ML20127P481
| ML20127P481 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/31/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9212020231 | |
| Download: ML20127P481 (3) | |
Text
_. _ _,. _ _ _ _ _.. _ _ - _ _ _ _. _ _.. _. _. _ _ _. _... _ _ _ _ _ _ _ _ _
/
Distribution:
Dockat File:
50-263 L-Rdg SEB RF l
Docket No.
50-263 i
i Karl R. Goller, Assistant Director I
for Operating Reactors Directorate of Licensing NORTHERN STATES POWER C0. - MONTICLLLO NUCLEAR PLANT
- PRELIMINARY REFORT OF FUEL CASK DROP ACCIDENT ANALYSES",- DATED OCTOBER 1,1974 STRUCTURAL EVALUATION, POSITION AND STATEMENTS (TAR-1271) l Plant Name Monticello Docket No.:
50-263 Licensing Stage Post - OL Review Branch and Project Leader Requesting Assistance: ORB-2; J. Shea Requested Completion Date: January 6.1975 Technical Branches Involved: Auxiliary and Power Conversion Systems Branch Structural Engineering Branch
. Accident Analysis Branch Description of Request: Memo dated November 22,1974(ORB-2-TAR-1271)
Review Status: Waiting for Information In accordance with your re Directorate of Licensing, quest the Structural Engineering Branch, has reviewed and evaluated structural sections of the applicant's report cited above.
I We find that additional information 'is required before we can complete 1
our review.- The additional information requested, which concerns structural aspects, is contained-in the enclosure.
!g R. R. Maccary, Assistant Director for Engineering-Directorate of Licensing -
~
Enclosure:
Request for Additional
... J Information for Monticello l
Document B l
cc_ Next Page r
l LS L:SEB j[.p L:
7
.,,.u.-
..AGluckmann.c a;.LSh 0. _
RMMaccary__
.m.-
..t 12/y/74
.12/31/74 12/y/74 ucm.m....m um aa
- o..s.o m.,,.
1, 9212O20231 741231 PDR-ADOCK 05000263-P PDR
_;.7.._.__.___.
i a
I I
K. R. Goller \\
cc w/o encli A. Gianbusso, L
/
f W. Mcdonald, L
/
i cc w/encle i
S. Hanauer, DRTA F. Schroeder, L R. Klecker, L S. Yarga, L D. Eisenhut, L L. Shao, L A. Gluckmann, L i
T. Carter, L J. Shes. L R. Diggs, L
+
C. Long, L
~
B. Grimes L D. Ziemann, L t
s i
i i
i l
l t
i a
i
.... q onice >
-, +
.~..
u-..,
.,~
w,......s Perse AEC.)l, (Rev. 9-33) AECM 0240 W u e, oovanament pasurine onscas sene.sas.tes
NORTHERN STATES POWER C0 MONTICELLO NUCLEAR PLANT DOCKET #50-263
-l
" PRELIMINARY REPORT OF FUEL CASK DROP ACCIDENT ANALYSES" DATED OCTOBER 1,1974 STRUCTURAL POSITION, STATEMENTS, AND REQUEST FOR ADDITIONAL INFORMATION (TAR-1271) l The information provided in this document is not sufficient to permit an evaluation of the safety margin provided in the design and const-ruction of the spent fuel pool and other critical structural elements for loads generated by a cask drop when combined with other design loads.
It is the position of the Structural Engineering Branch that:
When the loads due to a cask drop are considered together with other design loads, the safety margins for the spent fuel pool, floor' slabs, beams and protective structures for Category I myipment, should be similar to the sefety margins estabikhed in Document (B) prepared by the Structural Engineering Branch, Directorate of Licensing and entitled " Structural Design Criteria for Category I Structures Outsid'e the Containment." The Document (B) was originally written for structures outside of the containment but is also applicable to the structures inside the containment.
Therefore, provide a statement that when cask drop loads are included in the analysis ~ the design criteria end the design methods for the spent fuel pool, and other essential structural systems satisfy the require-monts of Document (B) cited above.
t
..r e.
. ~. _.
i