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{{#Wiki_filter:-ilic cnu 105 U s. NUCLE An ntGULA TONY CC*
{{#Wiki_filter:-
G3 EON oOCKE T NUMDtn (2 M'50-289_,-' ' " " " " ' ' " NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO: FROM: oATc c7 coCUMENT Metropolitan Edison Company 8/20/76 Mr. Robert 'i. Reid Reading, Pa.
oOCKE T NUMDtn ilic cnu 105                                               U s. NUCLE An ntGULA TONY CC*   G3 EON (2 M'         ,-                                                                                50-289                _
oATt ntCrivEo R. C. Arnold 9/23/76)(.ETTEn ONoronizEo encP INPUT FORM NUMOEn cF COPIES RECEIVED Konio'NAL)(UNCLAssir Eo One signed CCoPv oESCRIPTicN ENCLOSURE Ltr. re our 6/9/76 ltr. and their 7/9/76 ltr.....concerning Reactor Vessel Supports Analysis.(2-P)PLANT NAME:
                                                                                                    ''""""''"
Three Mile Island 41 DISTRILUTION FOR REACTOR VESSEL SUPPORT INFO FOR OPERATING REACTORS PER MR. TRAMMELL 7-12-74 SAFETY FOR ACTION /INFORMATION 8/25/76 RJL'_'IGNED AD;Collor_ d$ m ta ent r.Reid IM PROJE_CT RiNACER; Bridges IC. ASST: Ingram i INTERNAL DISTRIBUTION k REG FILD SP.C l'DR KNIGilT_ ROSZTOCZY giCHECK~.X C. TRAMMELL Sl!A O P. BARANOWSKY
NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO:                                           FROM:                                         oATc c7 coCUMENT Metropolitan Edison Company                       8/20/76 Mr. Robert 'i. Reid                     Reading, Pa.                                 oATt ntCrivEo R. C. Arnold                                     9/23/76
~P. NORIAN I R. BOSNAK i V. NOONAN'_I_ll _EXTE'~L DISTRIBUTION CONTRCL NUMBER
    )(.ETTEn                 ONoronizEo             encP                     INPUT FORM           NUMOEn cF COPIES RECEIVED Konio'NAL           )(UNCLAssir Eo                                                         One signed CCoPv oESCRIPTicN                                                     ENCLOSURE Ltr. re our 6/9/76 ltr. and their 7/9/76 ltr.....concerning Reactor Vessel Supports Analysis.
% LPDR: Harrisburg, Pa.
(2-P)
~]v807 1469 278 , , NeQFoAM 193(2 76) 7910290 6 40
PLANT NAME:
[-  
Three Mile Island 41 DISTRILUTION FOR REACTOR VESSEL SUPPORT INFO FOR OPERATING REACTORS PER MR. TRAMMELL 7-12-74 SAFETY                             FOR ACTION /INFORMATION           8/25/76             RJL
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  '_'           IGNED AD;                 Collor
'METROPOLITAN EDISON COMPANY
_ d$ m ta ent r.                     Reid IM PROJE_CT RiNACER;                   Bridges IC. ASST:                   Ingram i
--- ----- . ..-..__.- ..--
INTERNAL DISTRIBUTION k REG FILD SP.C l'DR KNIGilT
.. - . . - . - - - - . . . - - - . _ .
_ ROSZTOCZY                                                                                                             ~
PC''T OFFICE BOX 542 READING, PENNsYLVANI A 19603 TELEPHONE 0601 N\ -6, 9s\t , ,'August 20 ,1976 6 D'-GqL 1189<//jh IN \-E,-', ' 'N a-g-.y h,J s.f f-**VlDirectcr cf :Iuclear Reacter Regulation Atta: Mr. Rccert W. Reid, Chief Cperating Reacters 3 ranch #h x U.S. :iuclear Regulatory Cc==ission w Washington, D.C.
giCHECK
20555 Lear Sir: Three Mile Island Nuclear Statica Unit 1 (T:C-1)
  .X C. TRAMMELL Sl!A O P. BARANOWSKY
      ~
P. NORIAN I       R. BOSNAK i       V. NOONAN
  '
_I
_
l l_                                  EXTE'~
                                              ~
L DISTRIBUTION                                         CONTRCL NUMBER
    % LPDR: Harrisburg, Pa.                                                                                 ]
v807
                                  ,    ,
1469 278 NeQFoAM 193(2 76)
-
7910290 6 40                 [
 
