ML20198G606
| ML20198G606 | |
| Person / Time | |
|---|---|
| Issue date: | 03/15/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2384, NUDOCS 8605290695 | |
| Download: ML20198G606 (13) | |
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.3 DATE ISSUED: March IS, 1986 SUMPARY/ MINUTES ACRS SUBCOMMITTEE MEETING ON STANDARD PLANT DESIGN JANUARY 6, 1986 WASHINGTON, D. C.
A meeting was held by the ACRS Standard Plant Design Subcommittee.
Notice of the meeting was published in the Federal Register on December 1
17, 1985 (Attachment A). The schedule of items covered in the meeting is in Attachment B.
The list of attendees is in Attachment C.
A list of the meeting handouts is in Attachment D.
The handouts are filed with the office copy.
H. Alderman was the designated ACRS Staff member. The meeting was convened at 1:30 p. m.
1 Principal Attendees ACRS NRC Staff C. Wylie, Subcommittee Chairman F. Miraglia, NRR C. P. Siess H. Berkow, NRR G. Reed C. Thomas, NRR i
C. Michelson D. Scaletti, NRR
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SUMMARY
/ STANDARD 2
PLANT DESIGN - Jan. 6, 1986 Opening Statement - Subcommittee Chairman C. Wylie Mr. Wylie noted that the purpose of the meeting was to review the NRC Staff proposed standardization policy statement to the Commission on nuclear power plants, and to be briefed by the staff regarding the status of the policy statement and the status of standardization in regard to nuclear power plants.
He also noted that the subcommittee eventually will consider what it wants to present to the full Committee and if there is a need for the ACRS to write a letter on the policy statement and what other future activities leading up to a letter on standard plants that the subcommittee would wish to consider.
F. Miraglia, Division Director of Pressurized Water Reactors Licensing-B Mr. Miraglia noted that within his scope he has the responsibility for the development of standardization policy.
He remarked that the concept of standardization was basically developed in April 1972 when the Commission proposed development of a standardization policy.
In March 1973 the Commission announced three concepts that it would use in the context of standardization. These are:
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MINUTES /
SUMMARY
/ STANDARD 3
PLANT DESIGN - Jan. 6, 1986 s
o Reference Design System - application for approval of the design of an entire plant or major portion thereof, o
Duplicate Plant Concept - this involves the application by one or more utilities for licenses to construct and/or operate a number of nuclear power plants of essentially the same design at different sites.
o Manufacturing license concept - The manufacturing license concept involves an application for a license to manufacture a number of identical nuclear power plants at a location other than those at which they are to be operated.
In August of 1974 the Replicate Plant Concept was added. The Replicate Plant Concept involves an application by a utility for a license to construct and/or operate one or more nuclear power plants of essentially the same design as one already licensed.
Mr. Miraglia explained that the current policy statement resulted from a need to update the 1978 policy statement to include the experience since that time and the Severe Accident Policy Statement.
Mr. Miraglia noted that the staff is proposing to retain the reference system design. The reference system is an application for approval or certification of an entire plant or substantial portion of a plant.
f MINUTES /
SUMMARY
/ STANDARD 4
PLANT DESIGN - Jan. 6,* 1986' A Comittee member asked if on a duplicate or replicate reference design
- would that have to be the whole plant? Mr. Miraglia replied that it would.
A Committee member asked Mr. Miraglia about how a substantial portion of a plant is interpreted? He asked if it means that the NRC staff will continue to accept NSSS and B0P as separate items like the old reference designs?
Mr. Miraglia replied that the thrust of the Commission's intent is that the reference design is what the Comission is after. However, the Staff retained the language of substantial or major portion because that language is used in the legislation.
There was considerable discussion regarding interfaces. Mr. Miraglia pointed out there are design interfaces and instruction interfaces. He noted that depending on the scope of the application, the interfaces could be narrow or broad.
Mr. Thomas pointed out that the review of a reference design is outside the context of a specific application.
Part of the review is deferred to when a utility submits an application for a license that references it.
Mr. Miraglia noted that if it is a very broad scoped reference plant, if it covers the whole plant, then the amount of information and what you need to assure that the interfaces have been met is very small.
.i MINUTES /SUMPARY/ STANDARD 5
PLANT DESIGN - Jan. 6; 1986-Mr. Thomas noted that interface requirements appear in the application for standard design and they are supplemented by interface requirements in the Staff Safety Evaluation Report. The two taken together consti-tute the set of interface requirements that must be addressed by a utility applicant.
A Comittee member asked if you take a complete plant to design certi-fication, does that mean that the final design is not subject to litiga-tion?
Mr. Miraglia responded that what it means is that the final design is not subject to litigation to the extent that the scope is covered.
Regarding the amount of review for a standard plant, Mr. Miraglia pointed out that an individual standard plant would not save review time.
