ML16294A251

From kanterella
Jump to navigation Jump to search
Document Transmittal Regarding Issue MNS TS 4.0 Rev. 1 Amend 288/267
ML16294A251
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/12/2016
From:
Duke Energy Corp
To:
Office of Nuclear Reactor Regulation
References
Download: ML16294A251 (3)


Text

Date: 10l12l201§ Disbibution: Duke Energy Dorument Transmittal #: TR-NUC-MC-004302

1. Boyer, Robert P
2. Carroll, Michael E DOCUMENT TRANSMITTAL FORM

Purpose:

~

Released By:

3. Gardner, Troy R Facility: MCG!.!IRE NUCLEAR STATION Dl!kg Engi::gy:
4. Mc Ginnis, Vickie L SUBJECT 13225 HDgg!:l! Egrry: RoDd
5. OPS HUMAN PERFORMANCE -

Issu~ MNS TS 4.0 Rev. 1 Amend, 288[267 Dogiment Management

6. OPS TRNG MGR.

MG02DM

7. QATS-Huntersville, NC 28Q78
8. RESIDENT NRC INSPECT MNSDCRM@duke-enei::gy.com
9. _SERV BLDG FILE ROOM -
10. U S NUC REG WASHINGTON, DC
11. USNRC
12. WESTINGHOUSE ELECTRIC CO LLC Page 1of1
.\:',.

.:*: >h:*:.:~*~ .:f, -- s

  • .J.;*!* **~'*:" ..* " " :;:/';;\:U*+Docu"inentl:D ?~{,;- -- -- '*' *~

1 2 3 4 6 7 8 9 10 11 12 utNL ;Mc:~:t.1Ns,,TS4:1.~.2;4,3 ?001;:~ -tssi.JE_o < >-_*!'('2'3;; FYIIE FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&A(E R&A(E R&AIE Remarks: B,gmQvg[Renla~ RDQeli ~.0-1 II. 4.0-2

(

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The McGuire Nuclear Station site is located at latitude 35 degrees, 25 minutes, 59 seconds north and longitude 80 degrees, 56 minutes, 55 seconds west. The Universal Transverse Mercator Grid Coordinates are E 504, 669, 256, and N 3, 920, 870, 471.

The site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of either Zircalloy, ZIRLO, or Optimized ZIRLO' clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. Limited substitutions of ZIRLO, Optimized ZIRLO', zirconium alloy or stainless steel filler 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 fuel 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 53 control rod assemblies. The control material shall be silver indium cadmium (Unit 1) silver indium cadmium and boron carbide (Unit 2) 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 nominal U-235 enrichment of 5.00 weight percent;
b. kett < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
c. kett ~ 0.95 if fully flooded with water borated to 800 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; McGuire Units 1 and 2 4.0-1 Amendment Nos. 288/267

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

d. A nominal 10.4 inch center to center distance between fuel assemblies placed in Region 1 and
e. A nominal 9.125 inch center to center distance between fuel assemblies placed in Region 2.
f. Neutron absorber (Baral) installed between fuel assemblies in the Region 1 racks.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fyel assemblies having a maximum nominal U-235 enrichment of 5.00 weight percent,
b. kett :::;; .0.95 if fully flooded with unborated water, which includes
  • an allowance for uncertainties as described in Section 9.1 of the UFSAR;*
c. kett:::;; 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and
d. A nominal 21 inch center to center distance between fuel assemblies placed in the 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 elevation 745 ft.-7 in.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1463 fuel assemblies (286 total spaces in Region 1 and 1177 total spaces in Region 2) .

  • McGuire Units 1 and 2 4.0-2

)

Amendment Nos. 225 I 207