIC AND GAS CO. V.C. SUMMER NUCLEAR STATION PEOPLE                . COMPUTERIZED EXPOSURE NUCLEAR TRACKING SYSTEM            PAGE    1      j CNTRPT_PERG116R
                                                                                    '15-FEB-1995 09:04        <
PERSONNEL AND MAN-REM BY WORK AND DUTY FUNCTION FINAL END OF YEAR REPORT FOR 1994 NUMBER OF PERSONNEL OVER 100 MREM          TOTAL MAN-REM STATION UTILITY CONTRACT      STATION UTILITY CONTRACT WORK AND JOB FUNCTION            WORKERS WORKERS WORKERS      WORKERS WORKERS WORKERS ROUTINE MAINTENANCE MAINTENANCE PERSONNEL                47      0      146      11.773      0.026    48.736 OPERATIONS PERSONNEL                  7      0        9      2.557      0.025    2.487 EEALTH PHYSICS PERSONNEL            6      0        57      1.903      0.000    17.287 SUPERVISORY PERSONNEL                0      0        1      0.290      0.000    0.383 ENGINEERING PERSONNEL                3      0        21      1.430      0.000    6.914 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL              16      0      327        6.054      0.020 146.761 OPERATIONS PERSONNEL                  5      0        2      1.675      0.000    0.811 HEALTH PHYSICS PERSONNEL            2      0        3      0.669      0.000    1.880      '
SUPERVISORY PERSONNEL                0      0        2      0.633      0.000    0.755 ENGINEERING PERSONNEL                1      0      104        0.994      0.000    47.135 REACTOR OPERATIONS & SURVEILLANCE 0.000    1.106 MAINTENANCE PERSONNEL                1      0        2      0.632 OPERATIONS PERSONNEL                9      0        1      3.513      0.001    0.402 HEALTH PHYSICS PERSONNEL            6      0        53      2.506      0.000    16.073 SUPERVISORY PERSONNEL                0      0        1      0.126      0.000    0.189 ENGINEERING PERSONNEL                0      0        1      0.102      0.000    0.249 WASTE PROCESSING
,            MAINTENANCE PERSONNEL                0      0        0      0.036      0.000    0.158 OPERATIONS PERSONNEL                0      0        0      0.001      0.000    0.179 HEALTH PHYSICS PERSONNEL            3      0        2      0.957      0.000    1.041 SUPERVISORY PERSONNEL                0      0        0      0.000      0.000    0.015 ENGINEERING PERSONNEL                0      0        0      0.000      0.000    0.000 IN-SERVICE INSPECTION MAINTENANCE PERSONNEL                0      0      33      0.170      0.049    9.688
!            OPERATIONS PERSONNEL                0      0        0      0.481      0.000    0.094 i
HEALTH PHYSICS PERSONNEL            0      0        0      0.020      0.000    0.206
,            SUPERVISORY PERSONNEL                0      0        0      0.046      0.000    0.002 0.323      0.000    5.149 ENGINEERING PERSONNEL                0      0      18 REFUELING FWINTENANCE PERSONNEL                0      0        0      0.021      0.000    0.251 OPERATIONS PERSONNEL                0      0        0      0.085      0.000    0.108
            ' HEALTH PHYSICS PERSONNEL            0      0        0      0.000      0.000    0.119 SUPERVISORY PERSONNEL                0      0        0      0.000      0.000    0.000 ENGINEERING PERSONNEL                0      0        1      0.007      0.000    0.301 i
TOTALS
!            MAINTENANCE PERSONNEL              64      0    508      18.686      0.095 206.700 OPERATIONS PERSONNEL                21      0      12      8.312      0.026    4.081 REALTH PHYSICS PERSONNEL            17      0    115        6.055      ~0.000  36.606 SUPERVISORY PERSONNEL                0      0        4      1.095      0.000    1.344 ENGINEERING PERSONNEL                4      0    145        2.856      0.000  59.748 L        GRAND TOTAL                            106      0    784      37.004      0.121 308.479
          *********** END OF REPORT ***********
 
              +4 h
e 4          M
  . e w
f v
d 4                        ATTACHMENT II TO 1994 ANNUAL REPORT a
4 i
i 4
b 6
l l
l l
l l
v 1
l
 
l
    .-  .                                                                                                                                                              i e                                                                                                                                                                ..
                                                              =                                                                                        5 a        ?
            .                                                  g                              '                                                                  S W                W                                                              E a
m:
i      i a        8 8                                                                                                                                A l
n l                          l 58  l M---*
                                                                                                            -- 7 ~- - - -- --- 0!/60
                                                          ~~      ' ' " -                              ~~-
i        i      i      p,        l    l                    'T'' - r- - ,- -
                                        \l ,
                                                                                                          .3                                      -
p _{_ 4 _ _}_q                            '..
p          q. _l. _.
                                                                                                .[ _
                                                                                                                                ..[.
J..
02/90 1                                                                                            .
I p + _ + + _1 p:+7                                                              .c 74+      .
                                                                                                                                +            _j . . 90/90 e
                                    .                                                                __ 1+
p_ ._ p _ p _ p _j p                              .;        .;    ..;. . _ r.      .j..
y            + . . g;jzo c
p__ _p _p _p _q                          j.      . .
                                                                              .p    .7            7  _ p. . -
                                                                                                                          .c
                                                                                                                                +            _j . _ oc/90
                                                                                                                              '.c.
_                                                                                                  s._ ,
                                                                                                                                      .T      '
p_. _L _}_ 4 _]                           '
                                                                                ;_  _7        _j. _{.            _j        _j_ .. ~ l'/90
                                                                                                                                      ~.        ,
k F_._ _p _{_ _{_ q .....j..,                            ,                        4      j -.          4          j. ?, q.-. 92/90 a
p _. q_                                                                              .j l          j  _j p        ..        .. L.    ;.      .j.                    j        j_            ,    - 40/90 s
1 i
p }_ _{_ _}_ 4 _j '.7
                                                                                                .p.      j          q..            .
                                                                                                                                            @ - 6;/t0
                                                  ~                                                                                        't  I t i
                                                                                                                                              #i I i f i          ,
i        i      i      i        i    ii          T    ~ 'I                  ,    i              ;        r        ' ; --    L O/ t0
                        .o      o. O          o    o            o-        O      O        O    o              o        o            o
                      .O        o      o          O  .o            O        O      O        O    o              o        o            o 9'    q      q          q    q            9        9      9_        Q    O,              O        .O            o o      o      o          o    o            D        O      D        O    c              a        c            o' O      m      to        b    to        ,T-        D      h        O    t.              c        eq e-                                        e        e      v.        e}}

Latest revision as of 03:10, 25 September 2022

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML20092H255&oldid=3492081"