ML20092F087
| ML20092F087 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/11/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092F090 | List: |
| References | |
| NUDOCS 9202190079 | |
| Download: ML20092F087 (4) | |
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7590-01 pjilT10 STATES NVCLEAR REGULATORY COMMISSION ENTERGY OPERATIONS. INC.
GBAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-116 ENVIRONMENTAL ASSESjLMINT AND FINDING OF NO SIGNIFICANT IMPACT The V. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from the requirements of-Appendix J to 10 CFR Part 50 in response to a request by Entergy Operations, Inc., for the Grand Gulf Nuclear Station, Unit 1, located in Clairborne County, Mississippi.
ENVIRONMERIA_l, ASSESSMENT idt011f i c a l i trLaf_p r.0p o s e d A c t i o n The proposed action would grant an exemption from a requirement of Section Ill.D.l(a) of Appendix J to 10 CFR Part 50 that the third test in each set of three tests intended to measure the primary reactor containment overall integrated leakage rate (Type A tests) shall be conducted when the plant is shutdown for the 10-year plant inservice inspections (Isis).
The preposed action is in accordance with the licensee's request for exemption dated June 25, 1991.
The N.ted for the Pron _qsed Actioh I
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The proposed exemption is needed because the present requirement would force the licensee, at a significant cost but without any significant increase in public health and safety, to perform an additional integrated leak rate test (ILRT) during the forthcoming outage, currently scheduled to start in April 1992.
9202190079 920211 DR_ ADOCK 0500 6
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Environmental Impacts of the Pronosed Action The croposed exemption would not affect the integrity of the plant's primary containment with respect to potential radiological releases to the environment in the event of a severe transient or an accident up to and including the design basis accident (DBA).
Under the assumed conditions of the DBA, the licensee must demonstrate that the calculated offsite radiological doses at the plant's exclusion boundary and low population zone outer boundary meet the guidelines-in 10 CFR Part 100.
Part of the licensee's demonstration is accomplished by the periodic ILRTs conducted about every 40 months to verify that the primary containment leakage rate is equal to or less than the design basis leakage rate used in its calculations demonstrating compliance with the guidelines in 10 CFR Part 100.
The licensee has successfully conducted a number of these ILRTs to date.
The most recent ILRT was completed in April 1989, during the third refueling outage, and was the second of the required Type A tests.
The next 1LRT will most probably be conducted in October 1993.
The 10-year 151 is scheduled to start during Refueling Outage 7, presently scheduled to start in April 1995.
As required by 10 CFR 50.55a, this schedule for the 10-year 151 is in compliance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda.
The proposed exemption request to decouple the schedule of the third Type A test (i.e., an ILRT) from that of the 10-year 151 will not in any way compromise the leak-tight integrity of the primary containment required by Appendix J to 10 CFR Part 50 since the leak-tightness of the containment will continue to be demonstrated by the periodic ILRTs, Additionally, the proposed
3 exemption will not affect the existing requirement in Section !!!.D.),(a) of Appendix J that three ILRis be performed during each 10-year service period.
Further, the proposed uncoupling does not affect the structural integrity of the structures, systems, and components subject to the requirements of 10 CFR 50.55a.
Accordingly, there will be no increase in either the probability or the amount of radiological release from the Grand Gulf plant in the event of a severe transient or accident.
Therefore, the Commission concludes that there are nc significant radiological environmental impacts associated with the proposed exemption.
With regard to potential nonradiological impacts, the proposed exemption involves a change to surveillance and testing requirements, it does not affect nonradiological plant effluents and has no other environmental impact.
Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption, 61ternativ.t 19 the proposed Action Since the Commission concluded that there are no significant environmental impacts associated with the proposed action, any alternatives have either no or greater environmental impact.
The principal alternative would be to deny the requested exemption.
Denial would not reduce the environmental impacts attributed to the facility but would result in the expenditure of resources and increase radiation exposures witnout any compensating benefit.
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4 6111rhtiitt_VILpf Rnnurces This action does not involve the use of any resources not previously considered in the final Environmental Statement for the Grand Gulf Nuclear Station, Unit 1, dated September 1981.
692M.itLand__P_enpn.L(gniyittd The NRC staff reviewed the licensee's request and did not consult any other agencies or persons.
flND]BG Of t!QJLGtilr]C ANT _]t1 PACT The Commission has determined not to prepare an environmental impact statement for the proposed exemption.
Based on the foregoing environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the request for exemption dated June 25, 1991, which is available for public inspection at the Commission's Public Document Room, 2120 L Street, N.W., Washington, D.C.
Dated at Rockville, Maryland, this lith day of February,1992.
FOR THE NUCLEAR REGULATORY COMMISS10N
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John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects - lil/IV/V Dffice of Nuclear Reactor Regulation l
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