ML20126C137

Requests Addl Info Re Rept Entitled, Analysis & SE of Spent Fuel Shipping Cask Handling at Monticello Generating Plant

ML20126C137
Person / Time
Site:	Monticello
Issue date:	03/02/1976
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Goller K Office of Nuclear Reactor Regulation
References
NUDOCS 9212220390
Download: ML20126C137 (2)

Text

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MAR 0 21976 ution:

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._ EBTRdg DochtNo.50-263 gentral File D. Eisenhut K. R. Goller, Assistant Director

• for Operating Reactors l Division of Operating Reactors i

l MONTICELLO SPENT FUEL SHIPPING CASK HANDLING

{ NORTHERN STATES POWER COMPANY Plant Name: Monticello Licensing Stage: Post OL Docket No.: 50-263 Branch and Project Manager Requesting Assistance: ORB-2, R. Snaider Operating Reactors Branches Involved: Engineering, Plant Systems Requested Completion Date: February 27, 1976 Description of Request: By memo TAR No. ORB-2-210 Review Status: Request for additional infornation l

The Engineering Branch, Division of Operating Reactors has reviewed the report entitled "An Analysis And Safety Evaluation of Spent Fuel Shipping Cask Handling At The Monticello Nuclear Generating Plant?

dated January 13, 1976 regarding the adequacy of the structural design criteria.

We find that before we can coglete our review, additional infomation as indicated in the enclosure, is necessary.

D. G. Eisenhut, Assistant Director for Operational Technology Division of Opernting Reactors l

Enclosure:

As Stated cc w/ encl:

V. Stello R. Snaider L. Shao R. Stuart i

D. Ziemann G. Bagchi A. Schwencer s

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' Form AEC-318 (Rev. 9 53) AECM 0240 W v. ,, ."ovlenmusnt psuntime o/rics sen.sso.ies 9212220390 760302 PDR ADOCK 05000263.

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NORTHERN STATES POWER COMPANY MONTICELLO SPENT FUEL SHIPPING CASK HANDLING REQUEST FOR ADDITIONAL INFORMATION ENGINEERING BRANCH

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f 1. In page 3-3 verify that.the strength properties of concrete and

[ reinforcing steel used for the analysis conservatively represent the insitu properties of the structures concerned.

l

! 2. In page 3-8 it is indicated that the force' acting on the structure '

l' is checked for punching shear and end shear on the-sla'b ard beam.

{ Indicate what limits are used to arrive at the acceptance criteria.

{ 3. In page 3-9 indicate the limiting value of ductility ratio, p to 2

arrive at the available strain energy of.the beam.

4. In tables 3-1 and 3-2 provide bases. to support the numbers shown f . for Mu and Vu '

5. In page 5-5 ground acceleration value of . 06g is indicated to be

[ the DBE. However, the safe shutdown earthquake for the plant is ,

j 0.12g horizontal . Establish stability against overturning moment l using this higher earthquake. The last sentence in section~5.2'

implies that no seismic restraintis required to protect the spent 4

fuel. Clarify whether spent fuel storage racks are seismically

, restrained as they are stored in the pool, a

6. In Figure 3-1 cask drop locations are indicated. Between drop j number one (No.1) and' drop number three (No. 3) there appears to-be a noncomposite beam W30X108 along the column line 6.9. Evaluate -

the consequences of a postulated cask drop at the center of this beam-l 4

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