ML25197A087
| ML25197A087 | |
| Person / Time | |
|---|---|
| Issue date: | 12/10/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC/Chairman |
| References | |
| Download: ML25197A087 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Honorable William A. Anders Chairman
- u. s. Nuclear Regulatory Conmission wasbington, DC 20555 December 10, 1975
Subject:
REPORl' Oi C. F. BRAUN STANDARD TClRBINE ISLAND DESIGN (BRAUN SAR)
Dear Mr. Anders:
At its 188th meeting on December 4-6, 1975, the Advisory Comnittee on Reactor Safeguards reviewed the application of c. F. Braun and Conpany for a Preliminary Design Approval (PDA) of its Standard '!'Urbine Island Design, Braun SAR, which has been developed as a conplementary element
.~£ the General Electric Company's BNR-6/Mark III Standard Nuclear Island design, GESSAR-238. ~e Braun SAR was previously reviewed at a SUbcannittee meeting in Washington, DC on December 3, 1975.
During its review, the Conmittee had the benefit of discussions with representatives of c. F. Bratm and Conpany and the Nuclear Regulatory Conmission (NRC) Staff. ~e Conmittee also had the benefit of the documents listed. ~e Bratm SAR together with the General Electric Company's GFSSAR-238, which was reviewed by the ACRS in its report dated March 14, 1975, is nearly equivalent t.o standard PWR Nuclear Steam SUpply Systen designs such as RESAR-41 and CESSAR-80 coni>ined with standard Balance of Plant designs such as SWESSAR..
'Ihe Bratm SAR describes the analysis and design of the structures, systems, and canponents within the piysical boundaries of the turbine island portion of the plant. Since most of what is included is conventional steam-electric power conversion equipnent and space for the radioactive off-gas systems, the major safety matters of interest are those concerning the interfaces with safety-related features identified in GESSAR-238 and those to be proposed by the nuclear power plant license applicant in the Balance of Plant design.
'Ihe interface responsibilities related to GESSAR, Bratm SAR, the Balance of Plant design, and the nuclear power plant license applicant are still being worked out by the NRC Staff. 1he Committee wishes to be kept informed of the resolution of these matters.
139
Honorable William December 10, 1975
'Ihe propos~ turbine island design will pe.r:mit the use of turbine-generators fran any of three U.S. suppliers. 'Ibis approach ai;pears to be acceptable but will require further examination when a conplete tmit, including a specific turbine-generator, is proposed for licensing by a utility applicant.
'Ihe integration of fire protection for the plant and the coordi-nation of instrumentation sensors in the turbine island with inter-dependent controls in the nuclear island and in the Balance of Plant, will require attention at the time when Braun SAR is used~ a portion of a nuclear power plant license application. Plans for dealing with these matters should be included in the NBC Staff's standard review plans.
'Ihe proposed orientation of the turbl.ne-generator with respect to the nuclear island is suitable for a single tmit installation. For multiple unit power plants, the location and orientation of the tmits should be such as to yield acceptably low probabilities of damage by low-trajectory turbine-generator missiles unless suitable missile-shielding is provided.
Generic problems related to large water reactors are discussed in the
,Conmittee*s report dated March 12, 1975. 'Ibose problems relevant to Braun SAR should be dealt with appropriately by the NBC staff and the.
Applicant.
'Ihe Advisory Committee on Reactor Safeguards believes that the item.c; mentioned above can be resolved during the standardized plant licensing process and that if due consideration is given to the foregoing, Preliminary Design Approval for Bratm SAR can be granted in accord with the spirit and purposes set forth in the Conmission*s policy statement on standardization of nuclear power plants as described in WASB-1341, 0 Programmatic Information for the Licensing of Standarci-ized Nuclear Power Plants0 and in conformance with the Regulations of
.Appendix O to Part 50 and Section 2.110 of Part 2 of Title 10 of the Code of Federal Regulations.
Sincerely yours,
~
- w. Kerr Chairman 140
Honorable William December 10, 1975 References
- 1. Braun Safety Analysis Report (Braun SAR)
- 2..Amendments Nos. 1 through 7 to Braun SAR
- 3. Report to the Advisory Cammi ttee on Reacto~ Safeguards by the Office of Nuclear Reactor Regulation, u.s. Nuclear Regulatory Conmission in the Matter of c. F. Braun and. Conpany, Braun SAR Standard Turbine Island Design D:>cket No. sm 50-532, dated November 1975 141