ML23331A903
| ML23331A903 | |
| Person / Time | |
|---|---|
| Site: | 07103103 |
| Issue date: | 07/11/2017 |
| From: | Govt of Czech Republic, Office for Nuclear Safety, Secured Transportation Services |
| To: | Boyle R Office of Nuclear Material Safety and Safeguards, US Dept of Transportation (DOT), Office of Hazardous Materials Safety |
| Shared Package | |
| ML23331A891 | List: |
| References | |
| CAC 001794, EPID L-2023-DOT-0004 | |
| Download: ML23331A903 (10) | |
Text
ST AT E OFFICE FOR NUCLEAR SAFET Y
Senovázné nám. 9, 110 00 Prague 1 Nuclear Safety Division
In Prague, on: 11 July 2017 Ref. No.: SÚJB/ONRV/12586/2017 File No.: SÚJB/POD/25717/2016/1 RAW and Spent Nuclear Fuel Management Division Handled by: Mgr. Irena Petrová
RESOLUTION
The State Office for Nuclear Safety (SÚJB) as an ad ministrative body competent as per Section 3(3c) of Act No. 18/1997 Coll., on peaceful utilization of nuclear energy and ionizing radiation (the Atomic Act) and on amendment and supplement of some acts in the version in force on the date of commencement of the procedure (hereinafter Act No. 18/1997 Coll), in the administrative procedure commenced as per S. 44(1) of Act No. 500/2004 Coll., the Administration Rule (adm.r.), on 21 December 2016, based on an application submitted by party to the procedure according to Section 27(1a) of the Administration Rule - -KODA JS a.s., registered office Orlík 266/15, 316 00 Plze - Bolevec, Identification No. 25235753, Reg. No. 111121 (the party to the procedure), of 19 December 2016, Ref. No. JS-OBCH/464/16, in the matter of a repeated issue of Resolution on the type approval for cask for transport and storage of nuclear materials, has decided as follows:
SÚJB as per Section 67(1) of the Administration Rul e and Section 23(2) of Act No. 18/1997 Coll. and in accordance with Section 232(6) of Act No. 263/2016, the Atomic Act I
a p p r o v e s
the design type of -KODA VPVR/M cask as a B(U)F type for road and railroad transport, for inland waterway transport and for sea transport of spent nuclear fuel (VJP) - fuel assemblies (PS) or fuel elements from research reactors as described in Condition No. 1 of this Resolution, and assigns to this package system which is manufactured in compliance with the documentation being assessed the following identification mark
CZ/048/B(U)F-96
and assigns the following code marking to the Resolution on type approval of -KODA VPVR/M cask for the needs of international identification
CZ/048/B(U)F-96 (Rev. 2).
-KODA VPVR/M cask for transport of nuclear materials meets the requirements of Act No.18/1997 Coll. and pertinent implementation regulations, as well as the recommendation of the International Atomic Energy Agency IAEA Safety Standards, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, Specific Safety Requirements No. TS-R-1, Resolution ref. No. SÚJB/ONRV/12586/2017 2/10
International Atomic Energy Agency, Vienna, 2005 and requirements of international transport regulations that refer to the IAEA rules mentioned above.
II a p p r o v e s
the design type of -KODA VPVR/M cask as an S type for storage of spent nuclear fuel - fuel assemblies or fuel elements from research nuclear reactors as described in Condition No. 2 of this Resolution - in a relevant storage facility.
The cask for storage of nuclear materials meets the requirements of Act No.18/1997 Coll. and Regulation No. 317/2002 Coll., on type approval of casks for transport and storage of nuclear materials and radioactive substances, on type approval of ionizing radiation sources and on transport of nuclear materials and defined radioactive substances (on type approval and transport), in the version in force on the date of commencement of the administrative procedure.
-KODA VPVR/M Cask Description
-KODA VPVR/M cask (cask) consists of a cylindrical body which is reduced in its top and bottom parts with a rounded transition.
