ML052570317

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Song Unit 2, Tech Specification Pages Re Zirlo Clad Fuel
ML052570317
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 09/14/2005
From:
NRC/NRR/DLPM
To:
Donohew J N, NRR/DLPM,415-1307
Shared Package
ml052570759 List:
References
TAC MC4243, FOIA/PA-2014-0204
Download: ML052570317 (2)


Text

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Exclusion Area Boundary The exclusion area boundary shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be as shown in Figure 4.1-2.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 217 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy or ZIRLOIM clad fuel rods.

with an initial composition of natural or slightly enriched uranium dioxide (UOz) as fuel material. Integral or Discrete Burnable Absorber Rods may be used. They may include:

borosilicate glass - Na2O-B 203-SiO 2 components, boron carbide -

B4 C, zirconium boride - ZrB 2, gadolinium oxide - Gd 203, erbium oxide - Er203. Limited substitutions of zirconium alloy (such as ZIRLOPM or Zircaloy) 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 Element Assemblies The reactor core shall contain 83 full length and eight part length control element assemblies (CEAs). The control material shall be silver indium cadmium, boron carbide, and inconel as approved by the NRC.

(continued)

SAN ONOFRE--UNIT 2 4 .0-1 Amendment No.199

- a

.: - -,. I Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"
2. CENPD-137P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model"
3. CEN-356(V)-P-A, "Modified Statistical Combination of Uncertainties"
4. SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"
5. CEN-635(S), "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology"
6. Letter, dated May 16, 1986, G. W. Knighton (NRC) to K.

P. Baskin (SCE), "Issuance of Amendment No. 47 to Facility Operating License NPF-10 and Amendment No. 36 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 3 SER)

7. Letter, dated January 9, 1985, G. W. Knighton (NRC) to K. P. Baskin, "Issuance of Amendment No. 30 to Facility Operating License NPF-10 and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)
8. "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A
c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 Not Used 5.7.1.7 Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

(continued)

SAN ONOFRE--UNIT 2 5.0-27 Amendment No.199