ML19317G783

Forwards Request for Info Re Util Procedures & Plant Sys for Movement of Heavy Loads Near Spent Fuel.Util Should Review Procedures for Heavy Load Movement to Assure Min Potential for Handling Accidents Causing Spent Fuel Damage

ML19317G783
Person / Time
Site:	Rancho Seco
Issue date:	05/17/1978
From:	Stello V Office of Nuclear Reactor Regulation
To:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML19317G774	List: ML19317G773 ML19317G783
References
NUDOCS 8004010609
Download: ML19317G783 (3)

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UNITED STATES

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NUCLEAR REGULATORY COMMISslON hn WASHING TON, D. C. 20555 t

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May 17,1978 5: -

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All Licensees for Power Reactors except those in the Systenatic

j Evaluation Program

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In January,1978, the NRC published NUREG-0410 entitled "NRC Program

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As part of this program, the Task Action Plan for Category A Technical

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Activity No. A-36, " Control of Heavy Loads Near Spent Fuel", was approved.

As you are aware, overhead handling systems are used to lift heavy objects in the vicinity of spent fuel in both PWRs and BWRs.

If a heavy object, e.g., a spent fuel shipping cask or a shielding block, were to fall or tip E.!

on to spent fuel in the storage pool or the reactor core during refueling and damage the fuel, there could be a release of radioactivity to the

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environment and a potential for radiation over-exposures to inplant per-

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sonnel.

If the dropped object is large, and the damaged fuel contained a large amount of undecayed fitsion products, radiation releases to the environment could exceed 10 CFR Part 100 guidelines. These concerns are

?.i currently considered in licensing reviews. We believe there is a need

[.H to systematically review NRC requirements, facility designs and technical i.!

specifications regarding the movement of heavy loads, to assess safety

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r.argins and to improve those margins where warranted.

7;g The staff efforts currently underway commenced with a detailed evaluation 5=

of current NRC requirements and licensee procedures for the movement of

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heavy loads near spent fuel.

Bassi on the results of that evaluation, zw====-

assessments will be performed of t.ic probabilities and consequences of FE===

heavy loads damaging spent fuel. A determination will then be made of the 5.;

need for revising the Standard Review Plan, the Standard Format and Con-2.==-

tent nf Safety Analysis Reports for Nuclear Power Plants and the Standard

[if= ;is Technical Specifications.

E E gnaru Based on a review of the adequacy of the information currently available

&M in the docket files regarding licensee procedures and plant systems for the

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movement of heavy loads near spent fuel, we have determined that additional E...

information is necessary.

Accordingly, the enclosure provides a list of

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information required by the staff to continue the evaluation of this concern.

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.. May 17, 1978-

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Within 45' days of the receipt of this letter, you are requested to pro-vide the information requested in the enclosure.. Some of the information s=== -

requested may have previously been provided to the NRC.

If this is correct, a reference identifying when and where that information was F==

provided will suffice or you may, at your option, provide another copy gg=g with your response. Any questions regarding this request should be for-1;;;;;;;.;

warded to the Task Manager for this effort, James A. Long, (301) 492-8041.

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This request has been reviewed by the General Accounting Office and approved under Clearance No. B-180225 (R0522). This clearance expires 2/28/31.

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.:q In the interim, while these efforts are ongoing, you should review your current procedures for the movement of heavy loads over spent fuel to F.i.i.iq assure that the potential for a handling accident which could result in p: 751 damage to spent fuel.is kept to a minimum.

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.cf Ed Sincerely,

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.1 Vi tor Stel o; dre,'/, irector

'=1 Division of perdting Reactors Office of Nuclear Reactor Regulation Ex:2.

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Enclosure:

Infonnation Request

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I Approved by GA0 B-180225 (R0522)

="F Expires 2/28/81 Enclosure INFORMATION REQUESTED

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1.

Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.

2.

Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool.

For each object listed, provide its approximate weight and size, a diagram

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of the movement path utilized (including

• carrying height) and the frequency of movement.

3.

What are the dimensions and weights of the spent fuel casks that are

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or will be used at your facility?

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4.

Identify any heavy load or cask drop analyses performed to date for' j:.::

your facility.

Provide a copy of all such analyses not previously p

submitted to the NRC staff.

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5.

Identify any heavy loads that are carried over equipment required for

[F the safe shutdown of a plant that is operating at the time the load is p.

moved.

Identify what equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc.) and discuss the feasibility of such an accident affecting this equipment. Describe the basis for your conclusions.

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If heavy loads are required to be carried over the spent fuel storage i ~'

!..E pool or fuel transfer canal at your facility, discuss the feasibility I=

of-a handling accident which could result in water leakage severe enough to uncover the spent fuel. Describe the basis for your conclusions.

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Describe any design features of your facility which affect the potential m.,

for a heavy load handling accident involving spent fuel, e.g., utilization F="

of a single failure-proof crane.

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Provide copies of all procedures currently in effect at your facility i[ _

for the movement of heavy loads over the reactor core during refueling, Egg;E the spent 'uel storage pool, or equipment required for the safe shut-down of a plant that is operating at the time the move occurs.

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Discuss the degree to which your facility complies with the eight (8) ngulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December,1975) regarding Spent Fuel Storage Facility Design Basis.

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