Control of Heavy Loads Near Spent Fuel (Generic Letter 78-16)
GL78016
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555
May 16, 1978
Licensees for all Plants in the Systematic
Evaluation Program
In January, 1978, the NRC published NUREG-0410 entitled "NRC Program for the
Resolution of Generic Issues Related to Nuclear Power Plants." As part of
this program, the Task Action Plan for Category A Technical 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
onto 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
environment and a potential for radiation over-exposures to inplant
personnel. If the dropped object is large, and the damaged fuel contained a
large amount of undecayed fission products, radiation releases to the
environment could exceed 10 CFR Part 100 guidelines. These concerns are
currently considered in licensing reviews. We believe there is a need to
systematically review NRC requirements, facility designs and technical
specifications regarding the movement of heavy loads, to assess safety
margins and to improve those margins where warranted.
The staff efforts currently underway commenced with a detailed evaluation of
current NRC requirements and licensee procedures for the movement of heavy
loads near spent fuel. Based on the results of that evaluation assessments
will be performed of the probabilities and consequences of heavy loads
damaging spent fuel. A determination will then be made of the need for
revising the Standard Review Plan, the Standard Format and Content of Safety
Analysis Reports for Nuclear Power Plants and the Standard Technical
Specifications.
All licensees except those in the Systematic Evaluation Program are being
requested to provide information regarding the movement of heavy loads near
spent fuel at their facilities. A copy of the information request in
enclosed for your use. You need not submit this information for your
facility at the present, however, it will be required and reviewed during
the SEP program for your plant. This request had been reviewed by the
General Accounting Office and approved under Clearance No. B-180225 (R0522).
This clearance expires February 28, 1981.
.
- 2 - May 16, 1978
In the interim, while these efforts are ongoing, you should review your
current procedures for the movement of heavy loads over spent fuel to assure
that the potential for a handling accident which could result in damage for
spent fuel is kept at a minimum.
Sincerely,
Victor Stello, Jr., Director
Division of Operating Reactors
Office of Nuclear Reactor Regulation
Enclosure:
Information Request
.
Approved by GAO
B-180225 (R0522)
Expires 2-28-81
Enclosure
INFORMATION REQUESTED
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
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 or
will be used at your facility?
4. Identify any heavy load or cask drop analyses performed to date for
your facility. Provide a copy of all such analyses not previously
submitted to the NRC staff.
5. Identify any heavy loads that are carried over equipment required for
the safe shutdown of a plant that is operating at the time the load is
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.
6. If heavy load are required to be carried over the spent fuel storage
pool or fuel transfer canal at your facility, discuss the feasibility
of a handling accident which could result in water leakage severe
enough to uncover the spent fuel. Describe the basis for your
conclusions.
7. Describe any design features of your facility which affect the
potential for a heavy load handling accident involving spent fuel,
e.g., utilization of a single failure-proof crane.
8. Provide copies of all procedures currently in effect at your facility
for the movement of heavy loads over the reactor core during refueling,
the spent fuel storage pool, or equipment required for the safe
shut-down of a plant that is operating at the time the move occurs.
9. Discuss the degree to which your facility complies with the eight (8)
regulatory positions delineated in Regulatory Guide 1.13 (Revision 1,
December, 1975) regarding Spent Fuel Storage Facility Design Basis.
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