ML19329A573
| ML19329A573 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/18/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001070570 | |
| Download: ML19329A573 (2) | |
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g December 18, 1970 Files DUKE POWER CfMPAW REQUEST FOR WIT 11 HOLDING OF INFORMATION (DOCKET NOC50-263 50-270, and 50-287)
Duke Power Company has referenced or incorporated the following documents in support of its application for operating licenses The documents for the Oconee Nuclear Station Units 1, 2, and 3.
and relate to once-through steam generator research, development, internals vent. valve evaluation program and test results:
testing:
fuel assembly stress and deflection analysis for loss-of-coolant accident and seismic excitation; effect of fuel rod failure on emergency core coeling effectiveness; reactor vessel model flow tests; computer codes and methods used in performing LOCA analyses; and i
proprietary answer: to AEC questions:
The Babcock & Wilcox Company's Report Nos. BAW-100002:
BAW-100002, Suppl. 1; Rev. 1: BAW-10008 Part 2, Rev. 1; BAW-100009; BAW-10012; BAW-10023.
Duke Power Company's icplication Amendment No.14 dated July 9, 1970.
Duke Power Company has requested that the information contained in the above documents be withheld from public disclosure pursuant to Section 2.790 of 10 CFR Part 2.
The company also stated that release of the information would be detrimental to the Babcock and Wilcox Company and to Duke Power Company.
Our Staff review of the information contained in the documents reveals that:
(1) The FSAR and amendments thereto for the Oconee Nucle.2r Station provide sufficient information to enable an interested member of the public to identify the significant design features of
- Further, the plant and the associated safety considerations.
with respect to the proprietary information on the steam genera-tor contained in BAW-10002 and BAW-10002, Supplement 1, the FSAR and amen 6ments thereto contain nonproprietary information
. on the steam generators, and the DRL Safety Evaluation adequately describes the general nature of the tests performed and the data evaluation program results without revealing proprietary Access to these documents by the general public information.
thus provides interested individuals with n suf ficient col-Icetion of inforwation ou B&W's new design of a once-through
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o-Files I (2) The decisments which the Duke Power Company has requested to i
be withheld from public disclosure provide information on i
once-through steam generator develtepsent and testing, a proto-type internals vent valve for use on PWR plants designed by B&W, fuel assembly stress and deflection analysis tests run to evaluate potential fuel rod cladding failure mechanisms and their effect on emergency cora cooling effectiveness, a sisesary of development and testing relative to the hydraulic characteristics of a typical Babcock & Wilcox reactor vessel and internals, computer codes and methods used in performing LOCA analyses, fuel element positions and burn up, the hybrid analog-digital computer program used for certain analysis calculations, amplified information on the supports for the reactor vessel, pressuriser, steam generator. and pump and motor components of the facilities.
t in view of the foregoing, I have determined that disclosure of the infor-mation contained in the above doctssente is not required in the public interest nor by 10 CFR Part 9, and they should, therefore, be withheld from public inspection pursuant to 2.790(b) of 10 CFR Part 2 DISTRIBUTION:
Docket File (3)
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