ML19332C279

Summary of 890925 Meeting W/Northern States Power, Tlg Engineering,Black & Veatch & Shaw Pittman in Rockville, MD Re Transport of Pathfinder Reactor Vessel.Meeting Handout Encl

ML19332C279
Person / Time
Site:	07109238
Issue date:	11/07/1989
From:	Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8911270093
Download: ML19332C279 (24)

Text

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' MEMORANDUM FOR:'

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Nancy L. Osgood

. -Transportaticn Branch, NMSS

SUBJECT:

MEETING SUMMA?.Y CONCERNING TRANSPORT OF PATHFINDER REACTOR:

VESSEL e

Attendees:

Northern States Power TLG Engineering Black &= Veatch

'Al Kuroyama Iqbal Husain Mitch Bjeldar.es

- Ron Meyer Tom LaGuardia Mohamed Moussa

Dennis Zercher Adam Levin James Stresewski

-Shaw, Pittman NRC Jay Silberg Ross.Chappell Earl Easton Henry Lee Curt Lindner DanMartin(part-time)

Nancy Osgood Carl Withee Introduction i

A meeting was held at the request of Northern States Power Company (NSP) at Rockville, Maryland, on Septeuber 25,:1989, concerning the transport of the Pathfinder reactor sessel. The Pathfinder plant is being decommissioned. The reactor. vessel will be transported intact from Sioux Falls, South Dakota, to Richland,-Washington.- The fuel has been removed from the reactor vessel, but the reactor internals wi11' remain in place.

N

= Package Configuration Steel plates,will be welded over reactor vessel openings. The head will be L, 4, bolted on the vessel using the original head studs. The vessel will be filled e

with gravel and grout to immobilize loose surface radioactivity. A steel plate

.will be installed around the vessel for radiation shielding. Aluminum honeycomb

'i material will'be installed around the package to act as an impact limiter.

=There are no lifting or tiedown fixtures which are a structural part of the package.

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The. vessel.will be analyzed for a 1-foot side drop and a drop at an~ angle with G

one end suspended one foot. These drop configurations =were chosen as the worst case credible drops during-transport.. Results'of the drop analyses are included in the meeting handout.

! Contents

An. activation analysis has been performed that demonstrates that radioactivity-concentrations meet the requirements for' low specific activity (LSA). The total radioactivity is estimated at 467 Ci in activated metal-components and 95 mci as loose surf ace contamination. The radioactivity is 'primarily Co-60. Since the total radioactivity exceeds two times the A2 valve for Co-60, it was recommended that NSP investigate the potential impact of the 10 CFR Part 71.

proposed rule change, which limits radioactivity to two times A2 for LSA Type A

. packages.

Schedule An application' for the certification of the reactor vessel as a Type _A LSA-package-is expected to be submitted to NRC on October 20. 1989.. NSP is hoping for approval by. July,1990. The actual shipping date is. expected to be in the fall,,1990.

Original Sig'ned by' Nancy L. Osgood Transportation Branch, HMSS

Enclosure:

Meeting Handout I

)istr.ibution:,w/o encloture

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MEMORANDUM FOR:

The Files-1'

'FROMi-Nancy L; Osgoof Transportation Branch, NMSS

SUBJECT:

MEETING

SUMMARY

CONCERNING TRANSPORT OF PATHFINDE'R REACTOR.

VESSEL Attendees:i Northern' States Power TLG Engineering-Black & Veatch -

4 Al-'Kuroyama

_Iqbal Husain Mitch Bjeldanes Tron Meyer.

Tom LaGuardia Mohamed Moussa o

Dennis.Zercher-Adam Levin James Stresewski l

Shaw, Pittman

-NRC Jay'Silberg; Ross Chappell Earl Easton N

Henry Lee

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Curt Lindner DanMartin(part-time)

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Nancy Osgood

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f Carl Withee s

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meeting was held at the request of iiorthern States Power Company (NSP)"at'j

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'.7 i.Rockville,' Maryland, on September 25, 1989, concerning the transport of the

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M Pathfinder reactor vessel..The Pathfinder plant'is being decommissioned. 'Thec, Uj Jt'

' reactor vessel will be transported intact from Sioux Falls, South Dakota, to t s i-f.

