ML20062E980

Summary of 901107 Telcon W/Util,New York Power Authority & Stone & Webster Re Reactor Pressure Vessel Transportation

ML20062E980
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/15/1990
From:	Osgood N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9011270008
Download: ML20062E980 (18)

Text

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!c l' NOV 1 6 1990 i

SGTB:NLO ,

50-322 MEMORANDUM FOR: The Files  !

FROM: Nancy L. Osgood, SGTB, SGTR, NMSS i

SUMMARY

OF TELEPHONE CONFERENCE CALL REGARDING TRANSPORTING

! SHOREHAM REACTOR PRESSURE VESSEL Participants l 1

fiRC LILCo Stone & Webster l l Stewart Brown (part time) Sheldon Schreiner Jim Powers l Marissa Garcia uary Gisonda Jerry Liu l Henry Lee George East Nancy Osgood fi1E8 j Li Yang Siva Kumar '

Fred Shar l Introduction A telephone conference call was held on November 7 - 1990, at the request of Long Island Lighting Co. (LILCo), to discuss transporting the.Shoreham reactor pressure vessel (RPV). LILCo stated that they were exploring several options for removing the RPV from the plant. One option was to remove the RPt whole and to transport it intact to a dis >osal site.. - To'furtherl evaluate this option, LILCo was requesting that tie NRC Transportation; Branch discuss the requirements that apply to qualifying the reactor vessel as a radioactive materials transport package. It was emphasized that no decision.had yet been-made en the disposition of the RPV, Discussion The discussion centered on the attached handout. The handout'was transmitted by: facsimile to NRC staff on November 6,1990.

1. Package Description The fuel has been removed from the RPV. Other components which may have high concentrations of radioactivity may also be removed. Most reactor '

internals would remain in the vessel. The head would be removed- from- .,

the vessel, and a cover plate bolted over the vessel opening.L Other  ;

nozzles would be cut off close to the vessel, and.would'also have cover plates. The head would not be part of the package. -Pipes acting as an impact limiter would be used in some' areas around the vessel.. The vessel dimensions are approximately 20 feet in diameter by 67 feet long.

The vessel wall thickness is approximatelyL5.5 to 6.5-inches.. The total package weight is estimated'at 800 tons.

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, 2. Radioactivity

.. . i The estimate of radioactivity is included-in the-handout. -The estimates indicate that the vessel and its internals may qualify as low specific ,

activity radioactive material. It was suggested that if an application is submitted, that-the neutron flux levels and neutron energy spectrum i R

be described in the application, and that benchmarking radiation measurements be reported. Sufficient.information should be provided so

, that NRC staff can perform independent-verification calculations'of- l l radioactivity and radioactivity concentration.

3. Structural Evaluation The structural issues discussed are included in the handout. The structural analyses would consider two oblique drops at shallow angles.-

One dro) would look at impact at the vessel flange, and one- at- the bottom lead. :Some type of impact limiters will be used. The current concept is-to place pipes at particular points to absorb impact energy.

Impact limiters would also be used to prevent nozzle stubs from direct ,

impact. NRC staff stated that force-deformation-information would be ,

required for. any impact limiters. NRC staff recommended that elastic analysis be used for drops. Load combinations should include stresses '

due to impact, pressure and thermal loads. NRC staff stated that fracture toughness of the package should be inherent in the material.

NRC staff stated that'it will not be-necessary to evaluate crack initiation and propagation if the material itself can be shown to have .

adequate fracture toughness. Operational controls, such as confining-the shipment to summer months, could possibly be considered in the-evaluation of fracture toughness in extremely, low temperatures.

Cristant signed by.

. Nancy L.'Osgood I Transportation Branch Division of Safeguards and Transportation, NMSS:

Attachment:

Handout ,

DISTRIBUTION:

NRC File Center Participants;- w/out att. A i

iNRCSPORM7 Meeting Notebook --w/out att.

NMSS r/f - w/out att. CRChappell - w/out att.

SGTB r/f - w/out att. CEMacDonald - w/out att. 3 0FC :SGTB' y :SGT

................... ..................................................... 1 NAME:NL0sgood :C happell I

..................................................... j DATE:11/N/90. .111/ . . . . . . . . . . . . . . . . . . .b9 0 0FFICIAL RECORD COPY l

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2 COMPONENTS REMOVED BEFORE SHIPMENT

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.REACTOd ACTIVATION ANALYSIS RESULTS .

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Top Fuel Core Jet Core Vessel Inner 1/2 l Isotope A2 Guide Shroud Pumps Support Clad Vessel Was i

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! Isi 100 5.55E-03 2.43E-04 3.05E-05 1.24E-04 9.02E-07 6.12E-09

! 5'suin 20 6.97E-03 0.00 0.00 1.56E-04 0.00 1.91E-07

! [ Ni 900 4.05E-95 1.76E-06 2.21E-07 9.06E 1.5fE-09 4.44E-11

! Totals - 2.81E-01 1.06E-02 1.33E-03 6.28E-03 3.93E-05 Si.06E-06 h.

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2 PREPARATION FOR SHIPMENT .

Remove specified ' components Cut-back nozzles (piping & CRD)

Plug and shield nozzles Add cribbing to support shroud Add closure plate at top of RPV Attach lifting rig Lift and lower Attach up. ender (outside containment)

Add impact limiters (Selected areas) s s  :

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i STEPS IN TRANSPORTING SHOREHAM RPV .

Seal Package Lift from containment Attach upender Up-end to horizontal position l

i Add impact limiters l Transfer to land transporter i Travel on site to dock j i .

Transfer to barge Barge transport to near burial site l Transfer to land transporter j 1 Travel on public roads at very low speed -

!M ii Transfer for burial

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PACKAGE EVALUATION .

LSA package Lifting Evaluate vessel (Initial lift, subsequent jacking)

Evaluate attachments

. Lift rig to RPV flange bolt circki Upender to RPV skirt

Consider limiting orientations l Stresses < 1/3 yield l

Tie-Down

Saddle supports, strap, and upender Lg No structural attachment to vessel except skirt Li 10g axial load on vessel produces low stress in skirt .

!$ in case of excessive load, skirt will fail w/o knpairing vessel l Transport E Described in detail on subsequent pages -

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i TRANSPORT LOADS .

l Deadweight l Tie-down strap tension i i

Thermal i i Uneven solar heating @ 100T ambient l Sudden temperature drop (-20T to -40T)

! Pressure l 11.2 psig intemal, 5.3 psig extemal l Vibration / Shock i j Considered negligible due to low transport speeds Drop impact (1 foot) j}

l Side impact, two cases (Top closure, lower vessel)

Penetration L

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ACCEPTANCE CRITERIA .

ASME analysis criteria will be used for convenience l Deadweight, strap-tension, thermal, pressure l Stress intensity less than ASME RI Service Level A Drop Impact Plastic deformation of unpact runiters and vessel

, No breach of vessel boundary Meet ASME Appendix F Penetration ~

Meet BRL formula e

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l METHODS OF EVALUATION t

Manual Evaluation l Pressure per ASME rules (Vessel, closure plates, nozzle

! reinforcement) l Strap tension l

Penetration

Finite Element Evaluation

! Deadweight .

! Pressure Thermal Drop Impact i

g Load Combinations g Deadweight + Pressure + Thermal , ,

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BRIi ILE FRACTURE PREVENTION Linear-elastic and elastic-plastic fracture mechanics Similar to NUREG/CR-3826

Review fracture toughness data or requirements l

Review NDE data to establish flaw size

! Envelop transport loads (including drop)

! Evaluate crack initiation i

Evaluate crack propagation a

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