ML25196A088
| ML25196A088 | |
| Person / Time | |
|---|---|
| Issue date: | 01/13/1978 |
| From: | Lawroski S Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC/Chairman |
| References | |
| Download: ML25196A088 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, O. C. 20555 Honorable Joseph M.* Hendrie Chairman January 13, 1978 U. s. Nuclear Regulatory Commission Washington, DC 20555
Subject:
REPORT ON YELLav CREEK NUCLEAR PLANT, UNITS 1 AND 2
Dear Dr. Hendrie:
During its 213th meeting, January 5-7, 1978, the Advisory Committee on Reactor Safeguards corrpleted its review of the application of the Tennessee Valley Authority (the Applicant) for a permit to construct the Yellow Creek Nuclear Plant, Un:i.ts 1 and 2. The application was reviewed at a Subcorrmittee meeting in Corinth, Mississippi on Decem-ber 16, 1977. A tour of the site was made by Subcorrmittee members on December 15, 1977. During its review, the Committee had the benefit of discussions with representatives and consultants of the Applicant, Combustion Engineering Incorporated, and the Nuclear Regulatory Commis-sion (NRC) Staff. The Committee also had the benefit of the documents listed.
The Yellow Creek Plant site is located in Tishomingo County, approxi-mately 15 miles east of Corinth, Mississippi. The minimum exclusion area distance is 695 meters; the low population zone radius is three miles. The nearest population center is the Florence-Muscle Shoals-Sheffield-Tuscurnbia, Alabama corrplex (1970 population of about 62,900) which is located approximately 35 miles east of the site.
The application for the Yellow Creek Plant was sul::mitted in accordance with the Corrmission's standardization policy as described in Appendix 0 to Part 50, "Licensing of Production and Utilization Facilities," and Section 2.110 of Part 2, "Rules of Practice," of Title 10 of the Code of Federal Regulations. For this application, the reference system is the Combustion Engineering Standardized Nuclear Stearn Supply System known as Standard Reference Systern-80. This design has been reviewed by the ACRS and was discussed in its report of September 17, 1975, "Conbustion Engineering Standard Safety Analysis Report - CESSAR-80."
The reactor containment scheme for the Yellow Creek plant consists of a spherical steel vessel and a reinforced concrete shield building, generally similar to those for the Cherokee and Perkins plants.
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Honorable Joseph January 13, 1978 An acceleration of 0.25g for rock-supported structures and 0.30g for soil-supported structures has been specified for the safe shutdown earthquake selected for the Yellow Creek Plant. 'I'he applicant has used a probabilistic treatment to choose an operating basis earthquake with which are associated ground level accelerations of 0.08g for rock sup-ported structures and O.lOg for those supported on soil. The Committee considers these values acceptable.
The NRC Staff has identified a number of safety items which will require resolution before issuance of a construction permit. These lllcltters should be resolved in a lllclnner satisfactory to the NRC Staff.
With regard to generic problems cited 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 the Yellow Creek Plant are: II-1, 2, 3, 4, SB, 6, 7, 9, 10; IIA-2, 3, 4; IIB-1, 2; IIC-1, 2, 3A, 3B, 4, 5, 6; IID-1, 2; IIE-1. These problems should be dealt with by the Staff and Applicant as solutions are found.
The Advisory Committee on Reactor Safeguards believes that if due con-sideration is given to the foregoing, the Yellow Creek Nuclear Plant, Units 1 and 2 can be constructed with reasonable assurance that it can be operated without undue risk to the health and safety of the public.
References
+~
Stephen Lawroski Chairlllcln
- 1. Yellow Creek Nuclear Plant, Units 1 and 2 Preliminary Safety Analysis Report, Volumes 1 through 6 and Amendments 1 through 10.
- 2. Safety Evaluation Report related to construction of Yellow Creek Nuclear Plant, Units land 2, NUREG-0347, December 1, 1977, Docket Nos. STN 50-566 and STN 50-567.
- 3. Letter from J.E. Gilleland, TVA to O. D. Parr, NRR, on safety grade instrumentation to detect the loss of cooling water to the reactor coolant pumps, dated September 14, 1977.
- 4. Letter from J.E. Gilleland, Tl/A to D. B. Vassallo, NRR, on revised operating basis earthquake, dated October 14, 1977.
- 5. Letter from J.E. Gilleland, TVA, too. D. Parr, NRR, on plant nonitoring system, dated November 7, 1977.
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Honorable Joseph January 13, 1978
- 6. Letter from J.E. Gilleland, 'NA, to D. B. Vassallo, NRR on out-standing issues, dated November 14, 1977.
- 7. Letter from J.E. Gilleland, TVA, to O. D. Parr, NRR, on out-standing issues, dated November 23, 1977.
- 8. Letter from G. R. Lanning, Jr., to the Nuclear Regulatory Commis-sion Advisory Committee [sic), on geology and emergency plans, dated December 16, 1977.
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