Placed in the inner cask space of a cylindrical shape with a smooth surface provided with aluminum spray is a basket of atabor sheets consisting of 36 square cells for fuel and a central hole for the basket suspension. A system of two upper and two lower lids provided with gaskets is used to close the cask. Each of the lids is screwed independently to the cask body.
The upper primary lid consists of a thick-wall cylindrical plate with a diameter of 630 mm. In the lid centre, there is a hole for inserting the basket central suspension. There are holes in the lid for drying the cask inner space before sealing the secondary lid and also holes for the basket tie rods. The lower primary lid is analogical as regards dimensions with the upper lid.
In the centre of the lid, there is a threaded hole for fixing the central suspension and threaded holes for the basket tie rods.
The upper secondary lid is a circular plate, on the inner front surface provided with a recess inserted into the body inner recess fixing thus the lid together with eight guide feathers against undesirable external force effects. The guide feathers are screwed along the lid perimeter. Made in the lid there is a receiver of the valve for vacuuming and filling the cask with helium. The receiver is covered with a massive cap. The lower secondary lid is dimensionally analogous to the upper one, however, there is no receiver. Each of the secondary lids is screwed to the body with 16 screws M36. The inner space between the primary and secondary lids is used for monitoring the cask leak tightness.
The cask is manufactured by -KODA JS a. s., Orlík 266/15, 316 00 Plze - Bolevec.
Cask parameters and illustration
-KODA VPVR/M cask parameters
Parameter Cask body outer diameter 1 200 mm Height without shock absorbers 1 505 mm Height with shock absorbers 2 155 mm Cask cylindrical wall thickness 300 mm Resolution ref. No. SÚJB/ONRV/12586/2017 3/10
Max. weight of loaded cask without shock absorbers 11 150 kg Max. weight of loaded cask with shock absorbers 12 390 kg Maximum weight of loaded fuel assemblies with VJP 450 kg
-KODA VPVR/M cask illustration
Cask use conditions:
The type-approved cask -KODA VPVR/M of type B(U)F identified CZ/048/B(U)F-96 can be used for road and railroad transport, for inland waterway transport and for sea transport and also for storage, in compliance with the limits and conditions of a respective storage facility, of fuel assemblies which can be, as follows:
A. Undamaged fuel assemblies B. Stainless steel hermetic casings a) With damaged fuel assemblies, b) With fuel elements from damaged fuel assemblies c) With parts of damaged fuel assemblies under the following conditions:
Resolution ref. No. SÚJB/ONRV/12586/2017 4/10
- 1. Admissible Radioactive Contents of Transport Cask a) Types of assemblies with VJP that can be loaded in cask EK-10, S-36, VVR-M, VVR-M2, VVR-M5, VVR-M7, VVR-(S)M, IRT-2M,IRT-3M, IRT-4M, TVR-S b) Number of assemblies (ZS) in the cask max. 36 c) Total activity of all assemblies in the cask max. 3,93.1015 Bq d) Residual heat power of one assembly in the cask max. 37.5 W e) Total residual heat power of ZS in the cask max. 450 W f) Initial nominal enrichment of fresh fuel with isotope 235U max.90% of weight g) Weight of 235U in each ZS in the cask max. 500 g
- 2. Admissible Radioactive Contents of Storage Cask a) Types of assemblies with VJP that can be loaded in cask EK-10, IRT-2M, IRT-4M, b) Number of ZS in the cask max. 36 c) Total activity of all ZS in the cask max. 3,93.10 15 Bq d) Residual heat power of one ZS in the cask max. 37.5 W e) Total residual heat power of all ZS in the cask max. 450 W f) Initial nominal enrichment of fresh fuel with isotope 235U max.80% of weight g) Max. weight of 235U in each ZS in the cask max. 500 g
- 3. Cooling Medium Gaseous helium with the maximum operating pressure up to 0,07 MPa (absolute pressure) is the cooling medium inside the cask. The filling of the cask with helium must be documented in a protocol.
