ML19208B220
| ML19208B220 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 08/23/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19208B221 | List: |
| References | |
| NUDOCS 7909190363 | |
| Download: ML19208B220 (2) | |
Text
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gjG 2 31979 MEMORANDUM FOR:
R. Reid, Chief, Operating Reactors Branch #4, D0R FROM:
G.' Lainas, Chief, Plant Systems Branch, D0R
SUBJECT:
REVIEW 0F ARKANSAS NUCLEAR ONE, UNIT 1 ECCS ELECTRICAL, INSTRUMENTATION AND CONTROL (TAC 6161)
Plant Name: Arkansas Nuclear One, Unit 1 (ANO-1)
Docket No.:
50-313 Responsible Branch: ORB #4 Project Manager:
G. Vissing Reviewing Branch: Plant Systems Branch Status:
Incomplete The Arkansas Power and Light Company, pursuant to the Comission's order for modification of license dated December 27, 1974; submitted in its letter of July 9,1975 a reevaluation of ECCS Cooling Per'ormance that conforms with the requirements of Appendix K 10 CFR Part 50.
Additional information, at the request of the staff,-necessary to permit completion of an evaluation of the electrical and instrumentation sub-systems of the emergency core cooling system (ECCS) was submitted in the licensee's letters listed in the reference section of the attached Safety Evaluation.
The attached evaluation does not address the subjects of emergency ventilation in vital equipment areas and of degraded voltage, or the issues which have grown out of the Three Mile Island accident. These issues will be addressed by the staff in separate safety evaluations.
We have completed our review of the documentation submitted and find exclusive of the "open" issue of radiation exposure in environmental qualifications that the electrical and in-* rumentation subsystems of the emergency core cooling system as modir'ied satisfy the single failure criterion; and, therefore, are acceptable. The basis for
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- this determination is presented in our evaluation enclosed. The resolution of the "open" issue will be reported in a supplement to the attached Safety Evaluation.
M G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Enclosure:
As stated
Contact:
J. Burdoin X-28077 cc w/ enclosure:
D. Eisenhut W. Russell B. Grimes W. Gammill P. Check M. Mendonca G. Vissing G. Lainas D. Tondi J. Burdoin
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