ML20198P299: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[RC-98-0229, Fifteenth Annual 10CFR50.59 Rept for VC Summer Nuclear Station, for Period Ending 970806.With ]]
| number = ML20198P299
| issue date = 08/06/1997
| title = Fifteenth Annual 10CFR50.59 Rept for VC Summer Nuclear Station, for Period Ending 970806.With 981230 Ltr
| author name = Taylor G
| author affiliation = SOUTH CAROLINA ELECTRIC & GAS CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000395
| license number =
| contact person =
| document report number = RC-98-0229, RC-98-229, NUDOCS 9901070023
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 20
}}
 
=Text=
{{#Wiki_filter:6, %                  ,
_m F
gwI                    'Mg
$kt0{. hU;. m? Y                  '
                            '' N                                                                                                ,
V
[ Q[ S . /w pgg;
&?. ow <a L Qt?~
m  . s g, f''
.5                                                                                              December 30,1998                ,
. Ll jr  38CE&G.
X3n * . & i A SCANA COMPANY RC-98-0229
,% h , g (' 3            8, j gM;j g :p          '
            , s pg
@sn %    <*g                Q; n Document Cohtrol Desk p 43, *~ '31 U. S. Nuclear Regulatory Commission .                                                                          '
                              $ Washington, DC 20555 fy &y a t    .                %
$W,                  gdy.] oGentlemen:                                                                                          :
{MWf.    , , pm!                                      VIRGIL C. SUMMER NUCLEAR STATION ppp s ' , 'Q)
 
==Subject:==
          $                      DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 g
$wL
[- @#.My Nigw                                            10 CFR 50.54(a)(3) /10 CFR 50.59(b)(2) ANNUAL REPORT f
%rmd,Wh[
;fo      ub i N sa$        South Carolina Electnc & Gas Company (SCE&G) is subm Report pursuant to 10 CFR 50.59(b) and 10 CFR 50.54(a) for Virgil C. Summer p    T%^,d}w              l Nuclear Station.
i p &p<wVMyj This report contains a brief description of changes and modifications made to the k i NhM !facility, as described in the- Final Safety Analysis Report (FSAR) and the Fire                                    ,
M Protection Evaluation Report (FPER), as well as a summary of the safety evaluations M@E : ~ , . ; Q' j h] performed to evaluate these changes N                                                                      ;
$g Qf i '%3pfhy procedure b
* 9' Non-Conformance                              Notice [NCN] numbers), p numbers) Modification Changes (identified by the Modification Request h@ScX Md Form [MRF] and Modification Change Notice [ MON] numbers) and Engineering tiicHosM Change Requests (identified by the Engineering Change Request [ECR] numbers) 5ewh(edap%wSym?
K5mm                                              were completed during the time frame of one year prior to August 6            '
f 0.h44L 41 % ended the fifteenth year following the issuance of the VCSNS Operating License.
There. were no reportable changes to the quality assurance program during this Wg[_            '
                        %]ypenod.
MM4%          ',1              i3 Should you have any questions, please call Mr. Donald L. Jones at (803) 345-4480.
i403315.5209w -
%mW                            G-i t
hW          4        r    #j p15l          '
Very ruly.yours,              [
                                                                                                                                ^
h"      +
%y','",Mb-)f
* h .'.
: h.        f    43 UCuOC4                                              h 7% g h                                                                              Gary J. Taylor          /~      ;
g% h          '
Wd                                                                                              hL    '
M{#Q mp          ,
                                    , ; W q DLJ/GJT/dr-
                            > Q Enclosure W:Q% b 1J. L. Skolds C
gppI    9lc M    7%Q g &g                            /g c:-
W. F. Conway NRC Resident inspector J. B. Knotts, Jr.              !
                                            . R. R. Mahan (without Enclosure)                    RTS (RR-8450)                  l
  $$fMkd.M$
  % - g4W:                        ';        ' R.~J. White -                                    File -(818.02-8)
N        hjMff d8 .. vCT ' T;d L. A. Reyes ,
                                            . L. M. Padovan -
DMS (RC-98-0229)
S        EgMq f      M6Mhd                                        NUCLEAR EXCELLENCE - A SUMMER TRADITION! .
L                                                          1 mneer    F        748!!!                    m  *= %      a  .
 
i Enclosura td Docum:nt Control Desk Lett:r RR 8450 RC-98-0229 Page 1 of 19 i
r t
4 FIFTEENTH ANNUAL 10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION i
a 1
i I
1 l
i s
W
                            - +                      -                  -_m___._    _ _____ __ _ _ _ . ___ _ _._
 
Enclosuro to Docum:nt Control Desk Lett:r -
RR 8450 RC 98-0229 l            Page 2 of 19 i
FIFTEENTH ANNUAL 10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION t
i~
Acronyms and abbreviations used throughout this report are listed on the last page.
i-j            Identification No.                               
 
