ML20203Q141
| ML20203Q141 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/29/1986 |
| From: | Harpster T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8605090047 | |
| Download: ML20203Q141 (4) | |
Text
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e APR 2 91985 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN: Mr. Roger W. Kober Vice President Electric and Steam Production 49 East Avenue Rochester, New York 14649 Gentlemen:
In order for the Region to fully support the R. E. Ginna emergency exercise scheduled for September 10, 1986, an adequate review of the exercise objectives and scenario is essential. The guidelines identified below will be used for the submittal and review of the objectives and scenario packages prior to the exercise.
You will note that the schedule is similar to the least restrictive submittal schedule noted in FEMA Guidance Memorandum No.17, Revision 1, for comparable milestones.
Region I has found that licensees generally comply with these guidelines, however, we recognize the need to stress the importance of both completeness and tineliness.
The following schedule should be used for all exercises:
Days in Advance Information to be Submitted J
75 Days Description and scope of exercise, and the objectives to be fulfilled should be received in the Region I office. The objectives should include specific objectives to demonstrate, where appropriate, the effectiveness of corrective actions taken in regard to problem areas which have been previously identified during NRC inspections, emergency exercises and drills and your internal evaluation process.
60 Days NRC will provide comments in writing, based on our review of your submittal.
45 Days Complete exercise scenario package with modified objectives, schedules, exercise rules, all controller, contingency and simulation informa-tion, all data, including plant data, radiation level and release rate data, and samples of the data to be presented should be received in the Region I office, kf DON F
0FFICIAL RECORD COPY g g 3(
Rochester Gas and Electric 2
Corporation 30 Days NRC will provide comments in writing, based on our (and our contractor's) review of your submittal.
In order to protect the scenario from disclosure to participants, please send two copies to the Chief. Emergency Preparedness Section at the Letterhead address, marked, " EMERGENCY EXERCISE SCENARIO /0BJECTIVES."
In addition, please send two copies directly to Battelle Pacific Northwest Laboratory, Technical Leader, Emergency Preparedness Group. Health Physics Department, 2125 George Washington Way, Richland, WA 99352, in order to expedite the review process.
If you anticipate that the deadline will not be met, we reconnend you use overnight mail.
The NRC emergency preparedness specialist responsible for evaluation of your exercise is Walter Thomas.
Please identify the name, address and phone number of the individual on your staff with whom we should interface.
Your continued cooperation in this matter is greatly appreciated.
If you have any concerns or questions, please contact Mr. Thomas at 215-337-5043.
Sincerely, Orinir.31 Si"M !?T b
'h W 9>
T L.
pster, Chief Emergency Preparedness Section Division of Radiation Safety and Safeguards CC:
Harry H. Voigt, Esquire Central Records (4 copies)
Director, Power Division R. Kowieski, FEMA RII D. Burke, Corporate Emergency Planner Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York 0FFICIAL RECORD COPY i
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Rochester Gas and Electric 3
Corporation bec:
Region I Docket Room (with concurrences)
DRP Section Chief W. Thomas W. Lazarus P. Gaul RI:DRSS RI:DRSS RI:DP RI:DRS$7 Gaul
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Lazarus g Haroster 4/
6 4/29/85 4/29/85 4/ I'/85 0FFICIAL RECORD COPY O
i BASIC COMPONENT When applied to nuclear power plants " Basic Component" means a plant structure, system, component, or part thereof necessary to assure the following.
The integrity of the reactor coolant pressure boundary, or The capability to shutdown the reacter and maintain it 'in a safe shutdown condition, or The capability to prevent or mitigate the consequences of accidents which could result in potential offsite release of radioactivity in excess of 10 CFR 100 limits In all cases, " Basic Component" includes design, inspection, testing or consult-ing services important to safety that are associated with the component hardware.
This definition is the :ame as or synonymous with that of safety-related items in 10 CFR 100 and other 10 CFR sections.
COMMERCIAL GRADE The term " Commercial Grade" item means a component or part thereof to which all of the following apply.
Not subject to design or specification requirements that are unique to facilities or activities licensed by the NRC, and Used in applications other than facilities or activities licensed by the NRC, and To be ordered from the manufacturer / supplier on the basis of specifications set forth in the manufacturer's published pr,oduct description, such as in a catalogue.
OEDICATION A " Commercial Grade" item is not part of a " Basic Component" for the purpose of 10 CFR 21 until after " Dedication". Also, the appropriate quality assurance, seismic, and environmental qualifications still apply if the equipment or parts will be required to perform any safety-related function. To ensure that such equipment and parts will be capable of performing their safety related function when called upon to do so, this dedication process must include the following.
Classification as safety-related Assure the capability and reliability of the item to perform its intended safety function Ability to perform under plant environmental and seismic conditions 10 CFR 21 and 10 CFR 50, Appendix 8, QA Program requirements The QA Program in place must be sufficient to ensure reliability of the dedication process.