ML20039H225
| ML20039H225 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 08/23/1977 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Taylor J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190740 | |
| Download: ML20039H225 (2) | |
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4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION f
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W 2 31977 Docket No. STN 50-561 Babcock & Wilcox Company ATTN: Mr. James H. Taylor Manager of Licensing Nuclear Power Generation Division P. O. Box 1260 Lynchburg, Virginia 24505 Gentlemen:
SUBJECT:
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT - BSAR-205 A copy of the subject Report, dated August 18, 1977, is enclosed for your use.
We have placed a copy of this report in the Commission's Public Document Room located at 1717 H Street, N. W., Washington D. C.
Sincerely, J
N b. L Llan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
As Stated cc w/ enclosure:
See Next Page O
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I 8201190740 810403 PDR FOIA MADDEN 80-515 PDR
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g Babcock & Wilcox Company AUG 2 3 7977 cc w/ enclosure:
Washington Public Power Supply System Mr. Al Lazar ATTN: Mr. N. O. Strand Babcock & Wilcox Managing Director (Acting)
Power Generation Group P. O. Box 968 P. O. Box 1260 3000 George Washington Way Lynchburg, Virginia 24505 Richland, Washington 99352 U. S. Environmental Protection Agency Mr. Robert Borsum ATTN:
EIS Coordinator Bethesda Representative Federal Activities Branch Babcock & Wilcox Region V Office Nuclear Power Ge.3 ration Division 230 South Dearborn Street Suite 5515, 7735 Old Georgetown Road Chicago, Illinois 60604 Bethesda, Maryland 20014 Honorable Alvin J. Vaith B. G. Shultz Chainnan, Board of County Commissioners Project Engineer Erie County Courthouse Stone & Webster Engineering Corporation Sandusky, Ohio 44870 P. O. Box 2325 Boston, Massachusetts 02107 Ohio Edison Company ATTN: Mr. Lynn Firestone Mr. W. E. Kessler Vice President Commonwealth Associates, Inc.
76 South Main Street 209 East Washington Akron, Ohio 44308 Jackson, Michigan 49201 Gerald Charnoff, Esquire Robert J. Kafin, Esq.
Shaw, Pittman, Potts & Trowbridge 115 Maple Street 1800 M Street, N. W.
Glen Falls, New York 12801 Washington, D. C.
20036 Mr. B. M. Miller Thomas A. Kayuha, Esquire Ohio Edison Company Ohio Edison Company 76 South Main Street 76 South Main Street Akron, Ohio 44308 Akron, Ohio 44308 Ohio Department of Health ATTN: Director of Health 450 East Town Street Columbus, Ohio 43216 Harold Kahn, Staff Scientist Power Siting Commission 361 East Broad Street Columbus, Ohio 43216 m
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION j
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS I
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August 18, 1977 Honorable Joseph 11. Hendrie Chairtran U. S. Nuclear Regulatory Comission Washington, DC 20555
Subject:
REPORT Oil BABCOCK-205 STANDARD IUCLEAR STEAM SYSTEM
Dear Dr. Hendric:
At its 208th Meeting, August 11-13, 1977, the Advisory Comittee on Reactor Safeguards cc:rpleted its review of the application of Babcock
& Wilcox Co:rpany (.Tpplicant) for a Preliminary Design Approval (PDA) for its Standard nuclear Steam System (SSS), Babcock-205. A Subcomittee meeting was held uith representatives of Babcock & Wilcox Company (B&W) and the Nuclear Regulatory Corralission (NBC) Staff in Washington, D.C.,
on July 27, 1977. The Comittee had the benefit of discussions with q ')
representatives of the NRC Staff and the Applicant. The Comittee also had the benefit of earlier reviews of other Standardized Nuclear Steam Supply Systems and of the documents listed.
The B!.M Standard Safety Analysis Report (B-SAR-205) describes the B&W standardized two loop NSS for a 3820 t@it pressurized water nuclear plant with a core therrral power output of 3800 MWt. Its scope in-cludes the Reactor, Reactor Coolant System, Pressurizer Relief System, Emergency Core Ccaling System, Decay Heat Renoval System, Chemical Addition and Boron Recovery System, Makeup and Purification System, Instrumentation and Ccntrols, and Fuel Handling System. The reference design is similar to recent B&W 3620 mkt NSS designs reported on by the Comittee: Bellefcnte Nuclear Plant, Units 1 and 2 (July 16,1974),
Washington Public Potter Supply Systan Nuclear Power Stations 1 and 4 (June 11,1975) and Pebble Springs Nuclear Plants 1 and 2 (February 11, 1976). Earlier ACPS reports on PDA applications for standard reference nuclear steam supply designs are the March 14, 1975 report on the General Electric 90mpany GESSAR-238 Huclear Island and the December 17, 1976 report on die General Elec*.ric Company GESSAR-238 and GESSAR-251 Nuclear Steam Supply Systen, the Septerber 17, 1975 report on Combustion Engineer-ing, Inc., CESSAR-80, and the September 18, 1975 and July 14, 1976 reports on Westinghouse Electric Corporation RESAR-41 and RESAR-3S.
