ML16299A149
| ML16299A149 | |
| Person / Time | |
|---|---|
| Site: | 05200045 |
| Issue date: | 10/25/2016 |
| From: | GE-Hitachi Nuclear Energy Americas |
| To: | Office of New Reactors |
| Shared Package | |
| ML16299A146 | List: |
| References | |
| MFN 15-065, Suppl 1 | |
| Download: ML16299A149 (4) | |
Text
Enclosure 2 MFN 15-065, Supplement 1 GEH ABWR DCD Draft Revision 7 Markups IMPORTANT NOTICE REGARDING CONTENTS OF THIS DOCUMENT Please Read Carefully The information contained in this document is furnished solely for the purpose(s) stated in the transmittal letter. The only undertakings of GEH with respect to information in this document are contained in the contracts between GEH and its customers or participating utilities, and nothing contained in this document shall be construed as changing that contract. The use of this information by anyone for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
Design Features 4.0 (continued)
ABWR TS 4.0-1 Design Control Document/Tier 2 25A5675AU Revision 6 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries [shall be as described or as shown in Figure 4.1-1].
4.1.2 Low Population Zone (LPZ)
The LPZ [shall be as described or as shown in Figure 4.1-2].
4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 872 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material, and water rods. Limited substitutions of zirconium alloy rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
4.2.2 Control Rod Assemblies The reactor core shall contain 205 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.
4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a.
Fuel assemblies having a maximum k-infinity of 1.35 in the normal reactor core configuration at cold conditions;
- b.
keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the DCD Tier 2.
Design Features 4.0 ABWR TS 4.0-2 Design Control Document/Tier 2 25A5675AU Revision 6 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a.
Fuel assemblies having a maximum k-infinity of 1.35 in the normal reactor core configuration at 20ºC;
- b.
keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the DCD Tier 2;
- c.
keff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the DCD Tier 2; and
- d.
A nominal [approximately 16] cm center to center distance between fuel assemblies placed in storage racks.
4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 3.1 m above the top of the active fuel.
4.3.3 Capacity 4.3.3.1 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no less than 2354 fuel assemblies (270% of full core discharge).
18A-60 Emergency Procedure Guidelines 25A5675AW Revision 6 Design Control Document/Tier 2 ABWR Table 1 Operating Values of Secondary Containment Parameters (Cont.)
ABWR SC-10 Secondary Containment Parameter Maximum Normal Operating Value Maximum Safe Operating Value Area Radiation Level 10-5 Gy/h 10-5 Gy/h El. 18100 T.M.S.L. (Floor 500-2F)
- Main Steam/FW Tunnel 5000
- FPC Area
- Hx Area 5
- Pump Area 5
- Valve Area 5
El. 23500 T.M.S.L. (Floor 600-3F)
- SRV/MSIV Maintenance Room 5
- SLC Area 5
- SGTS Area
- Fan Area 5
- Filter Train Area 5
El. 31700 T.M.S.L. (Floor 800-4F)
- Dryer/Separator Area 5
- Reactor Well Area 5
- Spent Fuel Storage Area 5
- New Fuel Storage Area 5
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