== Description:==
;            FSAR RN 95-05                                      This change to the FSAR revised Section 9.3.1 to correct                  '
:                                                              inconsistencies in design and operational information for i                                                              the Spent Fuel Cooling System. This change does not i                                                              involve any unreviewed safety questions.
!            FSAR RN 95 34                                      This change to the FSAR identified several additional Rev.1                                              figures and sections to reflect the changes performed
!                                                              under MRF 21073 (previously reported in the 14th Annual
                                                              ' Report). This change does not involve any unreviewed
;                                                              safety questions.
i
:            FSAR RN 95-37                                      This change to the FSAR revised FSAR Figures 6.2-68, 6.2-76,6.2-79, and 10.4-12 to reflect the changes performed under MRF 90003 (reported in the 13th Annual Report). These changes do not involve any unreviewed
;                                                              safety questions.
E            FSAR RN 95-38                                      This change to the FSAR revised Section 11.6 to state that the Offsite Radiological Monitoring Program is i                                                              described in the Offsite Dose Calculation Manual (ODCM) instead of referencing the Operating License Environmental Report (OLER). Technical Specification                      ;
Administrative Control 6.8.8.(f) requires that an environmental monitoring program be established
:                                                              consistent with Appendix l to 10CFR50 and be contained 7                                                              in the ODCM. It is therefore appropriate that the FSAR reference the ODCM for the description of the
,                                                              - Radiological Environmental Monitoring Program. This change does not involve any unreviewed safety questions.
4 4
4 e
er                                                  w-w  e.g    s,              w- 6 w  -  w we                  p        w- +--
 
        " Enclosure td Docum:nt Control D si. Lattar RR 8450 RC-98-0229 Page 3 of 19 Identification No.     
 
== Description:==
 
FSAR RN 95-40            This change to the FSAR alicwed the use of oxygen scavengers other that hydrazine. This change affected FSAR Sections 10.3.5,-10.4.8.1.3,10.4.8.1.5, and 10.4.8.1.6. This change does not involve any unreviewed safety questions.
FSAR RN 96-04            This change to the FSAR revised Figure.1.2-1 that was Rev.1                    not previously included in FSAR RN 96-04 Rev. O and MRF 22337 (reported in the 13th Annual Report). This change does not involve any unreviewed safety questions.
FSAR RN 96-10            This change to the FSAR revised Figure 1.2-15,12.1-19 and 12A.4-7 to reflect changes to partition walls for an office area. This change does not involve any unreviewed safety questions.
FSAR RN 96-13            This change to the FSAR revised Figures 5.5-4 and 6.31 FSAR RN 96-58            to show compression fittings installed to facilitate drainage and LLRT. These changes do not involve any unreviewed safety questions.
FSAR RN 96-15            This change to the FSAR revised Figure 5.2-8 to reflect the change to the Residual Heat Removal System under l                                  ETBT-404, replacing the existing drain valves with larger ones and adding isolation valves. This change does not involve any unreviewed safety questions.
FSAR RN 96-16            This change to the facility installed hardware in the MRF 22740                refueling macliine needed to support in mast fuel sipping for failed fuel detection. This change affected FSAR Sections 9.0,9.1.4.2.2.1 and 9.3.5 and Figures 9.1-14 and 9.3-43. These changes do not involve any unreviewed safety questions.
l.
 
  ,, *
* Enclosuro to' Document Control Desk Lcitar RR B450 RC-98-0229 Page 4 of 19 Identification No.     
 
== Description:==
 
FSAR RN 96-19            These changes to the FSAR revised several figures as Rev.1 - 6                  part of the FSAR reconciliation project and included MRFs MRF 21740                  21632D,21740, 21746, MONS 21746A-D, 22362, MRF 21746                  22640, and 34889. MRF 21740 added bypass and drain MCN 21746A D              lines to allow draining portions of the SW System from MRF 22640                  outside the RB. MRF 22640 updated documentation on various system valves. MRF 21746 and associated MCNs 21746A D installed bypass lines on HVAC chiller SW outlet piping for better cold weather control. These changes do not involve any unreviewed safety questions.
FSAR RN 96 21            This change to the FSAR revised Figures 1.2-1, 2.4-1, 2.4-6,2.1-3, and 9.5-1 as well as Sections 1,2,3,9 and 11, to reflect the changes performed under MRF 90008 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-22            This change to the plant installed permanent removable MRF 21628                shielding around the RHR and SI piping in various areas MCN 21628A                of the plant. This change affected FSAR Figures 12.1-1, 12.1-10, and 12.1-12 and Table 3.2-2. These changes do not involve any unreviewed safety questions.
FSAR RN 96-23            This change to the FSAR r vised Figure 9.4-11 to remove MCN 22679D                the High Delta-P alarm switch from the Fuel Handling Building HVAC System. This change does not involve any unreviewed safety questions.
        . FSAR RN 96 24            This plant change replaced the obsolete seismic l          MRF 22665                instrumentation with a solid-state instrumentation system.
This change affected FSAR Section 3.7.4, Tables 3.7-10 and 3.7-11, and Figures 3.7-49 and 3.7-50. These changes do not involve any unreviewed safety questions.
FSAR RN 96-25            This change to the FSAR revised Figure 1.2-16 and 12.1-19A to reflect the changes performed under MRF 22741 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
l
 
    ' , - Enclosuro to Documsnt Control Desk Lcttar RR 8450 RC-98-0229 Page 5 of 19 Identification No.       
 