- 4. Drying the Filled Cask Inner Space Closing and decontamination of filled cask must be followed by drying the cask inner space, which must be documented in a protocol, in accordance with Clause 7.4.8 Drying in the applicable version of document Transport and Storage Cask for Spent Fuel from Research Reactors (-KODA VPVR/M Cask), Safety Documentation for Type Approval according to SÚJB Regulation No. 317/2002 Coll., Ae 11543/Dok, -KODA JS a. s., and with Clause 8.3 Periodicity of In-Service Inspections in the applicable version of document Rules for Safe Handling -KODA VPVR/M Cask - Source Data for User Manual, Ae 11650/Dok, SKODA JS a.s.
The content of residual water in the cask inner space after finishing the drying must be lower than 10 g H2O/m3 of the inner volume, and this value must be achieved before performing helium leak-tightness tests. Compliance with condition p/t300 Pa/15 min. for the pressure increase rate in the space being dried at an absolute pressure lower than 600 Pa in the inner cask space is the dryness criterion of the volume being dried.
Resolution ref. No. SÚJB/ONRV/12586/2017 5/10
- 5. Leak-Tightness Test For transport and storage of spent nuclear fuel in cask, it is required to perform and document in a protocol helium leak-tightness test of the cask in accordance with Clause 7.7 Vacuuming and Leak-Tightness Tests in the applicable version of document Transport and Storage Cask for Spent Fuel from Research Reactors (-KODA VPVR/M Cask), Safety Documentation for Type Approval according to SÚJB R egulation No. 317/2002 Coll., Ae 11543/Dok, -KODA JS a. s., and with Clause 8.3 Periodicity of In-Service Inspections in the applicable version of document Rules for Safe Handling -KODA VPVR/M Cask -
Source Data for User Manual, Ae 11650/Dok, SKODA JS a.s., with the criterion of the maximum leakage of 1.10 -7Pa.m3.s-1 for each checked sealing barrier.
- 6. Dosimetric Inspection Cask decontamination must be followed by dosimetric check which must be documented in a protocol while the dose rate equivalent must not exceed 2 mSv/hr on the cask surface and 0.1 mSv/hr at a distance of 1 m from the cask surface.
During transport under the conditions of sole use, the above values can be exceeded in accordance with paragraph 72 in Supplement No. 4 to Regulation No. 317/2002 Coll., on type approval and transport; in such a case, the dose rate equivalent on the cask surface must not exceed a value of 10 mSv/h, 2 mSv/h on the vehicle surface and a value of 0.1 mSv/h at a distance of 2 m from the vehicle surface.
Non-fixed cask surface contamination must not be higher than:
for gamma and beta active nuclides 4,0 Bq/cm2, for alpha active nuclides with low toxicity 4,0 Bq/cm2, for the other alpha active nuclides 0,4 Bq/cm2.
when averaging the wipe results from the surface of 300 cm2, from the places with the highest local contamination of the cask. This condition also applies to an empty cask.
- 7. Maximum Allowable Cask Surface Temperature During transport, the temperature of the cask outer surface on easily accessible places must not exceed a value of 85°C. If the temperature of the cask outer surface is higher than 50°C, the cask must be transported under the conditions of sole use.
The surface temperature of the cask body during the storage of VJP must not exceed a value of 85°C at an ambient temperature from -40 to +38°C.
- 8. Handling and Maintenance
Cask handling and maintenance must be carried out in accordance with Clause 7 Operation and Maintenance in the applicable version of document Transport and Storage Cask for Spent Fuel from Research Reactors (-KODA VPVR/M Cask), Safety Documentation for Type Approval according to SÚJB Regulation No. 317/2002 Coll., Ae 11543/Dok,
-KODA JS a.s., and in accordance with the applicable version of document Rules for Safe Handling -KODA VPVR/M Cask - Source Data for User Manual, Ae 11650/Dok, SKODA JS a.s.
