ML20099A618: Difference between revisions

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j lW&}e lj w~br /j, h                                     STAI E OF RilODE !SIAND AND PROVIDENCE PIANTNIIONS l
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STAI E OF RilODE !SIAND AND PROVIDENCE PIANTNIIONS j
!                                                                        Rhocle Islaral Atomic Energy Commisslon NUCLEAR SCIENCE CENTER Son.h Feny Road
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                                                                            ,arragansen, R.I. 02882-1197 July 23, 1992 U. S. Nuclear Regulatory Commission Attn:     Document Control Desk Washington, DC 20555 Gentlemen:
W Rhocle Islaral Atomic Energy Commisslon NUCLEAR SCIENCE CENTER Son.h Feny Road
Enclosure (1), Revision (1) to the Safety Analysis Report for the Low Enriched Fuel Coni.orsion of the Rhode Island Nuclear Science Center Research Reactor dated July 23,           1992, is forwarded per conversation between Mr. Marvin Mendonca (URC) and Mr. Terry Tehan           (RlAEC). This revision updates the analysis of the loss of coolant accident to reflect beamport operational and design considerations.
,arragansen, R.I. 02882-1197 July 23, 1992 U.
Very truly yours,           f t-
S.
                                                                              /p         &/
Nuclear Regulatory Commission Attn:
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Document Control Desk Washington, DC 20555 Gentlemen:
                                                                                                        /
Enclosure (1), Revision (1) to the Safety Analysis Report for the Low Enriched Fuel Coni.orsion of the Rhode Island Nuclear Science Center Research Reactor dated July 23,
Terry .'ehan Dire .or, RIEAC                                                     -
: 1992, is forwarded per conversation between Mr. Marvin Mendonca (URC) and Mr.
3 TT:cd Enclosure (1) i
Terry Tehan (RlAEC).
                                                                                                                                ) o SM1W$h 29006G                                                                                     Of 0 i f 9207290313 920723                                                                                   i PDR                                       ADOCK 05000193 P                                                         PDR
This revision updates the analysis of the loss of coolant accident to reflect beamport operational and design considerations.
    - _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ .}}
Very truly yours, f
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t-/p AeJ%
Terry.'ehan Dire
.or, RIEAC 3
TT:cd Enclosure (1) i
) o SM1W$h 29006G Of 0 i
f 9207290313 920723 i
PDR ADOCK 05000193 P
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- _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _.}}

Latest revision as of 06:48, 13 December 2024

Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations
ML20099A618
Person / Time
Site: Rhode Island Atomic Energy Commission
Issue date: 07/23/1992
From: Tehan T
RHODE ISLAND, STATE OF
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20099A620 List:
References
NUDOCS 9207290313
Download: ML20099A618 (1)


Text

_ _ _ _ _ _ - - - -

lW&}e lj h

STAI E OF RilODE !SIAND AND PROVIDENCE PIANTNIIONS j

l w~br /j, l

W Rhocle Islaral Atomic Energy Commisslon NUCLEAR SCIENCE CENTER Son.h Feny Road

,arragansen, R.I. 02882-1197 July 23, 1992 U.

S.

Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 Gentlemen:

Enclosure (1), Revision (1) to the Safety Analysis Report for the Low Enriched Fuel Coni.orsion of the Rhode Island Nuclear Science Center Research Reactor dated July 23,

1992, is forwarded per conversation between Mr. Marvin Mendonca (URC) and Mr.

Terry Tehan (RlAEC).

This revision updates the analysis of the loss of coolant accident to reflect beamport operational and design considerations.

Very truly yours, f

&/

/

t-/p AeJ%

Terry.'ehan Dire

.or, RIEAC 3

TT:cd Enclosure (1) i

) o SM1W$h 29006G Of 0 i

f 9207290313 920723 i

PDR ADOCK 05000193 P

PDR

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