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        . -                                    .
                                                            ,
                            -
NRC        .bTRIBUTION FOR PART 50 DOCl; .                  f.' ATERI AL
NRC        .bTRIBUTION FOR PART 50 DOCl; .                  f.' ATERI AL
,                                                                    * (1 EMPORARY FOf tM)
,                                                                    * (1 EMPORARY FOf tM)
                                                                                                              -
CONTROL NO: _1b" s
CONTROL NO: _1b"
                                                                                                '
s
                               .                                                                                      FILE:
                               .                                                                                      FILE:
      -
-
FROM: Florida Power Corp                              DATE OF DOC          DATE REC'D            LTH    TWX      RPT      OTHER St. Petersburg, Fla. 33733 3.T. Rodeers                                          12'-19-75        12-22-75              'IX
FROM: Florida Power Corp                              DATE OF DOC          DATE REC'D            LTH    TWX      RPT      OTHER St. Petersburg, Fla. 33733 3.T. Rodeers                                          12'-19-75        12-22-75              'IX
     - TO:                                .                              ORIG        CC OTHEH                  SENT1mc PDR            H Mr . A . Schwencer                              1 signed                                      SENT LOCAL PDR            XX
     - TO:                                .                              ORIG        CC OTHEH                  SENT1mc PDR            H Mr . A . Schwencer                              1 signed                                      SENT LOCAL PDR            XX CLASS UNCLASS                  PROPINFO                    INPUT        NO CYS REC'D              DOCKET N05 XXX                                                                'l                          50-302                      .
_
CLASS UNCLASS                  PROPINFO                    INPUT        NO CYS REC'D              DOCKET N05
                      -
XXX                                                                'l                          50-302                      .
DESCRil' TION: Ltr trans the fol:.owing:                                  ENCLOSURES: Info on Reactor Vessel Support i                                                          Evaluagion for LOCA          L0ading...
DESCRil' TION: Ltr trans the fol:.owing:                                  ENCLOSURES: Info on Reactor Vessel Support i                                                          Evaluagion for LOCA          L0ading...
                                         .                                                    (1 cy enc 1'ree'd)
                                         .                                                    (1 cy enc 1'ree'd) i I
              -
in MIT10,y0 PLANT NAME: Crystal River Unit 3.                                                                              -
i I
in MIT10,y0
              .
PLANT NAME: Crystal River Unit 3.                                                                              -
FOR ACTION /IEFLRTAATION                          DHL      12-30-75 BUTI.ER (L)                    EICilWENCER (L) ZlEMANN (L)                              REG AN (E)          REID(L)
FOR ACTION /IEFLRTAATION                          DHL      12-30-75 BUTI.ER (L)                    EICilWENCER (L) ZlEMANN (L)                              REG AN (E)          REID(L)
W/ Copies                      W/        pies              W/ Copies                W/ Copies          U/ COPIES CLARK (L)
W/ Copies                      W/        pies              W/ Copies                W/ Copies          U/ COPIES CLARK (L)
Line 62: Line 44:
YOUNGBLOOD          H. SMITH (L)                      HARTilELD (2)
YOUNGBLOOD          H. SMITH (L)                      HARTilELD (2)
DENISE                        J. COLT, Ins                  REGAN                S. TEETS (L)                    KLECKER LEG OPR                        LAIN AS                      PROJECT LDR          G. W!! LI AMS (E)                EISENHUT NILE & REGION (2)                    BENAROYA                                          V. WILSON (L)                    WIGGlIJTON HIFC                          VOLLMER
DENISE                        J. COLT, Ins                  REGAN                S. TEETS (L)                    KLECKER LEG OPR                        LAIN AS                      PROJECT LDR          G. W!! LI AMS (E)                EISENHUT NILE & REGION (2)                    BENAROYA                                          V. WILSON (L)                    WIGGlIJTON HIFC                          VOLLMER
                                                                                -
                                                                       ~!i GM.Eb5I          R. IN G R ' ti (L)          pE' Fer4used
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M.,_DUFCAN m                K. PARRISli (L)
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__
__ EXTLeiNAL DISTRIBUTION _                                                _ _ _ _ _
__ EXTLeiNAL DISTRIBUTION _                                                _ _ _ _ _
         #1 - 1.OCAL PDR Crystal River, Fla.
         #1 - 1.OCAL PDR Crystal River, Fla.
Line 74: Line 53:
         /g-/ Newton AC R S '.Andmon
         /g-/ Newton AC R S '.Andmon
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           ' " " ' " " ~
                                             \b                                          December 19, 1975
                                             \b                                          December 19, 1975
                                                                                                              '
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.s                                                                                                          i Mr. A. Schwencer, Chief                                                              %
                                                                                                            ;-  ,
Mr. A. Schwencer, Chief                                                              %
         ~,
         ~,
Director of Nuclear Reactor Regulation                                                V\v' Branch No. 2-3 U.S. Nuclear Regulatory Commission                                                        N.                    .
Director of Nuclear Reactor Regulation                                                V\v' Branch No. 2-3 U.S. Nuclear Regulatory Commission                                                        N.                    .
                       .h' ashing ton , D. C. 20555                                                                \ lc,      , , .
                       .h' ashing ton , D. C. 20555                                                                \ lc,      , , .
                                                                                                                                  - '
In Re:          Florida Power Corporation Crystal River Unit #3 Docket No. 50-302
In Re:          Florida Power Corporation
                                                                                                  -
Crystal River Unit #3 Docket No. 50-302