== Description:==
 
FSAR RN 96-26              This change to the FSAR affected Section 9.3.4, Table 3.9 8, and Figures 9.3-16 sheets 2,4, and 5, and 9.4-8, to reflect the changes performed under MRF 21511 (previously reported in the 12th Annual Repor1). These changes do not involve any unreviewed safety questions.
FSAR RN 96-27            This change to the FSAR affected Sections 9.4.8. This change provided a method for cooling the Reactor Vessel Cavity in the event of a loss of both Reactor Cavity Cooling Fans. This change does not involve any unreviewed safety questions.
FSAR RN 96-28            This change to the FSAR revised FSAR Figures 9.2 9b FSAR RN 96-30            and 10.4-8 to reflect the changes performed under MRF MRF 90109                22293 (previously reported in the 14th Annual Report).
MCN 90109A                Additionally, MRF 90109, MCN A installed flow conditioning devices used to improve the condensate suction flow patterns. These changes do not involve any unreviewed safety questions.
FSAR RN 96-29            This change to the FSAR revised FSAR Figures 9.3-18 and 11.2-2, Sheet 2, to show manual isolation valves as normally open for the boron recycle and waste evaporator concentrate drain lines. These changes do not involve any unreviewed safety questions.
FSAR RN 96-31            This change to the FSAR revised FSAR Figures 1.2-4, 1.2-5,1.2-16,9.4-1,9.4-10 and 9.3 9 and FSAR Section 9.4 to reflect the changes performed under MRF 22009 (previously reported in the 12th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-33            This change to tne FSAR revised Sections 3.5,9.4, and Figures 1.2-16, 9.4-22 through 9.4-24 to reflect the changes performed under MRF 22114 (previously l                                    reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
1 I
t                                                          - - - - _ _ _ _ _ _______ ___________ _ ____
 
Enclosuro to Document Control Desk Letter RR 8450 RC-98-0229 Page 6 of 19 Identification No.                                                                         
 
== Description:==
 
FSAR RN 96-34                                                                                This change to the FSAR revised Section 1.2 and Figures 1.2-1,1.2-5 through 1.2-7,1.2-12,1.2-13, aril 1.2-26. to reflect the addition of the MRF 90002 modihca; ions (previously reported in the 14th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-35                                                                                This change to the FSAR revised Figure 11.2-2, Sheet 1 to reflect the changes performed under MRF 22766 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96 36                                                                                This change to the FSAR revises Figure 1.2-7 to reflect ECR 50015                                                                                    the removal of the Polar Crane " Parked Position" from the plant drawing and FSAR figure. The removal of this
                                                                                                          " Parked Position"was evaluated under ECR 50015. This change does not involve any unreviewed safety questions.
FSAR RN 96-37                                                                                This change to the FSAR revised Figure 10.1-2,10.1-3, and 10.2-2, and Sections 3.5 and 10.2 to reflect the changes performed under MRF 22553 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-38                                                                                This change to the FSAR affects Section 9.1.4.2.1 to change the reference to sampling of boron concentration as specified in the Technical Specifications from daily to once per 72 hours, to agree with the Technical Specification sampling frequency. This change does not i                                                                                                          involve any unreviewed safety questions.
l FSAR RN 96-39                                                                                This change to the plant revised the alarm logic for the l            MRF 22467                                                                                    " Improper Lineup" alarm on the Liquid Waste System implemented under the MRF. This change affected FSAR Figure 10.4-17. These changes do not involve any unroviewed safety questions.
 
Enclosure to Documsnt Control Dcsk Letter RR 8450 RC-98-0229 Page 7 of 19 Identification No.     
 
