ML20040C522
| ML20040C522 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, 07002950  |
| Issue date: | 01/08/1982 |
| From: | Ketzlach N NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Andognini G ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8201280087 | |
| Download: ML20040C522 (5) | |
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, b Arizona Public Service Company ATTU: Mr. G.C. Andognini CJA/ DITTO \\'g' ggg Vice President, Electric Operati LTyson HJMcGurren P.O. Box 21666 WTCrow Region V Phoenix, Arizona 85036 RGPage GFiorella, Res IE DKasun Service List Gentlemen:
JDKerrigan lle have completed the initial review of the Arizona Public Service Company application dated August 17, 1981, for authorization to receive, store, inspect and transport special nuclear material and excore and incore detectors.
We find that additional infomation is needed (see enclosure) to complete our evaluation.
In order to neet your scheduled delivery date for fuel, your responses to the comments are due no later than February 12, 1982.
If there are any questions concerning this matter, please call me at (301) 427-4510.
Sincerely,
Origfnal Signed by N.Kctninch Norman Ketzlach e
Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, N!!SS Encl osure: Connents on Arizona Public Service Company License Application for Fuel Storage Only for the Palo Verde Nuclear Generating Station, Unit 1 (Dated 8/17/81) e2012eooe7 e2otos PDR ADOCK 0500o52e A
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COMMENTS ON ARIZONA PUBLIC SERVICE COMPANY LICENSE APPLICATION FOR FUEL STORAGE ONLY FOR THE PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 (DATED AUGUST 17,1981) 1.
Page 19, Section 1.1.2 Describe the fuel-assemblies in sufficient detail so that a nuclear criticality safety evaluation of the fuel handling and storage may be made (e.g., number and location of fuel rods and number of void positions / fuel assembly).
2.
Page 19, Section 1.1_.3 j
235 Specify the maximum U enrichment in a fuel assembly (only the
" nominal" enrichment is stated).
3.
Page 20-21, Section 1.2.1 Describe the shipping container laydown array when the fuel a.
assemblies are only in their inner container and in both their inner and outer containers and the maximum size of the array (total number of containers, number of containers in a stack).
b.
Provida the basis for the nuclear criticality safety of the laydom arrays, c.
Describe the maximum number of fuel assemblies in the inspection area (e.g., maximum number of assemblies at an inspection station, minimum edge-to-edge distance between individual assemblies and between the inspection area and the fuel storage area).
d.
Specify the minimum center-to-center spacing between fuel assemblies in the new fuel storage racks and between fuel assembly storage locations in the spent fuel pool racks.
e.
Correct the identification of the figure for the locations of the new fuel storage areas.
Describe the blocking devices used to assure the fuel assdmblies' f.
are stored in a checkerboard pattern in the spent fuel storage racks.
Confinm they are always in their specified locations in the racks when used to store unirradiated fuel assemblies.
4.
Page 21, Section 1.2.2 Confinn no construction activities will be performed in the fuel -handling j
areas during fuel har.dling operations.
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. 5 Page 21, Section 1.2.3 Specify whether plastic sheeting is to be wrapped around the assemblies a.
during ctorage.
If so, confirm the sheeting is open at the bottom so that water would drain freely from the assemblies in the event of flooding and subsequent draining of the storage area.
b.
Specify whether neutron poisons are used to ensure the nuclear criticality safety of the spent fuel pool storage array.
If so, specify the quality assurance program to confirm the poisons meet specifications and are properly installed in their design locations.
Specify the requirements for periodically testing their continued presence in the design locations.
6.
Page 25, Section 2.1.1 Specify the training requirements for personnel who may be in areas where a.
radioactive materials are handled and/or stored.
b.
Identify the position responsible for all aspects of radiation safety at the Palo Verde Nuclear Station.
Confirm he is responsibic to see that receiving, handling and storing of radioactive materials are in accordance with approved and documented procedures.
7.
Page 25, Section 2.1.2 Confinn the monitoring program includes all operations involving radioactive a.
materials, including routine surveys of fuel storage areas.
b.
Coafirm a commitment to Section 12.5.2 (Radiation Protection Procedures) of the referenced FSAR for the Part 70 license.
8.
Page 25, Section 2.1.3 State the minimum frequency and methods for calibration and testing of portable radiation survey instrumentation and laboratory radiation instrumentation.
9.
Page 25, Section 2.2.1 a.
Confirm the array in the Fuel Building ~ Shipping Container Laydown Area is no larger than that in a single shipment or specify the criteria for larger storage arrays.
If larger arrays are to be used, provide justification for the larger storage arrays.
b.
Identify the shipping container used (e.g., NRC Certificate of Compliance No.) and specify tne number of fuel assemblies per container.
. 10. Page 25-26, Section 2.2.2 Provide the results of the nuclear criticality safety analysis for the fuel assembly arrays in both the new fuel and the spent fuel pool storage areas.
- 11. Page 26, Section 2.2.3 Provide a demonstration that shows the effect of all degrees of moderation on the k of the arrays.
Describe the method (s) of analysis used and their vaif$ation.
- 12. Page 26, Section 2.2.4 Specify the maximum number of fuel assemblies outside the authorized a.
storage locations at any time.
If more than a single assembly is at a particular location, provide justification.
b.
Specify the minimum edge-to-edge spacing between single fuel assemblies or single fuel assemblies and storage arrays.
Provide justification for the distance between single assemblies if less than 36 inches, between single assemblies and fuel storage arrays or between array types if less than 12 feet.
- 13. Page 27, Section 2.2.5 Confirm you request an exemption from the pravisions of 10 CFR 70.24 in accordance with 10 CFR 70.24(d).
- 14. Page 27, Section 2.3 Confirm no load heavier than a fuel assembly will be moved over the fuel assembly racks when containing assemblies, the racks will withstand accidential drops by heavier loads without compromising nuclear criticality safety, or describe the conditions under which the crane interlock override and administrative controls are used to allow heavier loads to be moved over the racks without compromising nuclear safety of the storage array.
- 15. Pages 28-29, Section 3.2.1 a.
Identify the location for the storage of the Pu-Be startup sources.
Provide the security controls to assure unauthorized personnel cannot handle the sources and no one can be. exposed to the source outside their shielded shipping container.
b.
Confirm the s'torage area is a controlled area and is identified as a radiation area.
- c. ' Provide the radiation protection controls to be exercised upon receipt of the sources, during their storage and after the installation of a support clamp at the upper end of the Pu-Be source body.
.... d.
Confirm the Pu-Be source is placed back inside the shipping container after the support clamp is in position or provide the remaining source handling operations and related radiation protection controls.
- 16. Page 29, Section 3.2.2 a.
Confirm both the excore and incore detectors are placed in secured storage when not in use by authorized personnel and chall be used only by or under the supervision of individuals designated by the Manager, Nuclear Operations or the Supervisor, Radiation Protection.
b.
Identify the ANSI standard by title and the date of most recent issue (e.g., ANSI /ASME N45.22-1978).
- 17. Page 31 235 Confirm 3.30%
U is the maximum fuel enrichment (including analytical and sampling errors) to be in the fuel assemblies.
.