Resolution ref. No. SÚJB/ONRV/12586/2017 6/10
- 9. In-Service Inspections
In-service inspections will be performed in accordance with Clause 6 Periodicity of Cask In-Service Inspections in the applicable version of document Supplement No. 10 to Safety Documentation of -KODA VPVR/M Cask, Manual for Verification and Assessment of Compliance of -KODA VPVR/M Cask Properties and Parameters according to provision of Section 6 in Regulation 317/2002 Coll., Ae 11543/Dok, -KODA JS a. s., and with Clause 8.3 Periodicity of In-Service Inspections in the applicable version of document Rules for Safe Handling -KODA VPVR/M Cask - Source Data for User Manual, Ae 11650/Dok, SKODA JS a.s. and also in accordance with document Inspection and Service Plan of
-KODA VPVR/M and Transfer Casks, file No. PP 2404 191, ÚJV ez, a.s., as follows:
Periodic visual inspections of condition of the secondary lid screws, gaps between the secondary lid and the cask body, trunnion bolts and trunnions during storage once in a year, Periodic inspections of pressure in cask once in a year, Visual inspection of all basic cask components after every transport and before filling a previously used cask. Any handling the basket must be preceded by checking the integrity of the central suspension bayonet lock. After every transport, sealing Helicoflex in both secondary lids of the cask must be replaced, Periodic inspections of trunnion bolts condition for possible corrosion attack once in five years.
Cask inspections carried out according to the above cited documents must be documented in a protocol and archived throughout the cask life.
10 Quality Assurance
10.1 Every cask identified CZ/048/B(U)F-96 and having its serial number must be manufactured in compliance with the type-approved cask and must meet the parameters declared in the applicable version of document Transport and Storage Cask for Spent Fuel from Research Reactors (-KODA VPVR/M Cask), Safety Documentation for Type Approval according to SÚJB Regulation No. 317/2002 Coll., Ae 11543/Dok,
-KODA JS a.s.
10.2 Cask must be manufactured in accordance with the applicable version of document
-KODA JS a.s. Quality Plan, PZJ 02-04, -KODA JS a.s. related to the manufacture of this design type.
10.3 Compliance of every cask with the approved type mus t be proved and documented in a written Certificate of Compliance. The Certificate of Compliance must include all particulars in accordance with the requirements of § 6 of Regulation No. 317/2002 Coll.
on type approval and transport. For all newly manufactured casks, the Certificates of Compliance for all cask serial numbers will be sent to SÚJB prior to their first use at the latest.
11 Cask Marking and Labeling For transport, the cask must be marked and provided with labels in accordance with paragraphs 34 through 36, 38 and 39 and 41 through 44 in Supplement No. 4 to Regulation No. 317/2002 Coll., on type approval and transport, as follows:
Resolution ref. No. SÚJB/ONRV/12586/2017 7/10
a) The cask outer surface must be visibly, legibly and permanently provided with the following data:
Identification of carrier, consignee, or both, Cask number and correct transport name of the radioactive consignment, Maximum weight of full cask: 12 390 kg, Cask identification assigned by SÚJB: CZ/048/B(U)F-96, Cask serial number, Cask name and type: -KODA VPVR/M, type B(U)F.
b) Labels must be placed on two opposite sides of the cask outer surface according to a corresponding example in Fig. 2, 3, 4 and 5 in Supplement No. 4 to Regulation No.
317/2002 Coll., on type approval and transport, filled with data on the content, its activity and transport index (see paragraph 43 in Supplement 4 to Regulation No.317/2002 Coll.,
on type approval and transport).
c) Transport index (TI) is defined in accordance with Articles 26 and 27 of Supplement No.
