ML20096G034

Requests Explanation on Wepco Selection of Vsc Designed by Sierra Nuclear Corp for Implementation at Plant

ML20096G034
Person / Time
Site:	Point Beach
Issue date:	05/01/1992
From:	Shillinglaw F AFFILIATION NOT ASSIGNED
To:	Samworth B NRC
References
NUDOCS 9205220129
Download: ML20096G034 (7)

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L - p t+M % i M l' C o % cht W M n-C IE 47 Additional discussion regarding the design of physical provisions for ISFSI protection (guard houses, ferices, intrusion detectioc, etc.) are provided in Section 1.E.

H.

DECOMMISSIONING Decommissioning of the ISFSI will be performed in a manner similar to and in the same time frame as the decommissioning of Point Beach Nuclear Plant. This is predicated on the ability of the federal government to accept spent fuel as mandated by the Nuclear Waste Policy Act of 1982, as amended. It is anticipated that the MSBs will be transported in a compatible shipping cask to a federal repository when such a facility is y

F operational. However, should the storage facility not accept the MSBs intact, the VSC-24 system allows the MSBs to be brought back into the pool and the fuel repositioned into the racks for loading into transport casks to be provided by the DOE.

The empty MSBs can be decontaminated ofloose radioactive material by conventional water spr:ys and wipe downs. However, the small amount of neutron emissions from the stored fuel may slightly activate the MSB

=

steel. Depending on this level of activation, the MSBs either will be processed, packaged, and shipped for f

shallow land burial or will be sold as salvageable scrap.

Decontamination of the empty concrete cask can be accomplished through the use of conventional high

{

pressure water sprays to reduce contamination on the cask interior. He sources of contamination on the interior of the cask would be only crud frora the outside of the MSB. He expected low levels of contamination from this source can be easily removed with a high pressure water spray and wipe-down.

After decontamination, the VSC metal can be cut up for scrap or panially scrapped and any remaining contaminated portioe.s shipped as radioactive waste to a disposal facilitv. Concrete cask material will be broken apart and shipped to a landfill.

Due to the leak tight design of the MSB, no residual contamination is expecteo e be left behind on the l

concrete base pad. The base pad, fence, and peripheral utility structures are de facto decommissioned when Cie last cask is removed and may be dismantled with the rest of the plant.

l The spent fuel pool at Point Beach will remain functional until the ISFSI is decommissioned. This will allow f

the pool to be utilized to transfer fuel from the MSB to licensed shipping containers for shipment off-site.

I.

ESTIMATES OF INDUCED DEVELOPMENT No significant induced development is expected to be associated with the proposed ISFSI.

ElI J.

FEASIBILTlY ANALYSIS The VSC-24 system is a feasible technology which has been tested in a 17 assembly version at the Idaho Nuclear Engineering Laboratory. A Topical Safety Analysis Report has been submitted to the NRC and approved in the NRC's oafety Evaluation Report dated March 29,1991. At least one commercial installation g

(at the Consumers Power Company Palisades Plant) will be in place and functional prior to the start-up of g

the Point Beach ISFSI.

I 4

33

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(continued)

SATIC;UAEN11t St 71tEFT, DIVERSION OR ESTIMATES OF INDUaD ACCDENT IMPAC"!3 SABOTAGE DECOMMISSIONING DEVELOPMENT FEA5:BIIJ1T ANALYSIS PROPOSED PROJECT See ana wis of potential Spent fuel would be Spent feelin basket Little induced Feasible. NRC neense (CONCRETE CASK) acciden' impacts, page stored wit

• in the fenced would be transferred to development in the already plant boundary and transport casts.

Point Desch area. M,st

.wdProposed security measures Remainderof storage casks sad ISFSI

. cask. e successfully tested developed to safeguard casks would be disposed compocents are made in

. by DOE, currently the stored fuel.

as low-level waste. Pad other states.

being implemented at and other suode

. Patiandes.

would be handled as regular construction debris.

METM, CASKS Same as for the Same as for the Spent fuel would have Same as for the Fearible. Some types of proposed project.

proposed project.

to be transferred to a pied project.

casks already licensed transport cask.

and in use.

Otherwise, same as proposed propect.

PAODULAR Same as for the Sectrrity could be easier Ess-ntirlly the same as More on-cite Feasible. NRC license CONCRETE propowd project.

to provide since the for the yma constructio a would be already issued, in use at spent fuel would be project, excelt there required, but could be two sites now.

stored in fixed concrete would be mors absorbed by locallabor structures.

construction debris due pool with little impact.

to the larger amount of fixed structores.

VAULT Same as for the Security would be easier More difncult due to the Essentially the same as Feasible. Similar proposed project.

to provide since the fact that there would be for modraar concrete.

facility planned for Ft.

spent fuel would be a greater amount of He larger facility to te St. Vrain reactor in stored withm a vauh.

both low-level waste built could result in Coknoo. NRC and coutuwGus debris.

some short term approval granted.

employment surge in the construction trades.

STORAGE /

Samo as fx the Same as for the WonM be easier than Same as for the Feasible. None in use, TRANSPORT CASKS.

proposed project.

proposed project.

the proposed project propowd project.

but are under because the fuel could consideration. No cask be shipped without has dual certificauon

.epackaging. Casks (storage / transport) yet.

would be disposed as low-level waste. ISFSI pad and other structures would be disposed as construction debris.

d

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