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\\ August 18, 1977 lionorable Joseph M. Hendrie The Applicant has selected horizontal ground accelerations of 0.3g and 0.159 as appropriate design values for the safe shutdown and opera-ting basis earthquakes, respectively. Designs for the protection of Babcock-205 safety-related co::ponents and systems from other site-related hazards will be included in the balance of plant design. The reference NSS design includes the interf ace requirements inforcation essential to a balance of plant safety design consistent with the assumptions used in the NSS design-basis accident analyses. Since the utility-applicant will be responsible for instituting the quality assurance programs necessary to assure that all safety-related design requirements have been met, the Ccmittee will review these matters in more detail with the utility-applicants on a case-cy-case basis.
The NRC Staff had listed thirteen outstanding issues in its report to the The NBC Staff ncw believes that it has the information it needs to ACRS.
resolve eight of the thirteen issues, and that the remaining five issues The ACRS can be resolved before the anticipated time of granting the PDA.
recomr. ends that all outstanding issues be resolved in a manner satisfac-tory to the NRC Staf f.
j The Comittee believes that for Babcocs-205, as well as for other standardized nuclear steam supply systercs, studies should be made to quantify the reliability, effectiveness and safety margins for the The studies should include evaluation Emergency Core Cooling Systems.
of current NRC and EPRI programs on alternate ECC Systems to determine These efforts what, if any, improvements are practicable and desirable.
will require the substantiation of the bases for best estimate analyses and verification of codes, and increased input to and participation in the related NRC programs for safety research.
New features in.the instrument and control systems have been introduced through the specification of functional designs and design criteria f.
On all issues which the NRC Staf f har f ound to be adequate for the PDA.
involving instrumentation and control, the Comittee will use the case-by-case basis to ascertain progress of the work until the Babcock-205 design has progressed to the stage where Final Design Approval is achieved.
The Comittee has encouraged Applicants to consider instrumentation with the necessary ranges and diversity to follow the course of an accident.
4 Tmendations. Fct Regulatory Guide 1.97 (Revision 1) embodies these reco:
Trcends that a standardized PWR's, such as Babcock-205, the Comittee reco:
study be made of the merits of including instrumentation to sense the water level in the reactor pressure vessel.
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!!onorable Joseph M. Elendrie August 18, 1977 The Babcock-205 design includes provisions which anticipate maintenance, inspection, and operational needs of the plant throughout its service life. The Comittee believes that the NRC Staff and the Applicant
.I should continue to seek improvements in provisions of this type and, in addition should revies procedures for renoving accumulations of radioactive contamination so that maintenance and inspection programs and eventual decomicsioning can be more effectively and safely carried out.
The Cor.mittee believes that B&W and the NRC Staff should intensify their review for design provisions that will further inprove protection against sabotage and that provisions found timely diould be incorporated in early applica'. ions of Babcock-205.
With regard to other generic problems cited in the Committee's report,
" Status of Generic Items Relating to Light-Water Reactors: Report No. 5," dated February 24, 1977, items considered relevant to Babcock-205 are:
II-3, 4, 5, 6, 7, 9,10; IIA-3, 4, 5, 6, 7; IIB-1, 2; IIC-1, 4, 5; IID-1, 2.
These problems should be dealt with bf the Staff and the Applicant as solutions are found.
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The Comittee believes that methods that seek to develop reference systems through standardization and through replication need to be coupled with ongoing programs that will permit design changes which inprove safety and which, when justified, will be inplemented in a timely manner. Uce of reference systems should lead to more efficient and ef-
.fective licensing reviews. Standardized designs such as Babcock-205
.i. will-contiribute to this process. A transition period will be required
<. intwhich the Committee will still give attention to the items noted, on
' a case-by-case basis.
i The Cor.mittee. believes that, subject to the above coments and success-ful completion of the R&D programs, the Babcock-205 design can be suc-cessfully engineered to serve as a reference system.
Sincerely yours, Ojy?.
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M. Bender Chairman
j lionorable Joseph M.11endrie August 18, 1977
REFERENCES:
1.
The B&W Standard Safety Analysis Report (B-SAR-205) and Amendments 1 through 16.
2.
Report to the Advisory Comittee on Rhactor Safeguards by the Office of Nuclear Reactor Regulation, (CNRR), U. S. Nuclear Regulatory Comission in the Matter of Babcock and Wilcox Company Reference Safety IV:alysis Report, B-SAR-205, Docket No. STN 50-561, July 8,1977.
3.
Babcock and Wilcox letter to ONRR, Attention: Mr. Roger S. Boyd,
Subject:
B-SAR-205 - Outstanding Issues, dated July 15, 1977, Docket STN 50-561.
4.
Babcock and Wilcox letter to ONRR, Attention: Mr. Roger S. Boyd,
Subject:
B-SAR-205 - Outstanding Issues, dated July 21, 1977, Docket STN 50-561.
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