4 to Regulation No. 317/2002 Coll., on type approval and transport. Criticality safety index (CSI) is then determined according to Articles 28 and 29 in Supplement No. 4 to Regulation No. 317/2002 Coll., on type approval and transport (according to the CSI determined in the safety documentation and submitted to SÚJB CSI = 0). Radioactive consignments (casks with radioactive contents) and outer packages are classified in relevant categories according to Clause 33 in Supplement No. 4 to Regulation No.
317/2002 Coll., on type approval and transport.
12 General Conditions 12.1 Resolution of the State Office for Nuclear Safety on type approval of -KODA VPVR/M cask with identification number CZ/048/B(U)F-96 is only valid for casks of a given serial number with a written Certificate of Compliance certifying under condition 10.3 of this Resolution that the cask of a given serial number has been manufactured in accordance with the submitted safety documentation and satisfies the parameters declared therein.
12.2 A copy of the Resolution on type approval of -KODA VPVR/M cask with identification number CZ/048/B(U)F-96 and of the written Certificate of Compliance according to condition 10.3 of this Resolution must be submitted by the permit holder upon request according to § 9 (1m) of Act No. 18/1997 Coll. to relevant competent authorities.
12.3 A report on the results of in-service inspections carried out according to condition 9 of this Resolution shall be sent by the permit holder without being asked to do so to the State Office for Nuclear Safety according to § 9 (1m) of Act No. 18/1997 Coll.
for every -KODA VPVR/M cask with a given serial number.
12.4 Fulfilment of conditions:
1 and 2 of this Resolution shall be documented by a cartogram of filling the cask and relevant data concerning the ZS with VJP, 4, 4, 6, 6, 9, 10 of this Resolution shall be documented in writing.
12.5 Before the first use of -KODA VPVR/M cask with identification number CZ/048/B(U)F-96, the respective permit holder shall demonstrate to the State Office for Nuclear Safety according to § 9 (1m) of Act No. 18/1997 Coll. that it owns respective regulations for handling the cask that are in compliance with the documentation cited in conditions 4, 5, 8, 9 of this Resolution.
Resolution ref. No. SÚJB/ONRV/12586/2017 8/10
12.6 Operation records for the -KODA VPVR/M cask of a given serial number must be archived by the permit holder throughout the cask life according to Section 9 (1m) of Act No. 18/1997 Coll.
12.7 The application for type approval of -KODA VPVR/M cask with identification number CZ/048/B(U)F-96 for transport and storage of VJP submitted before the expiry of this Resolution must be supported by updated safety documentation proving particularly the fact that, due to radiation, temperature and pressure stress of the cask, and/or due to handling the cask during transport and storage of VJP, no changes occurred in strength, shielding and sealing characteristics or other properties declared in the safety documentation assessed by SÚJB before the issue of Resolution No.
5637/2011 of 14 March 2011, and -KODA VPVR/M casks meet the properties declared in the already assessed safety documentation for further period.
13 Accident Report If a cask defect or an accident, especially drop or turning over occurs when handling -KODA VPVR/M cask with identification CZ/048/B(U)F-96, filled with VJP or empty, SÚJB shall be immediately informed about this event. At the same time, a report about the event shall be prepared and sent by the permit holder to the State Office for Nuclear Safety within 14 days of the accident occurrence according to Section 9 (1m) of Act No. 18/1997 Coll. Such a cask will be put out of operation temporarily, without unnecessary delay and while meeting all the nuclear safety and radiation protection requirements. The conditions for re-use of the cask shall be decided by SÚJB on the basis of a justifie d proposal submitted by the permit holder according to Section 9 (1m) of Act No. 18/1997 Coll. and after meeting all the nuclear safety and radiation protection requirements.
14 Resolution Validity a) The Resolution on cask type approval does not supersede any other permits issued by the State Office for Nuclear Safety as per Section 9(1) of Act No. 18/1997 Coll. and/or permits or authorizations for activities issued by other administration bodies as per special regulations.
b) The Resolution on cask type approval does not relieve the carrier of its obligation to meet the requirements of other transport-competent bodies and of the obligation to meet any requirements of any country into or through which the cask loaded with radioactive substances will be transported.