== Description:==
 
FSAR RN 96-40            This change to the FSAR revised Figures 9.2-4,9.2-7,9.4-FPER RN 96-40            23, and 9.4-27, Sections 3.9,6.3,9.2,9.3, and 9.4, and FPER Figure E-023-007 and Sections 3.2 through 3.4, 4.2,4.4, and 4.5, to reflect the changes performed under MRF 22594 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-41            This change to the FSAR revised various Sections and Tables to reflect the changes performed under MRF 20051 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-42            This plant change increased core output power to 2900 FSAR RN 96-48            MWt. The FSAR was also revised to reflect the plant FSAR RN 96-76            changes performed under MRF 90102. The changes MCN 90102A-D              affected FSAR Figures 9.2-2,9.2-4, 9.3-1,10.3-1 through ICP-240.156              10.3-4,10.4-5,10.4-7A through 10.4-12,15.4-83 through Rev.1C                    90 and Section 15.4, as well as Table 15.4-19. The change to the procedure revised the programming and calibration requirements for Chessell Model 344 and 345 recorders to reflect instrument setpoint changes performed under MRF 90102, MCN D. These changes do not involve any unreviewed safety questions.
FSAR RN 96-43            This change to the FSAR revised Sections 4.1,4.2,4.3, MRF 22764                and 4.4 to reflect the changes performed under core l                                        design MRFs 22308 (previously reported in the 12th l
Annual Report), 22593 (previously reported in the 13th
!                                        Annual Report), and 22764. These changes do not l                                        involve any unreviewed safety questions.
FSAR RN 96-44            This change to the FSAR revised Sections 1.2,9.3 and 10.4, Figures 1.2-1,1.2-18,1.2-20,1.2-21,1.2 28,2.4-6, 9.2 8, 9.2-9A,B, and 10.4-5 through 10.4.8, as weil as Tables 10.4-3 and 10.4-9, to reflect the changes performed under MRF 90105 (previously reported in the 14th Annual Report). These changes do not involve any unreviewed safety questions.
 
Enclosure to Document Control Desk Lett r RR 8450 RC-98-0229 Page 8 of 19 Idgntification NA                                       
 
== Description:==
 
f FSAR RN 96-45                                              This change to the FSAR revised Figures 9.2-8 and 9.2-9A,B to reflect the changes performed under MRF 21655 (previously reported in the 12th Annual Report). These      l changes do not involve any unreviewed safety questions.
FSAR RN 96-46                                            This change to the FSAR revised Figures 9.2-8 and 9.2-9A,B to reflect the changes perfoi ned under MRF 22657      ;
(previously reported in the 13th Annual Report). These      !
changes do not involve any unreviewed safety questions.
FSAR RN 96-47                                            This change to the FSAR revised Figure 9.2-8,9.2-9A,B
\
J            MRF 22023                                                  and Section 9.2 to reflect the changes to 1% Water
            . MCN 22023A                                                Treatment System performed under MRF 22023 and MCN 22023A. These changeo do not involve any unreviewed safety questions.
FSAR RN 96-49                                            This change to the plant modified the operator break areas FPER RN 96-49                                            of the Control Room. This change affected FGAR Figures MRF 22288                                                9.41,1.2-15,12.1-19,12A.4-7, and 13.5-1, and FPER Figure E-023-018. These changes do not involve any unreviewed safety questions.
FSAR RtI 96-50                                            This change to the FSAR revised Figures 1.2-15,12.1-19 and 12A.4-7, and Sections 1.2,12.1, and 12A.4, to reflect the changes to curbs in the Radiation Protection areas performed under MRF 21546. Thes9 changes do not' involve any unreviewed safety questions.
FSAR RN 96-51                                            This change to the FSAR revised Figures 8.2-2B,C and Section 8.2 to change terminology used for circuit breakers. These changes do not involve any unreviewed
;,                                                                    safety questions.
FSAR RN 96 52                                            This change to the FSAR revised Figures 1.2-1 and 2.4-6 MRF 22753                                                to reflect changes made to the facility for vehicle barriers performed under MRF 22753. These changes do not involve any unreviewed safety questions.
                                                                                                                                    )
 
l                      ,.        .
o        " Enclosuro to Document Control Desk Letter
          ~
              ' RR 8450 -                                                                                                  l' RC-98-0229 ~
              . Page 9 of 19 '
Identification No.               
 
== Description:==
L
[.              FSAR RN 96-53                    This change to the FSAR revised Section 9.3 to reflect the f
addition of air accumulators to the Diesel Generator                    !
Cooler Fire Service Supply Valves (XVG-3105A/B) i                                                performed under MRF 20787. These changes do not
[                                                  involve any unreviewed safety questions.                                ,
FSAR RN 96-57                    This change to the facility increased the design                        !
temperature of the portion of the EFW system piping from                i I
the EFW Pumps to the Steam Generators from 95'F to .                    -
l                                                  150*F. This change affected FSAR Figures 10.4-12 and                    -
i                                                  10.4-16. These changes do not involve any unreviewed j                                                safety questions.                                                        :
i This change to the FSAR revit..d Figure 9.3 9 to reflect FSAR RN 09-59 the changes performed under MRF 20167 (previously
: 1.                                                reported in the 7th Annual Report). These changes do not                .
involve any unreviewed safety questions.
;              FSAR RN 96-60                    This change to the facility replaced the Pressurizer Heater circuit breakers with fusable disconnects. This change MRF 22074
[                                                  affected FSAR Figure 8G-4. These changes do not
~
involve any unreviewed safety questions.
t
:              FSAR RN 96-61                    This change to the FSAR revised Figure 10.4-8 and                          j Sections 5.5 and 10.4, to reibet the changes performed                  i under MRF 90010 (previously reported in the 13th Annual j                                                  Report). These changes do not involve any unreviewed                    )
:                                                  safety questions.                                                        )
i                                                  This change to the FSAR revised Figure 9.2-9 and 9.2-9B FSAR RN 96-62                                                                                              j to reflect changes performed under MRF 21657                            i (previously reported in the 12th Annual Report). These                  ;
changes do not involve any unreviewed safety questions.                  l l
FSAR RN 96-63                      This change to the FSAR revised Figure 9.2-5 to reflect                  l changes performed under MRF 20285 (previously                            )
reported in the 12th Annual Report). These changes do                    !
not involve any unreviewed safety questions.
i
                                                                                                                            )
i
_- ::: _            _a______--______.                    -    -                        .                        .
 
