ML19347D501: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:,
{{#Wiki_filter:,
                                                                                '
F e
F e
SOUTH CAROLINA ELECTRIC & GAS COMPANY Post orrier son re4 CotuMe:A. south CAROLINA 29218 T.C.NICHOL5.JR.
SOUTH CAROLINA ELECTRIC & GAS COMPANY Post orrier son re4 CotuMe:A. south CAROLINA 29218 T.C.NICHOL5.JR.
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Mr. Harold R. Denton, Director                                                        /
Mr. Harold R. Denton, Director                                                        /
Office of Nuclear Reactor Geulation                                  bi      If,%%g 4
Office of Nuclear Reactor Geulation                                  bi      If,%%g 4
                                                                                                        ##
                                                                                                               .s U. S. Nuclear Regulatory Commission                                      Q              /
                                                                                                               .s U. S. Nuclear Regulatory Commission                                      Q              /
Washington, D. C. 20555                                                  4Q        \
Washington, D. C. 20555                                                  4Q        \
:


==Subject:==
==Subject:==
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H. N. Cyrus J. B. Knotts, Jr.
H. N. Cyrus J. B. Knotts, Jr.
J. L. Skolds B. A. Bursey O. S. Bradham ISEG NPCF/Whitaker File PRS 8108260,275                                    j
J. L. Skolds B. A. Bursey O. S. Bradham ISEG NPCF/Whitaker File PRS 8108260,275                                    j
          ..                                                                                              .


                .
                                                                                                    '
       ~
       ~
Dilution flow is assumed to be a naximirm of 150 gpm, which is the capability of one primary water ir.akeup pump to deliver unborated p,
Dilution flow is assumed to be a naximirm of 150 gpm, which is the capability of one primary water ir.akeup pump to deliver unborated p,
(' )                  water to the PCS, A mininum RCS water volume of 5000 ft3 is used. This is a conser-vative estimate of the active RCS volume with one reactor coolant        23 s                            ,
(' )                  water to the PCS, A mininum RCS water volume of 5000 ft3 is used. This is a conser-vative estimate of the active RCS volume with one reactor coolant        23 s                            ,
pump operating.
pump operating.
        .-
             )
             )
: 4. Dilution During Startup T                Prior to startup, the RCS is filled with borated water at a bcron
: 4. Dilution During Startup T                Prior to startup, the RCS is filled with borated water at a bcron
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'                        tor coolant is acce.nplished by operation of the reictor coolant pumps. High source range flux level ara all reactor trip alarms are effective.
'                        tor coolant is acce.nplished by operation of the reictor coolant pumps. High source range flux level ara all reactor trip alarms are effective.
(,
(,
    ,
In the analysis, a conservatively high dilution flow capacity for the centrifugal charging pumps is considered (approximately 300 spm). A minimum volume of 7360 ft3 in the reactor coolant system        23 is used. This corresponds to the active volume of the RCS excluding
In the analysis, a conservatively high dilution flow capacity for
                                                                                                      '
the centrifugal charging pumps is considered (approximately 300 spm). A minimum volume of 7360 ft3 in the reactor coolant system        23 is used. This corresponds to the active volume of the RCS excluding
                   .      the pressurizer.
                   .      the pressurizer.
,
: 5. . Dilution During Full Power Operation                                    23 k'i th the unit at power _ and the RCS at pressure, the dilution rate is
                                          .
: 5. . Dilution During Full Power Operation                                    23
_,_
k'i th the unit at power _ and the RCS at pressure, the dilution rate is
(                      limited by the capacity of the charging valve (analysis is performed assuming two charging pumps are in operation although only              23
(                      limited by the capacity of the charging valve (analysis is performed assuming two charging pumps are in operation although only              23
                                                    '
(?
(?
s_.
s_.
          *.
   -{f 15.2-22b                  AMENDM?.NT 23 J ant'ARY, 1981}}
:.-
   -{f
    ,
              ,
.
15.2-22b                  AMENDM?.NT 23 J ant'ARY, 1981}}

Latest revision as of 02:23, 31 January 2020

Advises That Encl Page 15.2-22b in FSAR Amend 24 Was Mistakenly Renamed & New Page 15.2-22b Was Added.Renamed Page Will Be Added to FSAR in Next Amend to Bridge Info Currently on Pages 15.2-22b & 15.2-23
ML19347D501
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/20/1981
From: Nichols T
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8103260275
Download: ML19347D501 (2)


Text

{{#Wiki_filter:, F e SOUTH CAROLINA ELECTRIC & GAS COMPANY Post orrier son re4 CotuMe:A. south CAROLINA 29218 T.C.NICHOL5.JR. we p .. . . c c.ccor~c March 20, 1981 me ouer ... ...... o.c in#,. g s, 4 (.

                                                                                            .e c.% a #

Mr. Harold R. Denton, Director / Office of Nuclear Reactor Geulation bi If,%%g 4

                                                                                                              .s U. S. Nuclear Regulatory Commission                                      Q              /

Washington, D. C. 20555 4Q \

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 Boron Dilution Event - FSAR

Dear Mr. Denton:

In FSAR Amendment 24. the attached page 15.2-22b was mistakenly renamed and a new page 15.2-22b was added. The page which was renamed will be added back into the FSAR in the next amendment to bridge the information currently found on pages 15.2-22b and 15.2-23. If you have any questions, please let us know. Very truly yours, T. C. Nichols, Jr. RC:TCN:pj Attachment I CC: V. C. Summer w/o att. l G. H. Fischer w/o att. ! T. C. Nichols, Jr. w/o att. C. A. Price D. A. Nauman ! W. A; Williams, Jr. i R. B. Clary A. R. Koon A. A. Smith. H. N. Cyrus J. B. Knotts, Jr. J. L. Skolds B. A. Bursey O. S. Bradham ISEG NPCF/Whitaker File PRS 8108260,275 j

      ~

Dilution flow is assumed to be a naximirm of 150 gpm, which is the capability of one primary water ir.akeup pump to deliver unborated p, (' ) water to the PCS, A mininum RCS water volume of 5000 ft3 is used. This is a conser-vative estimate of the active RCS volume with one reactor coolant 23 s , pump operating.

           )
4. Dilution During Startup T Prior to startup, the RCS is filled with borated water at a bcron
      . ,/                           -

concentration of 1555 ppa. This is a conservative estimate with the reactor at a 1.77% Ak/k shutdown margin at 5570F, Core monitoring is by external BF3 detectors. Mixing of the reac- ' tor coolant is acce.nplished by operation of the reictor coolant pumps. High source range flux level ara all reactor trip alarms are effective. (, In the analysis, a conservatively high dilution flow capacity for the centrifugal charging pumps is considered (approximately 300 spm). A minimum volume of 7360 ft3 in the reactor coolant system 23 is used. This corresponds to the active volume of the RCS excluding

                 .       the pressurizer.
5. . Dilution During Full Power Operation 23 k'i th the unit at power _ and the RCS at pressure, the dilution rate is

( limited by the capacity of the charging valve (analysis is performed assuming two charging pumps are in operation although only 23 (? s_.

  -{f 15.2-22b                   AMENDM?.NT 23 J ant'ARY, 1981}}