ML19296D493
| ML19296D493 | |
| Person / Time | |
|---|---|
| Site: | North Anna, 07002718  |
| Issue date: | 10/16/1979 |
| From: | Stallings C Virginia Power (Virginia Electric & Power Co) |
| To: | |
| Shared Package | |
| ML19296D480 | List: |
| References | |
| 14428, NUDOCS 8003040682 | |
| Download: ML19296D493 (7) | |
Text
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ENCLOSURE REVISIONS TO OCTOBER 3, 1977 APPLICATION FOR SNM-1801 NORTH ANNA UNIT 2 (All page and attachment numbers refer to original application)
APPLICATION OF THE VIRGINIA ELECTRIC AND POWER COMPANY FOR A LICENSE TO RECEIVE, POSSESS AND STORE SPECIAL NUCLEAR MATERIAL AT THE NORTH ANNA POWER STATION 1.0 General Information 1.1 Application Virginia Electric and Power Company (hereinafter referred to as
" Applicant"), pursuant to the Regulations of the Nuclear Regula-tory Commission (10 CFR, Part 70), hereby applies for a license to receive, possess, inspect, store, and pack for delivery to a carrier, special nuclear material in the form of new fuel assemblies and in-core fission chamber detectors as described herein. Authority is also requested to use a fuel assembly for checking final alignment of fuel handing equipment, including the indexing of the manipulator crane.
1.2 Carocrate Data The Applicant is Virginia Electric and Power Company, the principal g
office of which is located at One James River Plaza, Richmond, Vir-l ginia 23209.
Other information concerning the Applicant is set forth in the application of Virginia Electric and Power Company, as amended, filed as Docket Nos. 50-338 and 50-339.
1.3 Identification of Reactor The fuel assemblies referred to in Section 1.1 will make up the first core of the reactor of North Anna Power Station Unit No. 2.
North Anna Power Station is presently under construction on a site on the southern shore of Lake Anna, in Louisa County, Virginia, approximately 40 miles north of Richmond.
The site is described in the Final Safety Analysis Report, which was submitted to the AEC on April 30, 1973. Construction of Unit No. 2 was authorized by the Atomic Energy Commission in construction permit CPPR-78 issued on February 19, 1971, in Docket No. 50-339.
1.4 Period of License The Applicant requests that the license applied for herein be issued prior to Feb. 1, 1978, to accommodate the earliest anticipated arrival date of the first shipment of fuel, and that the license continue in effect until the licensed activities are authorized by issuance of the Operating License for Unit No. 2.
Page 1 of 9
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9 3.
Fuel Storage 3.1 _ Storage Areas The location and general details of the fuel storage area are shown in FSAR Figures 1.2-2, 1.2-17, and 1.2-18, copies of which are attached.
(Nos. 4, 5, and 6) The fuel storage facili-ties are designated Seismic Class I, and are designed to withstand, without loss of capability to protect the public, the most severe environmental phenomena ever experienced at the site with appro-priate cargins included in the design for uncertainties in histori-cal data.
The fuel building is fully discussed in Sections 3.8.1 and 9.1.2 of the FSAR.
3.2 Storage Facility Equipment ine new ruel storage area is designed to hold 126 new fuel assemblies in specially constructed racks.
The remaining fuel assemblies for the first core are stored in the spent fuel pool.
The storage racks in both areas are designed to form a subcritical array with a center-to-center spacing between fuel assemblies of 21 inches in the new fuel area, and 14 inches in the spent fuel pool.
The racks consist of square guide tubes, open at both ends, supported in a structural steel network at the top, and restrained in the horizontal direction at the bottom. The fuel assemblies, when in-serted in the guide tubes of the new fuel racks, are supported by the stainless steel lined concrete floor of the storage area.
The base of the spent fuel racks serves to support the weight of the fuel assemblies, and to distribute the load to the spent fuel pool floor.
A movable platform with two electric hoists runs over the spent and new fuel storage areas.
Cranes carrying heavy objects, such as a spent fuel cask, are prevented by design from passing over the stored fuel, as shown on Figs. 1.2-17 and 1.1-18.
(Attachment Nos. 5 & 6) 3.3 Fire Protcction The materials used in construction of the fuel storage area are concrete and steel.
The fuel assemblies themselves and the fuel racks which hold the fuel are also constructed of non-flammable materials. After fuel is stored therein, the fuel storage area vill be under constant access control.
Therefore, a fire in the fuel storage area is highly unlikely.
Nevertheless, fire fighting equipment will be available.
Page 3 of 9 d
a-3.4 Security The special nuclear material will be protected as described in Section 13.7 of the operating license application and the security plan.
4.
Transfer of Fuel Transportation of the fuel assemblies from the fabrication location at Columbia, South Carolina, to the fuel building at Unit No. 2 will be the responsibility of the fuel fabricator, Westinghouse Electric Corpora-tion, Nuclear Fuel Division, Post Office Box 355, Pittsburgh, Pennsylvania 15230.
The fuel assemblies will be delivered in shipping containers which are the property of the fuel fabricator.