      ^'
Enclosura ts Document Control Desk Lett:r RR 8450 RC-98-0229 -
Page 10 of 19-Identification No.-                . D.escription:
FSAR RN 96-65                          This change to the FSAR revised Section 6.2 to reflect the changes performed under MRF 90010 (previously reported in the 13th Annual Report). These changes do not involve any unreviewed safety questions.
FSAR RN 96-66                        -This change to the FSAR revised Table 5.2-1 to change the ASME code year and addenda for the Pressurizer          j
                                                                                                              ~
Relief piping. This change does not involve any unreviewed safety questions.                                ;
FSAR RN 96-67                          This NCN added more specific operator actions to limit NCN 5465 '                            EFW leakage to a faulted S/G following a secondary side break. This change affected FSAR Section 10.4.9.3.
These changes do not involve any unreviewed safety            I questions.
i FSAR RN'96-68                          This change to the FSAR updated Appendix 3A to denote        h the number of steam generators inspected in the first
,                                                inspection interval following the steam generator            !
!                                                repiccoment project. This FSAR change was made to            l
;                                                agree with the change made to Technical Specification 4.4.5.1, in support of S/G replacement. These changes do
[                                                not involve any unreviewed safety questions.
1
!        FSAR RN 96-69                          This change to the facility deleted the automatic closure of  ,
[        MRF 22263                              the VCT purge isolation valve to prevent trips of the        l on-line waste gas compressors. This change affected FSAR Figure 11.3-4 and Section 9.3.4. These changes          ;
:                                                do not involve any unreviewed safety questions.              ,
I
,        FSAR RN 96-71                          This change to the FSAR revised Section 15.3.5 to reflect    !
h                                                the analysis basis for Technical Specification 3.11.2.6.
[                                                This change reduces the Waste Gas Dscay Tank curie          .
limit to 131,000 Cl. These changes do not involve any        i unreviewed safety questions.
        . FSAR RN 96                      This change to the FSAR revised Figures 15.4-71 through L.                                              15.4-73, Sections 6.2 and 15.4, and Tables 15.4-6 and 15.4-7, to reflect the update of the hydrogen generation t
                                                .and control analyses. These changes do not involve any unreviewed safety questions.
4
              -~-._..___..__A..--.. A __-__a                            ,r--          ,-  +        ~ ~ v
 
1 h
H, ,
      ' l Enclosurs to Document Control Desk Lett:r I                  -98 229-Page 11 of 19 Identification No.         
 
== Description:==
 
FSAR RN 96-79                This change to the FSAR revised Figure 9.2-24 and -
Section 9.2.7 to reflect the changes performed under MRF      )
                                        . 22769 (previously reported in the 14th Annual Report).        1 These changes do not involve any unreviewed safety questions.
          ' FSAR RN 97_-02              This change to the facility installed permanent AP gages in MCN 21746E                  each of the three Chiller Rooms for use in setting the Service Water flows through the HVAC Chillers. This
* change affected FSAR Figure 9.2-2. These changes do not involve any unreviewed safety questions.
FSAR RN 97-06                This change to the FSAR revised Section 9.2.2 to reflect    :
the changes to the CCW Booster Pump autoGtart setpoint      :
as part of the FSAR reconciliation project. This change does not involve any unreviewed safety questions.
FSAR RN 97-00                Revised the Penetration isolation Verification Procedure to STP-115.001                  add provisions for draining of penetrations to meet the Rev.12A                      requirements of GL 96-06. This change affteted FSAR Section 6.2 and Table 6.2-53. These changes do not          .
involve any unreviewed safety questions.
            ' FSAR RN 97-10              This change to the FSAR revised Sections 3.5,5.2,6.3, 12.2, and 12A, and Tables 3.5-2,6.3-3,6.3-7,6.3-9,12.2-4, and 12A.3-1, to reflect the changes performed under      ,
MRF 20482 (previously reported in the 5th Annual Report). These changes do not involve any unreviewed        :
safety questions.
FSAR RN 97-11              This change to the FSAR revised Figure 9.2-9B and Section 9.2-3 to properly label root, drain, and vent valves in the Domineralized Water System. These changes do not involve any unreviewed safety questions.
FSAR RN 97-17              This change replaced failed level probes in the Leak        ;
            ~ MRF 34428                    Detection System with newer, more reliable switches. NCN DNCN 5304                    5304 provided the justification for temporarily accepting c                                      the failed level probes until replacement under the MRF.
This change affected FSAR Sections 6.3 and 7.6. These changes do not involve any unreviewed safety questions.
[N '.
N,
    ^$l                        (. :
 