          .
                                                                            -
_      .
                                                                          $WY
                                                              .,' ;:,, mee na noanss METROPOLITAN EDISON COMPANY
              --
                                  - ----- . ..-..__.- ..--                         .   . - . . - . - - - - . . . - - - . _ .
PC''T OFFICE BOX 542   READING, PENNsYLVANI A 19603                                                     TELEPHONE                           0601 N\9s\t 6,    ,
                                                                                                                                -                ,'
August 20 ,1976                     6                                   '-
GqL 1189                           </
jh IN \
                                                                                                                              /      D '
                                                                                                                                                -   E,-
                                                                                                      ,''               .y      N a                 -
s            -g h,J
                                                                                                                                                .
f f-     *
* V                        l Directcr cf :Iuclear Reacter Regulation Atta: Mr. Rccert W. Reid, Chief Cperating Reacters 3 ranch #h                                                                             x U.S. :iuclear Regulatory Cc==ission                                                                               w Washington, D.C.         20555 Lear Sir:
Three Mile Island Nuclear Statica Unit 1 (T:C-1)
Decket :Io. 50-269 Cperating License :Io. DPR-50 Reacter Vessel Suppcrts Analysis Ycur letter of June 9,1976 requested additional infor=ation evaluating the adequacy of the reactor pressure vessel supports under leads not previcusly considered. As indicated in our July 9th resp nse, ve ha.e
Decket :Io. 50-269 Cperating License :Io. DPR-50 Reacter Vessel Suppcrts Analysis Ycur letter of June 9,1976 requested additional infor=ation evaluating the adequacy of the reactor pressure vessel supports under leads not previcusly considered. As indicated in our July 9th resp nse, ve ha.e
=et with other Sabcock & Wilcox :ISSS users in an effort to evaluate the ccncern and discuss pcssible resolutions.
            =et with other Sabcock & Wilcox :ISSS users in an effort to evaluate the ccncern and discuss pcssible resolutions.
Two paths are being pursued in parallel to 'letermine our required acticn.
Two paths are being pursued in parallel to 'letermine our required acticn.
The first approach is to undertake a review of verk spenscred by a group of utilities evaluating the absolute and relative pr bability of a postu-lated pipe break between the reacter vessel neccle and the reacter cavity vall.
The first approach is to undertake a review of verk spenscred by a group of utilities evaluating the absolute and relative pr bability of a postu-lated pipe break between the reacter vessel neccle and the reacter cavity vall. Science Applicatiens, Inc. (SAI) is submitting their results ir, the form of a tcpical report in late August , 1976. '"he :IRC staff was intr duced to the study in a presentation involving SAI en July 13, 1976.
Science Applicatiens, Inc. (SAI) is submitting their results ir, the form of a tcpical report in late August , 1976.
'"he :IRC staff was intr duced to the study in a presentation involving SAI en July 13, 1976.
The seccnd apprcach is a review of the additional informatien requested in your June 9th letter which requires a ecstly, multi-year analysis fer each plant. Discussions with 3abecek & Wilecx and cther consulting firms, review cf ACES hearings transcripts, and your letter itself indicates uncertainties in the present state of the art analysis to evaluate this particular case.
The seccnd apprcach is a review of the additional informatien requested in your June 9th letter which requires a ecstly, multi-year analysis fer each plant. Discussions with 3abecek & Wilecx and cther consulting firms, review cf ACES hearings transcripts, and your letter itself indicates uncertainties in the present state of the art analysis to evaluate this particular case.
1469 279 g.kg*g-$r  
g                                        1469 279
*a< .'Mr. Rctert
          .
'4.Reid, Ch.ef August 20, 197c
kg*g
,:e nn, , Ugb**wf As a result of our preliminary review, it is our belief that the SA:
                                                                                                                                    -
                                                                                                                                            $
r
 
a< .   *
'
Mr. Rctert '4. Reid, Ch.ef                         August 20, 197c nn, , ,:e Ugb **wf As a result of our preliminary review, it is our belief that the SA:
study substantiates the extremely icw probability of a pipe rupture in the reactor vessel cavity area at IMI-1; therefore, the pcstulated treak represents no significant hazard to the health and safety of the public. In this light, no further analysis is censidered required.
study substantiates the extremely icw probability of a pipe rupture in the reactor vessel cavity area at IMI-1; therefore, the pcstulated treak represents no significant hazard to the health and safety of the public. In this light, no further analysis is censidered required.
Following your review of the SAI study, we would like to meet with you to discuss this issue and address any further cencerns yor =ight have.
Following your review of the SAI study, we would like to meet with you to discuss this issue and address any further cencerns yor =ight have.
Sincerely,/' I i/,.R.C.Abncld Vice President ECA:1CL:=ft
Sincerely,
} k ()h. )}}
                                                  ,
                                                    /' I/  i
                                                  .
R.C.Abncld Vice President ECA:1CL:=ft
                                      } k ()h   .)}}

