ML25196A102
| ML25196A102 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/16/1978 |
| From: | Lawroski S Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC/Chairman |
| References | |
| Download: ML25196A102 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 Honorable Joseph M. Hendrie Chairman
- u. s. Nuclear Regulatory Corrmission Washington, D.C.
20555 Februaiy 16, 1978
Subject:
REPORT ON EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2
Dear Dr. Hendrie:
During its 214th meeting, February 9-11, 1978, the Advisory Committee on Reactor Safeguards completed its review of the application of the Georgia Power Company, Oglethorpe Electric Membership Corporation, Municipal Elec-tric Authority of Georgia and the city of Dalton, Georgia (the Applicants) for a license to operate the Edwin I. Hatch Nuclear Plant, Unit No. 2. The plant will be operated by Georgia Power Company.
The application was re-viewed at Subconmittee meetings on January 27 and 28, 1978 in Washington, D.C. During its review, the Comnittee had the benefit of discussions with representatives and consultants of the Nuclear Regulatory Commission (NRC)
Staff; General Electric Company; Southern Company Services, Incorporated; Bechtel Power Corporation; and the Applicants. The Committee also had the benefit of the documents listed.
The Edwin I. Hatch Nuclear Plant is a two-unit station located on the south bank of the Altamaha River approximately 11 miles north of Baxley, Georgia. The two units are virtually identical except that Hatch Unit No. 1 utilizes 7X7 fuel assemblies while Hatch Unit No. 2 will utilize 8X8R (Retrofit) fuel assemblies. The rated thermal power for each unit is 2436 MW(t).
Each unit includes a General Electric Company BWR/4 boiling water reactor. The Comnittee reported on the application for a construc-tion permit for Unit No. 2 on November 3, 1971.
Hatch Unit No. 2 is the first reactor scheduled to use the new General Elec-tric 8X8R fuel on a core-wide basis. This fuel design is a slightly rrod-ified version of the General Electric 8X8 fuel assembly design currently in use in a nu.mber of boiling water reactors. These rrodifications in-clude, among others, an increase in fuel length, use of natural uranium at the top and bottom of the fuel rod and the addition of a second water rod to each fuel assembly. These changes improve the shutdown and ther-mal margins, provide flatter local power distribution, and improve fuel cycle efficiency. Four of the 8X8R fuel asserolies have been operating in Peach Bottom Unit No. 2 since May 1976 and two assemblies have been 743
Honorable Joseph Februa-cy 16, 1978 operating in Venoont Yankee since August 1976. The NRC Staff has concluded that the 8x8R fuel assembly design is acceptable for use in Hatch Unit No. 2.
The Comnittee concurs.
The NRC Staff has identified a number of safety-related items which will require resolution prior to a decision on the issuance of an operating li-cense. These matters should be resolved in a manner satisfactory to the NOC Staff.
With regard to the generic problems listed in the Committee's report, "Status of Generic Items Relating to Light-Water Reactors - Report No. 6,"
dated November 15, 1977, items considered relevant to Edwin I. Hatch Nu-clear Plant, Unit No. 2 are: II-1, 4, SA, SB, 6, 7, 8, 10; IIA-4; IIB-2, 41 IIC-1, 3A, 3B, 5, 6, 7; IID-2. These problems should be dealt with by the NRC Staff and the Applicants as solutions are found.
The Advisory Comnittee on Reactor Safeguards believes that if due consid-eration is given to the items mentioned above, and subject to satisfactory completion of construction and preoperational testing, there is reasonable assurance that the Edwin I. Hatch Nuclear Plant, Unit No. 2 can be oper-ated at power levels up to 2436 MW(t) without undue risk to the health am safety of the public.
References
+~
Stephen Lawroski Chairman
- 1. Edwin I. Hatch Nuclear Plant, Unit No. 2, Final Safety Analysis Report, with.Ai-nendments 18 through 41.
- 2. Report to the Advisory Conmittee on Reactor Safeguards by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comnission in the matter of Georgia Power Company, et al, Edwin I. Hatch Nuclear Plant, Unit No. 2, dated January 4, 1978.
- 3. General Electric Company, "Lattice Physics Methods," NEDE-20913A, January, 1977.
- 4. General Electric Company, "Lattice Physics Methods Verification,"
NEIX>--20939A, January, 1977.
- 5. General Electric Company, "BWR Simulator Methods Verification,"
NE00-20946A, J-anuary, 1977.
- 6. General Electric Company, "Three-Dimensional BWR Core Simulator,"
NE00-20953A, January, 1977.
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Honorable Joseph Februazy 16, 1978
- 7. General Electric Company, "BWR/6 Fuel Design," NEDE-20948-P, June, 1976, and Amendment No. 1, November, 1976.
- 8. General Electric Company, "BWR/4 and BWR/5 Fuel Design," NEDE-20944-P, September, 1976.
- 9. General Electric Company, "BWR Fuel Channel Mechanical Design and Deflection," NEDE-21354-P, September, 1976.
- 10. General Electric Company, "BWR/6 Fuel Assembly:
Evaluation of Com-bined Safe Shutdown Earthquake (SSE) and Loss-of-Coolant Accident (I.OCA) LOadings," NEDE-21175-P, November, 1976 and Amendment 1, April, 1977.
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