ML20045D759
| ML20045D759 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/24/1993 |
| From: | Mellor R YANKEE ATOMIC ELECTRIC CO. |
| To: | Fairtile M NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| BYR-93-047, BYR-93-47, NUDOCS 9306300029 | |
| Download: ML20045D759 (2) | |
Text
' YANKEE ATOMIC ELECTRIC COMPANY
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0 580 Main Street, Bolton, Massachusetts 01740-1398 AN KEEy June 24,1993 l
BYR 93-047 1
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Mr. Morton Fairtile Senior Project Manger Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support
References:
(a)
License No. DPR-3 (Docket No. 50-29)
(b)
Letter, J. Thayer, Yankee Atomic Electric Cornpany, to M. Fairtile, Nuclear Regulatory Commission, dated June 17,1993
Subject:
ACTIVITIES PRIOR TO DECOMMISSIONING PLAN APPROVAL -
REQUEST FOR ADDITIONAL INFORMATION i
i
Dear Mr. Fairtile:
During a telephone conversation on June 23, 1993, the Nuclear Regulatorf Commission (NRC) requested clarification on Yankee Atomic Electric Company's response in Reference l
(b), concerning how Yankee Atomic Electric Company (YAEC) plans to address seismic hazards during plant modifications in the permanently defueled condition. Specifically, the NRC asked whether YAEC would ensure that remaining systems. structures and l
components, that may have been affected by removal activities, will be adequately supported l
to prevent an uncontrolled release of contamination or exposure to radiation following a seismic event.
Clarification Following removal of the steam generators, pressurizer and reactor vesselinternals, the total radioactivity remaining in the containment, excluding the activated metal of the reactor-l vessel and neutron shield tank, has been estimated to be less than 130 curies. This activity l
is in the form of activated corrosion products deposited on the interior surfaces of piping and system components. Approximately 25% of this inventory would have to be released -
to the environment to exceed the current licensing basis dose limits. It is unlikely that such a release could occur as a result of a design basis seismic event. Furthermore, there is a very limited number of components whose seismic features (as they existed during power 0
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U.S. Nuclear Regulatory Commission June 24,1993 Page 2 of 2 operations) will be affected by the current component removal activities. However, YAEC will ensure that components affected by any removal activities or other plant modifications, will be evaluated and supported, as appropriate,if failure following a design basis seismic event could result in a significant, uncontrolled release of contamination or exposure to radiation.
Sincerely, YANKEE ATOMIC ELECTRIC COMPANY xg r
Russell A. Mellor Yankee Project Manager pke c: R. Dudley, NRC, NRR E. Kelly, NRC Region I
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