==Dear Mr. Schwencer:==
==Dear Mr. Schwencer:==
Line 114: Line 78:
                       #3 to determine whether the three transient loads described in the enclosure of your letter were taken into account appropriately in the design.
                       #3 to determine whether the three transient loads described in the enclosure of your letter were taken into account appropriately in the design.
In response to your request, FPC and B5W have reviewed the design basis for the Reactor Ve..sel Support System for the Crystal River Unit #3 Plant. Attachment 1 shows the model used to calculate the Reactor Vessel Support System loads resulting from a loss-of-coolant accident.
In response to your request, FPC and B5W have reviewed the design basis for the Reactor Ve..sel Support System for the Crystal River Unit #3 Plant. Attachment 1 shows the model used to calculate the Reactor Vessel Support System loads resulting from a loss-of-coolant accident.
These loads were then combined with normal operating loads
These loads were then combined with normal operating loads and seismic loads to determine the resulting total stresses on the Reactor Vessel Support System.
            .
As noted in Attachment 1, the blowdown jet forces at the location of the break were considered in the design of the Reactor Vessel Support System.                          The remaining two effects; (1) transient differential pressures in the annular region between the vessel and the shield wall; and, (2) transient differential pressures across the core barrel within the reactor vessel, were not considered.
and seismic loads to determine the resulting total stresses on the Reactor Vessel Support System.
As noted in Attachment 1, the blowdown jet forces at the location of the break were considered in the design of the Reactor Vessel Support System.                          The remaining two effects; (1) transient differential pressures in the annular region between the vessel and the shield wall; and, (2) transient differential pressures across the core barrel within the
                ,
reactor vessel, were not considered.
14135 General Office 3201 Tnitty-fourtn streu sourn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151
14135 General Office 3201 Tnitty-fourtn streu sourn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151


  --
'
      .    .
    .
Mr. A. Schwencer            -
Mr. A. Schwencer            -
2-              December 19, 1975 Although all of the transient effects were not utilized, the method of analysis described in Attachment I was considered to be the " State-of-the-Art" at the time this analysis was performed. In addition, no additional analyses of the Reactor Vessel Support System for Crystal
2-              December 19, 1975 Although all of the transient effects were not utilized, the method of analysis described in Attachment I was considered to be the " State-of-the-Art" at the time this analysis was performed. In addition, no additional analyses of the Reactor Vessel Support System for Crystal
                 . River Unit #3 was required by the Commission as evidenced by their Safety Evaluation Report for Crystal River Unit #3,
                 . River Unit #3 was required by the Commission as evidenced by their Safety Evaluation Report for Crystal River Unit #3, dated July 5, 1974.
          -
Should additional disqussion concerning the design basis of the Reactor Vessel Support System for Crystal River Unit #3 be required, please feel free to contact this office.
dated July 5, 1974.
Should additional disqussion concerning the design basis of
        -
the Reactor Vessel Support System for Crystal River Unit #3 be required, please feel free to contact this office.
                                -
Very truly yours, e
Very truly yours, e
                                                           /
                                                           /
J.  . Ro gers Asst. Vice President JTR/iw Attachment
J.  . Ro gers Asst. Vice President JTR/iw Attachment l
          .
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                                                                                  $
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                                                         ~~.
                                                         ~~.
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Latest revision as of 15:54, 18 February 2020

Forwards Reactor Vessel Support Evaluation for LOCA Loadings in Response to NRC 751114 Request for Review of Design Basis
ML19329D702
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/19/1975
From: Rodgers J
FLORIDA POWER CORP.
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML19329D703 List:
References
NUDOCS 8003160320
Download: ML19329D702 (3)
v • d • e


Text

NRC .bTRIBUTION FOR PART 50 DOCl; . f.' ATERI AL

, * (1 EMPORARY FOf tM)

CONTROL NO: _1b" s

. FILE:

FROM: Florida Power Corp DATE OF DOC DATE REC'D LTH TWX RPT OTHER St. Petersburg, Fla. 33733 3.T. Rodeers 12'-19-75 12-22-75 'IX

- TO: . ORIG CC OTHEH SENT1mc PDR H Mr . A . Schwencer 1 signed SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET N05 XXX 'l 50-302 .