Enclosure to Document Control Desk Lett2r RR 8450 RC-98-0229 ~
Page 12 of 19 E            Identification No.            Qescription:                                                                -
i      ,
FSAR RN 97              This change to the FSAR revised Table 3.9-8 and Section l                                          3.9 to reflect the changes performed under MRF 90003 1                                          (previously reported in the 13th Annual Report). These j                                          changes do not involve any unreviewed safety questions.                    -
i
~
            . FSAR RN 97-21                This change to the FSAR separates the procedure for i                                          lifting the reactor vessel head from the procedure for filling j                                          the refueling cavity, and provides for filling the cavity via              '
9 the spent fuel cooling pumps. This change affected Section 9.1.4. These changes do not involve any unreviewed safety questions.
{
i            . FSAR RN 97-23                This change to the facility replaces the main telephone
!,            ECR 50043                    switches. This change affected FSAR Section 9.5.2.                          t i                                          These changes do not involve any unreviewed safety questions.
FSAR RN 97-28                This change to the FSAR revised Section 10.4 and Table 10.2-0 to reflect the changes performed under MRF 20726                      i (previously reported in the 7th Annual Report). These                        l I
changes do not involve any unreviewed safety questions.
FSAR RN 97-29 ~              This change to the FSAR revised Section 6.2.2 to update the incore instrumentation pit volume for use in the RB flooding analysis. This change does not involve any unreviewed safety questions.
FSAR RN 97-35                This change to the facility upgrades the chemistry MRF 22024                    sampling instrumeitts in the Water Treatment Plant. This                    ,
change affected FSAR Figure 9.2-9 and Section 9.2.3.
These changes do not involve any unreviewed safety questions.
FSAR RN 97-39                This change to the FSAR revised Sections 1.2.3 and 9.2.1                    i to reflect the changes performed under MRF 10759                            )
(previously reported in the 4th Annual Report). These                        j changes do not involve any unreviewed safety questions.
l l
l l
: w.                                                                                      -          -
* i Enclosura to Docum:nt Control Desk Lett:r
                  ' RR 8450
                    ' RC-98-0229
!.                  Page'13 of 19-g                    identification No.        Descript,igrn FPER RN 97-12            This plant change installed Appendix R fire switches on MON 22594Q                XPP-0001B and XPP-00010 in the CCW System. The FEP-1.0                  Fire Emergency Procedure and the Fire Switch Lineup
!'                  Rev.90                    Verification Prm:edure were revised to reflect these new STP-170.004              fire switches. This change also affected FPER Section Rev.1C                    4.5. These chariges do not involve any unreviewed safety F                                              questions.
b                    MCN 20951E                This change to the facility installed portions of the new fire                  ;
;                                              protection and contron system in the Nuclear Operations
!                                              Building, the Warehouses, the Craft Training Building, the Radweste Laundry Room, the Compactor area, the                                  '
;                                              Mechanical Maintenance Suilding, the Turbine Generator Exciter Housing and the Circulatin0 Water intake Structure. This MON installed new local control panels, conduit and cable, manual alarm stations and audible appliances, and pressure switches. These changes do                              i not involve any unreviewed safety questions.                                    1
                                                                                                                              )
MRF 2:1726                This change to the facility installed a post indicator valve                    )
in the fire service loop to allow instal!ation of a sprinkler                  I system to a site support office building. This change                            i affected FSAR Figure 9.5-1, Sheets 1 through 5, and Section 9.5. These changes do not invo!ve any unreviewed safety questions.
                                                                                                                              ]
MRF 22767                This change to the facility installed new conduit and MON 22767A,8            cables to support the installation of the Emergency information System. This change affected FSAR Figures 1.2-16 and 12.1-19A. These changes do not involve any unreviewed safety questions.
1 l
j_
          'I                                                                                ___-____-____--__:__-__________,
 
Enclosura to Document Control Desk Lett:r RR 8450-                                                                                          >
RC 98-0229 :
                ' Page 14 of 19 Identification No.           
 
