ML25196A274
| ML25196A274 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/19/1977 |
| From: | Bender M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC/Chairman |
| References | |
| Download: ML25196A274 (1) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 Honorable Joseph M. Hendrie Chainnan August 19t 1977 U. s. Nuclear Regulatory Ccmnission Washington, DC 20555 Si.Jbject:
REPORl' ON SHEARON HARRIS NUCLF.AR PCMER PLAN!'
Dear Dr. Herxlrie:
During its 208th meeting, August 11-13 1977, the Advisory Conmittee on Reactor Safeguards completed an updated review of the application of Carolina Power and Light C~ for a permit to construct the Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4. The application was first reviewed by the Conmittee in late 1972-early 1973 and reported on in its letter of January 17, 1973. Subsequently (May 8, 1975) the Applicant announced a three to six year delay in the project and an in-terruption of licensing activities. The principal matters of this review are:
(1) the applicability of new significant safety issues to the Shearon Harris plant and (2) the updating of previously reviewed matters to current requirements. These matters had been considered at a Subcomnittee meeting with the Staff and the Applicant in Raleigh, N. C. on August 6, 1977, following a site visit the preceding day. The Cormtl.ttee had the benefit of discussions with representatives and con-sultants of the Carolina Power and Light Ccmpany, the Westinghouse Electric Corporation, Ebasco Services, Inc., and the Nuclear Regulatory Camnission Staff (Staff). The Ccmnittee also had the benefit of the documents listed.
Each Shearon Harris unit will utilize a 2775 MWt three loop Westing-house pressurized water reactor (with 17x17 fuel asseui:>lies) enclosed in a steel lined concrete cont~,ment. The basic design of the nuclear steam supply system is similar to designs used for Virgil c. SUIIIIler, Unit 1, reported on in the Conmittee's letter of November 15, 1972 and Koshkonong Nuclear Plant Units 1 and 2, reported on in ACRS letters of January 15, 1976 and May 12, 1976.
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Honorable Joseph August 19> 1977 The safe shutdown earthquake acceleration for the Shearon Barris plant is 0.15g and that for the operating basis earthquake is 0.075g.
The Applicant has developed conservative seismic design response spec-tra and other seismic design bases in agreement with the latest NIC
- Regulatory Guides. The -Staff and the Ccmnittee concur that the bases for design of Category I structures, systems and components are appro-priate. The Applicant made a comprehensive investigation into the his-tory of 100vement along the geological fault, discovered in 1974, in the excavation for the Waste Processing Building. Results from a series of diverse radioactive dating methods indicated that the last ioovement of the fault had occurred a minimum of 2.5-35 million years ago. Based upon other geological considerations, the Applicant concluded that the last movement had occurred at least 150 million years ago. The Staff reviewed the information developed by the Applicant and agreed that the radianetric test results were minimum age assessments. The Staff con-cluded fran other geological considerations that the last movement took piace more than 136 million years ago. The Ccmnittee concurs with the conclusion of the Applicant and Staff that the fault is not capable.
The Applicant has reviewed the Shearon Harris safety design to assure that design, equipnent, materials, fabrication and construction meet or will be upgraded to meet current requirements. Safety systems under-going major modifications include: reactor core, reactor coolant, emer-gency core cooling, residual heat removal and waste processing systems, and Category I plant structures. The Applicant and the Staff concur that th.e Shearon Harris plant, to the extent details have been developed at this s~e of the project, conforms to current requirements. 80th the Staff and the Applicant need to continue to apply appropriate quality assurance measures to ensure that such conpliance continues throughout construction with particular attention paid to problems which could arise as a consequence of the unusual length of construction.
Two safety issues remain to be resolved prior to the Staff reconmenda-tion for issuance of a Construction Permit. These issues are confirma-tion of the nworst:, case" break for emergency core cooling system per-formance evaluation and the methodology and acceptance criteria for contaimnent subcompartment analysis.
These matters should be resolved in a manner satisfactory to the Staff.
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Honorable Joseph August 19, 1977 The Ccmnittee believes that the items mentioned above can be resolved during construction.
With regard to generic problems cited in the Ccmnittee's report, "Sta-tus of Generic Items Relating to Light-Water Reactors: Report No. s,*
dated February 24, 1977, items considered relevant to the Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4 are: II-2, 3, 4, 5, 6, 7, 9, 10; IIA-4., 5, 7; IIB-2; IIC-1, 2, 3, 5, 6; IID-2. These problems should be dealt with by the Staff and the Applicants as solutions are foum.
The design and construction of the four units at the Shearon Harris Sta-tion will span alloost two decades. The conmitment by the Applicant to participate in the timely resolution of generic matters identified by the NRC Staff and by the ACRS and the appropriate implementations are of major significance. The ACRS recomnends that the Applicant provide the Staff with annual reports on these matters. The reports should in-clude the safety programs in which the Applicant participates, evalua-tions made to improve reliability and effectiveness of engineered safety features, and design improvements incorporated into the units.
The Advisory Conmittee on Reactor Safeguards believes that if due con-sideration is given to the foregoing, the Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4 can be constructed with reasonable assur-ance that they can be operated without umue risk to the health and safety of the public.
References M. Beooer Chainnan
- 1. Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4, Prelimin-ary Safety Analysis Report, Volllltles 1-9
- 2. Amendments 1-62 to the Preliminary Safety Analysis Report
- 3. Safety Evaluation Report, related to the construction of the Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4, Supplement Nos. 1-3.
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Honorable Joseph M.. Herxlrie August 19, 1977 4.. Letter from J. A. Jones, Carolina Power and Light Campany to E. Case, U. s. Nuclear Regulatory Ccmnission, on Fault Investi-gation, Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4, dated March 7, 1975.
- 5. Letter from J. A. Jones, Carolina Power and Light Coopany to B. C. Rusche, Office of Nuclear Reactor Regulation, U. s. Nuclear Regulatory Coomission, concerning responses to NR:: questions on the geological fault investigation, dated June 1975.
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