DESCRil' TION: Ltr trans the fol:.owing: ENCLOSURES: Info on Reactor Vessel Support i Evaluagion for LOCA L0ading...

. (1 cy enc 1'ree'd) i I

in MIT10,y0 PLANT NAME: Crystal River Unit 3. -

FOR ACTION /IEFLRTAATION DHL 12-30-75 BUTI.ER (L) EICilWENCER (L) ZlEMANN (L) REG AN (E) REID(L)

W/ Copies W/ pies W/ Copies W/ Copies U/ COPIES CLARK (L)

  • STO ..? (L) D!CKER (E) LE AR (L)

W/ Copics W/ Copies W/ Copics W/ Cepics !OOSN4K' PARR (L) VASSALLO (L) K.%GliTON (E)

W/ Copics W/ Copics W/ Copies -

spInc W/ Copics t/ g g g --

KNIEL (L) PURPLE (L) YOUNGBLOOD (E) dri w #OARANoWSKV W/ Copies W/ Copies W/ Copies W/ t.opies ~

~ "

IN1 ERNAL DISTRIPUTIOiJ efb F N G TECH REVIEW DENTON LIC ASST A/T IND .

FNHC NH SCHROEDER GRIMES R. DIGGS (L) BRAITMAN OGC, ROOM P 50GA MACCARY GAMMILL SA'LTZMAN d; NIGHT H. GEARIN (L)

GOSS!CK/ STAFF KASTNE R st GOULbOURNE (L) MEL1%

CASE PAWLICKl BALLARD P. KREUTZER (E)

.' 48HAO SPANGLER J. LL:E (L) PLANS 44IOYD STELLO M. nU3'inno0gL) MCDONALD

/AGOilE (L) HOUSTON .E NVI R O_ ' S. REED (E) CHAPi.1AN DEYOUNG (L) NOVAK MULLER - M. SERVICE (L) DUBE (Ltr)

SKOVHOLT (L) ROSS DICKER S. SHEPPARD (L) E. COUPF GOLLER (L) (Ltr) IPPOL ITO KNIGHTON t/.. SLATER (E) PETERSON P. COLLINS TEDESCO .

YOUNGBLOOD H. SMITH (L) HARTilELD (2)

DENISE J. COLT, Ins REGAN S. TEETS (L) KLECKER LEG OPR LAIN AS PROJECT LDR G. W!! LI AMS (E) EISENHUT NILE & REGION (2) BENAROYA V. WILSON (L) WIGGlIJTON HIFC VOLLMER

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__ EXTLeiNAL DISTRIBUTION _ _ _ _ _ _

  1. 1 - 1.OCAL PDR Crystal River, Fla.

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\b December 19, 1975

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N

.s i Mr. A. Schwencer, Chief  %

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Director of Nuclear Reactor Regulation V\v' Branch No. 2-3 U.S. Nuclear Regulatory Commission N. .

.h' ashing ton , D. C. 20555 \ lc, , , .

In Re: Florida Power Corporation Crystal River Unit #3 Docket No. 50-302

Dear Mr. Schwencer:

In your November 14, 1975, letter you requested Florida Power Corporation (FPC) to review the design bases for the Reactor Vessel Support System for Crystal- River Unit

  1. 3 to determine whether the three transient loads described in the enclosure of your letter were taken into account appropriately in the design.

In response to your request, FPC and B5W have reviewed the design basis for the Reactor Ve..sel Support System for the Crystal River Unit #3 Plant. Attachment 1 shows the model used to calculate the Reactor Vessel Support System loads resulting from a loss-of-coolant accident.

These loads were then combined with normal operating loads and seismic loads to determine the resulting total stresses on the Reactor Vessel Support System.

As noted in Attachment 1, the blowdown jet forces at the location of the break were considered in the design of the Reactor Vessel Support System. The remaining two effects; (1) transient differential pressures in the annular region between the vessel and the shield wall; and, (2) transient differential pressures across the core barrel within the reactor vessel, were not considered.

14135 General Office 3201 Tnitty-fourtn streu sourn . P O Box 14042. St Petersburg. Florida 33733 e 813-866-5151

Mr. A. Schwencer -

2- December 19, 1975 Although all of the transient effects were not utilized, the method of analysis described in Attachment I was considered to be the " State-of-the-Art" at the time this analysis was performed. In addition, no additional analyses of the Reactor Vessel Support System for Crystal

. River Unit #3 was required by the Commission as evidenced by their Safety Evaluation Report for Crystal River Unit #3, dated July 5, 1974.

Should additional disqussion concerning the design basis of the Reactor Vessel Support System for Crystal River Unit #3 be required, please feel free to contact this office.

Very truly yours, e

/

J. . Ro gers Asst. Vice President JTR/iw Attachment l

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