== Description:==
MRF 34911                        NCNs 4894 and 4911 earlier identified discrepancies NCN 4911 =                      between the hydraulic calculations and actual field NCN 4894                        conditioris for the Control Building Preaction Fire Suppression System, and conditions where the hydraulic            '
demand exceeded the available capacity. These NCNs provided technical justification for allowing the system to remain as is until long term design changes could be made. MRF 39411 provided a complete reanalysis of the s'                                                Preaction Fire Suppression System and specified modifications to the system to provide for more efficient use of the flow capacity available to the system. These
!~                                                changes do not involve any unreviewed safety questions.
j:                ECR 50002                        This change to the facility installed new fiber optic            ,
i                                                  communications equipment to replace microwave                    >
l
                                                  - equipment which was removed. This change affected
!                                                  FSAR Figure 1.2-16 and Section 9.5.2. These changes
;                                                  do not involve any unreviewed safety questions.                  .
;                ECR 50019                        This change to the facility removed the PAP electrical and g                                                  support equipment prior to demc!ition of the PAP. This
:                                                  change affected FSAR Figure 2.4-6. These changes do not involve any unreviewed safety questions.
ECR 50028            S          - This change replaced the existing Industrial Cooling Water i                                                  System Cooling Towers with more efficient models. The scope of the modification included changes to the j                                                  Industrial Cooling Water System piping, changes to the j                                                  tower support structures, and evaluations of the
<                                                  implementation of the project while the p unt was at power operation. These changes do not involve any unreviewed i                                                  safety questions.
i                  ECR 50044                      This change installed several security delay fences with personnel and vehicle access gates to enhance the
:                                                  VCSNS Security Department's defense of the plant.
i_                                                These changes resulted from preparaCcas for the
:                                                  Operational Safeguards Response EVAation (OSRE).
;.                                                These changes do not involve any unreviewed safety l                                                  questions.
4 4          i
                        .a ..      ,
[
 
l 3 ..    ' (* Enclosure to Docum:nt Control Desk Lett:r RR 8450, l'
RC-98-0229
;            Page 15 of 19                                                                                      l l
!            Identification No.             
 
== Description:==
i            ECR 50045                        This change installed several anti-ballistic shields            1 L                                            throughout the plant to enhance the VCSNS Security              ,
;.                                            Department's defense of the plant. These changes 1
resulted from preparations for the OSRE. These changes
;                                            do not invcive any unreviewed safety questions.
,                                                                                                            i l            ECR 50046'                      This change installed several security door delay devices l                                            to enhance the VCSNS Security Department's defense of            i
;                                            the plant. These changes resulted from preparations for l                                            the OSRE. These changes do not involve any unreviewed safety questions.
: l.                                                                                                            ;
!            ECR 50047                        This ECR removed three doors from the plant in order to l                                          . enhance the VCSNS Security Department's defense of the plant. These changes resulted from preparations for the          ;
OSRE. The ECR evaluated the removal of the doors and              ,
provided details for closure of the doorway openings with        !
j                                            reinforced concrete and concrete masonry. This change            i
;                                            does not involve any unreviewed safety questions.
ECR 50054                        This plant modification changed the high concentration alarm setpoints for Waste Gas Recombiner H2 and O2              ;
inlet analyzers to alarm to meet Technical Specification          ,
requirements. These changes do not involve any unreviewed safety questions.                                      ;
ECR 50059                        This change to the facility added he Leading Edge Flow Meter temperature and flow devices on the Main Feed Water System. This change affected FSAR Figure 10.4-11. These changes do not involve any unreviewed safety questions.
Railspur Removal                This change removed several sections of railspur track PO N667149                      which had not been used in many years and had become            :
e                                            unnecessary. The rail material was removed for salvage purposes. This change affected FSAR Figures 1.2-1 and 2.4-6. This change does not involve any unreviewed safety questions.
l l
  =
 
L
          'E
: Enclosurs to Docum:nt Control Desk Lett:r
                  ' RR 8450 L                : RC-98-0229
                  ' Page 16 of 19 i                . Identification No.           
 
== Description:==
 
l
: j.                ' NCN 96-0301 L                  This NCN accepted a potential condition of the Alternate FEP-4.0                        High Head SI Cold Leg Recirculation Valve spuriously
;                  Rev. 2C -                      opening during a fire vue to a hot short. The Fire
:                                                  Emergency Respons.s Procedure was revised to provide
,                                                  compensatory action. These changes do not involve any                '
unreviewed safety questions.
l EPP-100                        The Radiation Emergency Plan was revised to reflect that Rev 38                        the Emergency Offsite Facility would be activated at a Site
!-                                                Area Emergency or higher classification. This change to i                                              _ the Radiation Emergency Plan does not decrease the
:                                                  effectiveness of the plan.
i                  EPP-100                        The Radiation Emergency Plan clarified existing Rev. 39                        commitments with editorial changes and reflected the deletion of the ERONS System for emergency response notification. This change to the Radiation Emergency Plan            ,
does not decrease the effectiveness of the plan.
ES-560,120                    Revised the procedure for Feedwater flow rate and                      l
!            ,    Rev.1                          temperature normalization surveillance to change the
['
methods for adjustment of temperature normalization constants and presents a new adjustment for a constant
                                                ~ for normalizing Feedwater flow rate. These changes do j                                                  not involve any unreviewed safety questions.                        j i                  FEP-4.0                        Revised the procedure for Control Room evacuation due i                  Rev. 2B                        to a fire to refer to starting the CCW Pump using the local Appendix R Stop/ Start switch. This change does not j                                                  involve any unreviewed safety questions.
HPP 626                        Deleted the procedure for the calibration and use of the Rev. 2B                        Eberline HFM 6 (hand and foot monitor) because this type monitor has become obsolete. This change does not
;.                                                involve any unreviewed safety questions.                              l PSP-100.                    - This revision to the Physical Security Plan clarified Amendment 59                    existing commitments and specified access control options in support of the PAP demolition. This changa to the Physical Security Plan does'not decrease the safeguards effectiveness of the plan.                                            !
                                >i i    ,                        A[                                ______.___u______________
 