Revision as of 13:17, 19 October 2019

Responds Further to NRC 760609 Request for Addl Info Re Reactor Pressure Vessel Load Support Adequacy.Science Applications Inc Topical Rept,Due Aug 1976,justifies No Further Analysis
ML19210A420
Person / Time
Site: Crane 
Issue date: 08/20/1976
From: Arnold R
METROPOLITAN EDISON CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
GQL-1189, NUDOCS 7910290640
Download: ML19210A420 (2)
v • d • e


Text

-

oOCKE T NUMDtn ilic cnu 105 U s. NUCLE An ntGULA TONY CC* G3 EON (2 M' ,- 50-289 _

"""""

NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO: FROM: oATc c7 coCUMENT Metropolitan Edison Company 8/20/76 Mr. Robert 'i. Reid Reading, Pa. oATt ntCrivEo R. C. Arnold 9/23/76

)(.ETTEn ONoronizEo encP INPUT FORM NUMOEn cF COPIES RECEIVED Konio'NAL )(UNCLAssir Eo One signed CCoPv oESCRIPTicN ENCLOSURE Ltr. re our 6/9/76 ltr. and their 7/9/76 ltr.....concerning Reactor Vessel Supports Analysis.

(2-P)

PLANT NAME:

Three Mile Island 41 DISTRILUTION FOR REACTOR VESSEL SUPPORT INFO FOR OPERATING REACTORS PER MR. TRAMMELL 7-12-74 SAFETY FOR ACTION /INFORMATION 8/25/76 RJL

'_' IGNED AD; Collor

_ d$ m ta ent r. Reid IM PROJE_CT RiNACER; Bridges IC. ASST: Ingram i

INTERNAL DISTRIBUTION k REG FILD SP.C l'DR KNIGilT

_ ROSZTOCZY ~

giCHECK

.X C. TRAMMELL Sl!A O P. BARANOWSKY

~

P. NORIAN I R. BOSNAK i V. NOONAN

'

_I

_

l l_ EXTE'~

~

L DISTRIBUTION CONTRCL NUMBER

% LPDR: Harrisburg, Pa. ]

v807

, ,

1469 278 NeQFoAM 193(2 76)

-

7910290 6 40 [

.

-

_ .

$WY

.,' ;:,, mee na noanss METROPOLITAN EDISON COMPANY

--

- ----- . ..-..__.- ..-- . . - . . - . - - - - . . . - - - . _ .

PCT OFFICE BOX 542 READING, PENNsYLVANI A 19603 TELEPHONE 0601 N\9s\t 6, ,

- ,'

August 20 ,1976 6 '-

GqL 1189 </

jh IN \

/ D '

- E,-

, .y N a -

s -g h,J

.

f f- *

  • V l Directcr cf :Iuclear Reacter Regulation Atta: Mr. Rccert W. Reid, Chief Cperating Reacters 3 ranch #h x U.S. :iuclear Regulatory Cc==ission w Washington, D.C. 20555 Lear Sir:

Three Mile Island Nuclear Statica Unit 1 (T:C-1)

Decket :Io. 50-269 Cperating License :Io. DPR-50 Reacter Vessel Suppcrts Analysis Ycur letter of June 9,1976 requested additional infor=ation evaluating the adequacy of the reactor pressure vessel supports under leads not previcusly considered. As indicated in our July 9th resp nse, ve ha.e

=et with other Sabcock & Wilcox :ISSS users in an effort to evaluate the ccncern and discuss pcssible resolutions.

Two paths are being pursued in parallel to 'letermine our required acticn.

The first approach is to undertake a review of verk spenscred by a group of utilities evaluating the absolute and relative pr bability of a postu-lated pipe break between the reacter vessel neccle and the reacter cavity vall. Science Applicatiens, Inc. (SAI) is submitting their results ir, the form of a tcpical report in late August , 1976. '"he :IRC staff was intr duced to the study in a presentation involving SAI en July 13, 1976.

The seccnd apprcach is a review of the additional informatien requested in your June 9th letter which requires a ecstly, multi-year analysis fer each plant. Discussions with 3abecek & Wilecx and cther consulting firms, review cf ACES hearings transcripts, and your letter itself indicates uncertainties in the present state of the art analysis to evaluate this particular case.

g 1469 279

.

kg*g

-

$

r

a< . *

'

Mr. Rctert '4. Reid, Ch.ef August 20, 197c nn, , ,:e Ugb **wf As a result of our preliminary review, it is our belief that the SA:

study substantiates the extremely icw probability of a pipe rupture in the reactor vessel cavity area at IMI-1; therefore, the pcstulated treak represents no significant hazard to the health and safety of the public. In this light, no further analysis is censidered required.

Following your review of the SAI study, we would like to meet with you to discuss this issue and address any further cencerns yor =ight have.

Sincerely,

,

/' I/ i

.

R.C.Abncld Vice President ECA:1CL:=ft

} k ()h .)

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