The validity of this Resolution expires on 31 July 2027.
Rationale:
SÚJB commenced administrative procedure with the pa rty to the procedure in the matter of the cask type approval based on application No. JS-OBCH/464/16 of 19 December 2016 submitted by the party to the procedure which was received by SUJB on 21 December 2016.
Since the administrative procedure in the above matter was commenced under Act. No.
18/1997 Coll. and was not completed before the entry into force of Act No. 263/2016 Coll.
the Atomic Act, the State Office for Nuclear Safety in this matter, in accordance with the provision of Section 232 (6) of Act No. 263/2016 Coll., the Atomic Act, completed the administrative procedure and assessed the rights and obligations related to it according to the existing legislation.
Resolution ref. No. SÚJB/ONRV/12586/2017 9/10
The Resolution is being issued after examining the submitted documentation that was submitted to the State Office for Nuclear Safety in accordance with the provision of § 23 of Act 18/1997 Coll. and according to § 3 and § 4 of Regulation No. 317/2002 Coll., on type approval and transport.
The party to the procedure filed the application for a repeated issue of the Resolution on type approval of VPVR/M cask which was issued by SÚJB several times, and lastly under File No.
SÚJB/ONRV/5637/2011 of 14 March 2011, valid until 31 October 2016, due to the expiry of the above cited SÚJB Resolution.
The application was in compliance with the above cited provisions of the legislation supported by the below documentation for the repeated type approval of -KODA VPVR/M cask:
A certified copy of the excerpt from the Commercial Register for -KODA JS a.s. of 5 October 2016; Safety Report - Repeated issue of the Resolution on -KODA VPVR/M cask type approval, Ae 16782/Dok Rev. 0, -KODA JS a.s., of 13 December 2016; Technical Report - -KODA VPVR/M Cask, Events, their Evaluation and Inspections Carried out in the Years 2011 - 2016, Ae 16938/Dok Rev. 0, -KODA JS a.s., of 15 December 2016; Inspection and Service Plan of -KODA VPVR/M and Transfer Casks, Working Procedure file No. PP 2404 191, Rev. 0, ÚJV ez, a.s., valid since 31 March 2015; Utilization of -KODA VPVR/M Cask Package System supplied by -KODA JS a.s. to IAEA (US DOE) and ÚJV ez, a.s., Czech Republic.
The State Office for Nuclear Safety also took into consideration that the previous applications of the party to the procedure, based on which the Resolutions on VPVR/M cask type approval were issued, contained in the Supplements the Safety Documentation satisfying all requirements according to relevant provisions of Act No. 18/1997 and Regulation No.
317/2002 Coll., on type approval and transport.
The State Office for Nuclear Safety states that the submitted safety documentation meets the relevant provisions of Act No. 18/1997 Coll. and the relevant provisions of Regulation No.
317/2002 Coll., on type approval and transport, and proves the suitability of -KODA VPVR/M cask for its use for transport of radioactive content referred to in condition 1 and for storage of radioactive content referred to in condition 2 and in accordance with the other conditions of this Resolution.
The administration fee of CZK 1 000,- was paid as per Clause 107 (f) of the Supplement to Act No. 634/2004 Coll., on administration fees.
For the above reasons, SÚJB has decided as provided in the Resolution statement.
Advice:
This Resolution can be appealed to the Chair of SÚJB through SÚJB, the Nuclear Safety Section, Senovázné námstí 9, 110 00 Prague 1, within 15 days of the delivery of this Resolution.
For the State Office for Nuclear Safety
RNDr. Peter Lietava RAW and Spent Nuclear Fuel Management Division Manager Resolution ref. No. SÚJB/ONRV/12586/2017 10/10
Distribution list:
Party to the procedure
-KODA JS a. s.
Orlík 266/15 316 00 Plze - Bolevec
File