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.LRichland, Washington. The fuel has been removed frcm the reactor vessel, but'

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.t jthe. reactor internals will-remain in place.

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Package Configuration

)Q w (Steel plates will-be welded over reactor vessel openings. The head will be t1 g

bolted on the vessel using the original head studs. The vessel will be filled

~

.w ti h gravel and grout to immobilize loose surface radioar.tivity. A steel plate

.will"be installed around the vessel for radiation shielding. Aluminum honeycomb L

material will be installed around the package to act as an impact limiter.

i There are no lifting or tiedown fixtures which are a structural part of the package.

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F es a;

t i-r Drop Analysis-

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)g'.);.?The.vesselEillbeanalyzedfora1-foctsidedropandadropatananglewith.

, "one end susper.d6d one foot. These drop configurations.were chosen as the worst.

tcase credible dropsJduring transport. Results of the drop analyses are< included 3

7 in the neeting handout..

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4 An activation analysis has been performed ~ that demonstrates that radioactivity,

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w' concentrations meet-the requirements for low specific activity (LSA). The total-radioactivity is estimated at 467 Ci in activated metal components and 95 mci e

.as' loose surface contamination. The radioactivity is primarily Co-60. Since" the total' radioactivity exceeds two times the A2 valve for Co-60, it was 4

= recomended that NSP investigate the potential impact of the 10 CFR Part-71 c proposed rule = change, which limits radioactivity to two times A2 for LSA Type A-packages.

Schedule

'. An application for the. certification of the reactor vessel as a Type A LSA packagc is.5xpected to be submitted to NRC on October 20, 1989. NSP is hoping for approvul by July, 1990. The actual shipping date is expected to be in the fall, 1990.

Y%

Nancy L. Osgood Transportation Branch, HMSS i

Enclosure:

Meeting 11andout

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Material Application Modulus Strength Strength.

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L 2.3 MECHANICAL PROPERTIES (CONT.).

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SUMMARY

OF DESIGN STRESS INTENSITY VALUES, SmL Y

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fi CRITERIA AND METHOD OF APPROACH

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DESIGN' CRITERI A

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Initial Conditions -

Ambient tempetature at -20 deg. F with;no insolation, Land sh i

ambient temperature at 100 deg F with maximum insolation.

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Cc:d environment - Cold ambient temperature of -40 deg F in still air and shade 1!

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generation

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of RPV and ASME Code calculations.

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Water spray will not have a significant effect on package.

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Corner drop not applicable per 10 CFR L71(c)(8).

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2.6.10 PENETRATION and 2.6.11 LOAD 1 RESISTANCE-M[

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Penetration Design Criteria --10 CFR 71 F (e)(10) di i

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13.0 lb steel cylinder 1.25 j

in dia dropping from '40.0 N

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Stanford Research Institute (SRI) i e

analytical equations.-

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- Available thickness

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l

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Load Resistance Design Criteria - Acceleration 5g vertical F

downward I

Method of Approach - Classical beam analysis supported l

at its ends.

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- allowable stress 3 Sm - 37.8 kei

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- margin of. safety 9.0

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2.6.7 FREE DROP

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!E Design Criteria - 10 CFR 71 - One foot drop onto a flat j;

essentially unyeilding horizontal surface.

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4 Method of Approach -

Case 1 - Drop of the vessel along its length.

E Package weight and kinetic energy distributed y

along its length.-

Case 2 - Drop of the vessel at its edge wherein 50% of f/

package weight and associated kinetic energy is y

transmitted on one edge of the vessel.

p i

impact l

Limiter - Precrushed HEXCEL energy absorbing material.

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Step-by-step evaluation of' maximum stress in RPV at each 9

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incremental depth of crushing. At each step, determine Resistance offered by.HEXCEL core n

Energy absorbed by HEVCEL core

[j Maximum stress in RPV wall.

p Repeat process until external energy - O.

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