ML19332A229
| ML19332A229 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/09/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19332A228 | List: |
| References | |
| 50-454-80-12, 50-455-80-11, NUDOCS 8009110313 | |
| Download: ML19332A229 (2) | |
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Appendix A NOTICE OF VIOLATION
.' Commonwealth Edison Company Docket No. 50-454 Docket No. 50-455 Based on the inspection conducted on June 17, 18, and 19, 1980, it appears that one of your activities was in noncompliance with NRC requirements, as noted below. This item is an infraction, and is applicable to both Units 1 and 2.
10 CFR 50, Appendix B, Criterion III, states, in part, that " Measures shall be established to assure that applicable... design basis...for those structures, systems, and components...are correctly translated into specifications, drawings, procedures, and instructions."
Commonwealth Edison Company Topical Report CE-1-A, " Quality Assurance Program for Nuclear Generating ~ Stations", Revision 9, dated July 16, 1979, states in Paragraph 3.1 that "The fundamental vehicle for design control involves multi-level review and/or evaluation of design documents by individuals or groups other than the original designer or designer's immediate supervisor whose authority and responsibility are identified and controlled by written procedures.
The design documents include, but are not limited to, design and construction specifications, equipment specifications, and process drawings. Review of and evaluation by the Architect Engineer will assure that designs and materials will conform to the ASME Code and other applicable codes, standards, regulatory requirements, SAR commitments, and appropriate qualf.ty Standards as applicable.
10 CFR 50, Appendix A, Criterion IV, states " Structures, systems, and components important to safety shall be designed to accommodate the effects of and be compat-ible with environmental conditions associated with norm <1 operation, maintenance, testing, and postulated accidents, and loss-of-coolant accidents. These structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids that may result from equipment failures and from events and conditions outside the nuclear power plant."
10 CFR 50, Appendix A, Criterion V, states " Structures, systems and components important to safety shall not be shared among nuclear power units unless it can l
be shown that such sharing will noc significantly impair their ability to perform I
their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units".
Contrary to the above, it was determined that CECO did not ensure that Sargent l
and Lundy adequately translated the requirements in 10 CFR 50, Appendix A, Criterion IV and V, in the design of the cooling water supply to the Emergency Diesel Generator 1A in the following instances:
8 0 0 91103l3' 1
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O Appendix A 1.
A common header is installed in the room housing Emergency Diesel Generator IB to supply the cooling water to Diesel Generators IA and IB.
jl The "to" and " return" cooling water lines to Diesel Generator IA pass through the room housing Unit IB.
In the event of an accident in Unit IB emergency diesel generator room, both Emergency Diesel. Generators IA and IB could become inoperable due to loss of cooling water.
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