ML25196A229
| ML25196A229 | |
| Person / Time | |
|---|---|
| Issue date: | 07/22/1977 |
| From: | Bender M Advisory Committee on Reactor Safeguards |
| To: | NRC/OCM |
| References | |
| Download: ML25196A229 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 United States Nuclear Regulatory Comnission Washington, o.c. 20555 July 22, 1977
SUBJECT:
REPORL' ON BLACK FOX STATION, UNITS 1 AND 2
Dear Cornnissioners:
During its 207th meeting, July 14-15, 1977, th~ Advisory Corrmittee on Reactor Safeguards reviewed the application of the Public Service Com-pany of Oklahoma, Associated Electric Cooperative, Inc., and Western Farmers Electric Cooperative (the Applicants) for a permit to construct the Black Fox Station, Units 1 and 2. The Public Service Company of Oklahoma will be responsible for the design, construction, and opera-tion of the station. The application was reviewed at a Subcornnittee meeting in Tulsa, Oklahoma on June 30, 1977 following a visit. to the site by Corrmittee members on the same day. During its review, the Cornnittee had the benefit of discussions with the Nuclear Regulatory Cornnission Staff (Staff), representatives of the Applicants, Black &
Veatch Consulting Engineers, and the General Electric Company. The Corrmittee also had the benefit of the documents listed and a presenta-tion by a member of the public.
The Black Fox Station (BFS) consists of two 3579 MWt reactors of the GFSSAR-238 NSSS design, which uses a BWR/6 boiling water reactor, each housed in a Mark III containment. The design of the BFS units is sim-ilar to that of the Hartsville and Phipps Bend units on which the Com-mittee reported May 13, 1976 and May 11, 1977 respectively. 'lbe Staff issued -a Preliminary Design Approval No. PDA-10 dated March 10, 1977 for the GESSAR-238 NSSS.
The GESSAR-238 includes the reactor, the reactor coolant system, the reactor protection system, the engineered safety features, and related auxiliary syste.111s on which the Cornnittee reported in its letter of December 17, 1976. The Applicants will design the portion of the plant external to the NSSS.
Al though the BFS is not a GESSAR-238 nuclear island design, it is very similar to that design.
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Commissioners July 22, 1977
'!he plant will be located in Rogers County in northeastern Oklahoma, approximately 23 miles east of the center of Tul.sa. 'lhe site consists of 2,206 acres bordering on the Verdigris River. The minimum exclusion area boundary distance is 2,790 feet. The low population zone has a rad-ius of 2.5 miles and includes a present population of 220. The nearest population center is Tulsa which had a population of 330,350 in 1970.
The Black Fox site is in a region of low seismic activity, and the Applicants and Staff have agreed on a horizontal ground acceleration of 0.12g for the safe shutdown earthquake and 0.06g for the operating basis earthquake. The Connnittee considers these values acceptable for this plant.
The BFS will be the first commercial nuclear power plant in the state of Oklahoma. For this reason, the Committee recommends that the Applicants and Staff give particular attention to assuring proper coordination with appropriate state and local agencies in the develop-ment of effective plans for routine environmental surveillance and emergency response for this facility.
The Committee believes that the item mentioned above can be resolved during construction.
With regard to the generic problems citeo in the Committee's report "Status of Generic Items Relating to Light-Water Reactors: Report No. 5," dated February 24, 1977 (attached), items considered rele-vant to the BFS are: II-4,6,7,10; IIA-1,5; IIB-2,3,4; IIC-2,3,5; IID-1,2. These problems should be dealt with by the Staff and the Applicants as solutions are found.
The Advisory Committee on Reactor Safeguards believes that if due consideration is given to the foregoing, the Black Fox Station, Units 1 and 2, can be constructed with reasonable assurance that they can be operated without undue risk to the health and safety of the public.
Attachment:
M. Bender Chairman Letter to Hon. M.A. Rowden from M. Bender dated 2-24-77, "Status of Generic Items Relating to Light-Water Reactors: Rpt. No. 5."
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Comnissioners July 22, 1977
REFERENCES:
- 1. Black Fox Station, Units 1 and 2, Preliminary Safety Analysis Report, volumes I-IX.
- 2.
Amendment 1-8 to the Preliminary Safety Analysis Report.
- 3. Safety Evaluation Report, NUR00-0190, related to the con-struction of the Black Fox Station, Units 1 and 2, June 1977.
- 4. I:bcurnents provided to the Conmittee by Dr. Richard E. 'Webb on July 14, 1977 at the 207th ACRS meeting:
- a. Black Fox Station, Units 1 and 2, Atomic Safety and licensing Board (ASLB), Memorandum and Order, May 25, 1977.
- b. Black Fox Station, Units 1 and 2, ASLB, Intervenors, C.A.S.E., Ilene Younghein, Lawrence Burrell and Clark Glymore, Response to Board's R~est for Credible Mechanisms, Board's Order, March 29, 1977.
- c. Black Fox Station, Units 1 and 2, ASLB, Staff Memorandum regarding Treatment of Extremely Large Accidents in the Health and Safety Hearing, March 24, 1977.
- d. letter dated 11-24-76 from R. E. Webb to c. Glymore, transmitting information on Black Fox Station.
- e. Research proposal submitted to u. s. Nuclear Regulatory Commission and u. s. Energy Research and Developnent Mministration by University of Massachusetts/Amherst;
.Amherst, Massachusetts 01002; October, 1976.
- f. Report for The Corranittee Ch Nuclear Energy-Massachusetts legislature, by Richard E. Webb; unpublished work, copy-right, Richard E. Webb,.1976; April 6, 1976.
- g. Miscellaneous sketches.
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