l
              ~
    - .        4 Enclosuro t6 Docum:nt Control Desk Lctt:r
            , . RR 8450                                                                                                    )
RC-98-0229 -
Page 17 of 19 r
i identification No.             
 
== Description:==
 
;                PSP-100 ~                        This revision to the Physical Security Plan clarified Amendment 40                    existing commitments and reflected changes implemented i'                                              - in support of the OSRE modifications and the Vehicle                    :
'                                                  Barrier System installation. This change to the Physical                :
Securi'.y Plan does not decrease the safeguards effectiveness of the plan.                                              ,
W
!                PSP-100                          This revision to the Physical Security Plan clarified                  {
Amendment 41                    existing commitments and reflected organizational i:                                                changes and changes implemented in support of the PAP                  '
;.                                                demolition. This change to the Physical Security Plan does not decrease the safeguards effectiveness of the
:                                                  plan.
!                PTP-125.013                      This procedure was newly developed to test the feasibility Rev.O                            of reducing the Turbine Building Closed Cycle Cooling                    l j                                                  operating pressure to the Main Turbine Lube Oil Cooler,                  l t      ,
the Main Generator H2 Cooler, and the Generator Breaker                  )
i                                                  Cooling Skid. This test does not involve any unreviewed safety questions.
f PTP-125.C'4                      This procedure was newly developed to test the 2A and
  .              Rev.0                            2B Feedwater Heater vent orifices to determine if i                                                  additional venting would increase thermal performance.
This test does not involve any unreviewed safety                        l questions.                                                              l PTP-225.002                      This procedure was newly developed to provide                            ,
l Rev.O                            instructions to test the Diesel Generator Air Start After-Coolers with cooling water isolated. This test does not involve any unreviewed safety questions.
SOP-114                          Revised the Reactor Building Ventilation System Rev.15C                          Operating Procedure to add actions for the loss of all Reactor Cavity Cooling Fans. This change does not involve any unreviewed safety questions.
I c.
li.    .m-            f.-. mC .- _ ._
 
_.-    Enclosura to Docum:nt Control Desk Lettgr
  .'      RR 8450 -
RC-98 0229 -
Page 18 of 19 i
_'i dentification No.     
 
== Description:==
 
;        SOP-123                    Revised the Spent Fuel Cooling System Operating F
        ' Rev. 9H.                  Procedure to change the required position of the fuel transfer tube valve to meet the requirements of GL 96-06.
                                  . This change does not involve any unreviewed safety questions.
        - SOP-409                    Provided operating procedures for the Loose Parts Rev. 4                    Monitoring System. This change does not involve any                                '
          'ARP-001-XCP-615            unreviewed safety questions.
Rev.5A 4
4 i
4 i
i v
t i
: 2.                                    - _ _ _ _        - . _ _ _ _ .            - . _ _ - _ _ _ _ _ . _ _ .  -  .
 
          / Enclosura tb Docum:nt Control D=k Lett:r RR 8450                                                        l RC-98-0229 Page 19 cf 19 ABBREVIATIONS and ACRONYMS ARP          Annunciator Response Procedure ASME'        American Society of Mechanical Engineers CCW          Component Cooling Water                          i
:          ECR          Engineering Change Request EFW          Emergency Feedwater ES          Engineering Services Procedure ETBT        Equal To or Better Than Evaluation FEP          Fire Emergency Procedure 4
FPER        Fire Protection Evaluation Report FSAR        Final Safety Analysis Report GL          Generic Letter HPP          Health Physics Procedure HVAC        Heating, Ventilation, and Air Conditioning      '
MCN          Modification Change Notice MRF          Modification Request Form MWt          Megawatts (thermal)
NCN          Non-Conformance Notice ODCM        Offsite Dose Calculation Manual 0LER        Operating Ucense Environmental Report i            OSRE        Operational Safeguards Response Evaluation PAP          Primary Access Portal PO          Purchase Order PSP          Physican Security Plan PTP          Performance Test Procedure RB          Reactor Building REP          Radiation Emergency Plan RHR          Residual Heat Removal RN          Revision Notice S/G          Steam Generator SI          Safety injection SOP          System Operating Procedure Y            STP          Surveillance Test Procedure SW          Service Water VCT          Volume Control Tank VCSNS        Virgil C. Summer Nuclear Station l
l 1
  &}}

Latest revision as of 11:45, 8 December 2021

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML20198P299&oldid=3338142"