The shipping container is a steel structure capable of storing or transporting one or two fuel assemb lies. Westinghouse Las been licensed by the U. S. Nuclear Regulatory Commissian License SNM-1107, Docket 70-1151, to package and transport fuel assemblies in such shipping containers.
Fuel assemblies will arrive at the storage site in the above described containers, which will be transported immediately into the fuel building. As soon as practicable after arrival, the fuel assemblies will be individually removed from the shipping containers and placed in one of the fuel storage areas.
5.
Financial Protection In accordance with the Code of Federal Regulations, Chapter 10, Section 140.13, the Applicant will make application for nuclear energy liability insurance in the amount of $1,000,000 to take effect on or prior to I
the earliest possible date for delivery of fuel, and the requested effective date of the Special Nuclear Materials License. A certificate of this insurance will be forwarded to the Commission.
The financial protection will continue in effect until just prior to loading the first fuel assembly into the reactor, at which time nuclear third party liability insurance will be provided.
6.
Radiation Control 6.1 Responsibility The Station Manager will have supervisory control over all Applicant personnel assigned to the North Anna Power Station and administrative control over all other personnel or persons within site boundaries.
He will be responsible for the safe performance of.all equipment and functions in the station.
In this responsibility, he will be assisted and advised by the Station Nuclear Safety and Operating Committee, which is comprised of the following staff members: Station Manger, Superintendent Operations, Superintendent Maintenance, Superintendent Technical Services.
Page 4 of 9
The qualifications of each of these members are given in Section 13.1.3 of the FSAR.
Direct radiation control is the responsibility of the Supervisor Health Physics.
His experience is detailed in 13.1.3.2 of the FSAR.
l 6.2 Radiation Control Drocedure Each new fuel assembly, as it is removed from its shipping con-tainer, will be checked visually for cleanliness, integrity and numbering. The check will include smear sampling to detect removable radioactive contamination of both alpha and beta-gamma emitters.
If there is a positive indication of radioactive con-tamination, the surface of the assembly will be wiped thoroughly and rechecked until free of contamination.
When the assembly has passed inspection, it will be placed in its designated storage l
location, either in the new fuel storage area, or the spent fuel storage pool.
l s
During periods of fuel handling, radiation surveillance will be carried out by a radiation technician.
Further details concerning the applicant's radiation monitoring procedures can be found in Section 12.1.4 of the FSAR.
Health Physics personnel will routinely perform weekly radiation surveys in the fuel storage area of the fuel building, once receipt of new fuel has begun.
Personnel monitoring procedures will ensure compliance with 10 CFR 20.
Self reading dosimeters or thermoluminescent dosimeters, or both, will be worn by all persons in the fuel storage areas.
7.
Nuclear Criticality Safety 7.1 Fuel Handling The loaded fuel shipping containers will be brought into the fuei building through the trailer loading and unloading area utilizing the fuel transfer platform hoist.
The new fuel assemblies will then be removed one at a time from the shipping containers for inspection. When the inspection has been satisfactorily completed, the assembly will be lowered into its designated storage location in either the new fuel storage vault or the spent fuel pool. This procedure of handling and inspecting only one fuel assembly at a time precludes completely any possibility of criticality occurring during the handling operations.
Page 5 of 9
7.2 Nuclear Safety Evaluation The storage racks in the new fuel storage area are designed to provide a center-to-center spacing of 21 inches between the fuel assemblies; those in the spent fuel pool provide a spacing of 14 inches.
Cal-culations based upon use of the LEOPARD type and PDQ codes in computing the lattice and spatial properties of the fuel array have demonstrated that maximum kef f in the event of flooding of either the new fuel area or the spent fuel pool with unborated water will be 50.95.
Thus, nuclear l
safety is u;smred even in the unlikely event that the fuel were to be submerged in unborated water.
All handling of the fuel will be performed only by designated qualified personnel under direct surveillance of a supervisor, following procedures approved by the Station Nuclear Safety and Operating Committee.
7.3 Recuest for Exemation The applicant requests an exemption from the further requirements of 10 CFR Section 70.24 on the basis that the security facilities and procedural controls employed at the North Anna Power Station prevent the possibility of accidental criticality during receipt, unloading, inspection and storage of the fuel assemblies.
8.
Accident Analysis The possibility of a fuel handling incident is very remote because of the extensive administrative controls and physical limitations imposed on all fuel handling operations. All fuel handling is conducted in accordance with prescribed procedures, approved by the Station Nuclear Safety and Operating Cocnittee.
In both fuel storage areas, the design of storage racks and manipulation equipment is such that:
1.
Fuel at rest is positioned by positive restraints in an always sub-critical (keff E0.95), geometrical array. No credit is taken for l
boric acid in the water.
2.
A maximum of one fuel assembly can be handled at one time.
3.
Violation of procedures by placing one fuel assembly next to any group of assemblies in the racks will not result in criticality.
4.
Crane facilities do not permit the handling of heavy objects, such as a spent fuel shipping container, above the fuel racks.
5.
The motions of the fuel transfer platform hoist are limited to a very low speed.
The fuel handling tool suspended from the overhead hoist is designed to engage the fuel element, and because of its geometry, cannot grip on any part of the Page 6 of 9
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