If a number of standard plants were built, then a considerable amount of review time would be saved.
Mr. Miraglis pointed out that in response to industry input, a replica-tion provision was put in the policy paper.
This allows a plant to be replicated up to five years from the promulgation of the policy state-ment.
He also noted that deviations from some of the provisions of the policy statements would be considered on a case-by-case basis.
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MINUTES /
SUMMARY
/ STANDARD 6
PLANT DESIGN - Jan. 6',
1986^
Another provision added to the policy statement is the Standard Review Plan (NUREG-0800). NUREG-0800 is the revision of the Standard Review Plan that incorporates all the TMI requirements. The policy statement indicates that if a plant was reviewed against NUREG-0800 then replication of that plant would be considered at any site. Also, an older plant that preceded NUREG-0800 would be considered for replication if it was supported by good design and a suitable operating history of that particular plant design.
Mr. Miraglia pointed out that Atomic Industrial Forum (AIF) wanted design approval and certification to be for 10 years. The NRC staff proposed 5 years for design approval and 10 years for certification.
The premise for the difference was to encourage the effort towards
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certification.
Regarding the level of design information for a final design approval or a design certification, NRC used the terms " equivalent to the FSAR."
AIF took the position that it could be less. Mr. Miraglia pointed out the need for further discussions between the staff and industry to better define the level of design information necessary for design approval and certification.
Regarding the application of the cost / benefit balance, AIF wanted to apply this to the lead plant. The staff did not agree.
The Subcommittee members had an informal discussion following the prepared presentation. One member expressed his opinion that the policy L
MINUTES /
SUMMARY
/ STANDARD 7
PLANT DESIGN - Jan. 6,' 1986' statement didn't give the assurance necessary that all the requirements are stated and a utility can order a reactor with confidence.
Mr. Miraglia noted that the policy statement provides options for the near term and other options for long term.
One member suggested that the NRC certify nuclear plants in a manner similar to Federal Aviation Authority (FAA).
One member noted that he was displeased with the overall policy state-ment but was pleased with many of the changes since the last policy statement.
One member suggested the Commission should concentrate on a complete design.
The meeting was adjourned at 4:35 p.m.
NOTE:
Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H St., NW., Washington, D. C., or can be purchased from ACE-Federal Reporters, 444 North Capitol Street, Washington, D. C. 10001, (202) 347-3700.
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a., t c: r..wan., ties any ofits consultar.ts who may be Cr_m C,mn.,g as C.U :s ts-In acecrdance with the Paperwork present, may exchange preliminary Ccmmim.:
Redat tion A::t and OM3 Guidelines, the views regarding matters to be p _.,. -,b
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Na!! anal S:icnce Foundation is posting considered during the balance of the Feb.: nch 5Coi e Icn: A:mally.
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presentetions by and hold discussic:.s Use:'l ) nerfr the.Wtionel Endor.rnent Fhi W 3 4-9520.
with representatives of the NRC Staff.
for ?..H::a:n" ' DaI:!on of Ftate OM"1DM Offican Carlos Tellez.
Its consultants, and other interested Prog ru ef th> Committec's (202)335-7343.
Persons rrgarding this review.
Title:
S r.ey of Earned Doctorates copuct wi 't the Ecclewmenl's Award >d in the United States.
Further information regarding topics to be discussed, whether the meeting authm:NlegEtion so that the AffectedPsblic: Individuals.
has been cancelled or rescheduled, the comm'ttee can r_=ain e!!gible for Numberof Responses:31.000 Chairman's ruling on request for tl.e fundier.
responses; total of 10.300 burden hours, Estimal5IN& cf Renondents: 53 Abstract: Persons with doctorate-level opportunity to present oral statements and the time allotted therefor can be Estimat:d Ho ::s f r Ft: pendents to education are key members of the labor obtained by a prepaid telephone call to Pro. ide Inf :-
f rce in scientific, engineering and the cognizant ACRS staff member. Mr.
reapader.t :.m rir..G hacrs per ur :de tota! hours for at1 learred professions. Information of their n:<pondente.
demegraphic and educational Herman Alderman (telephone 202/ti34-
- 2. Ti:'e: Divis.m uf S' ate P:cgram Plan background and immediate postdoctoral 1414} between 8:15 a.m.end 5.00 p.m.
for Compli. c., by State Humamties study or employment plans is essential Persons planning to attend this meeting Council 2 Optating as State Agencies. for :nalyses of supply and demand.
are urged to contact the above named Thde data also report on the flow of Individual one or two days befure the Form Ni 9,r:3136-407a Fraw7f Collection: Annually women and minorities into the fields.
scheduled meeting to be advised of any changes in schedule. etc., which may Rew n3ds: State humamtirs councils Dated: December 12.1985.
have occurred.
cp uting as state agencies.
Herman G. r!c:.!:g.
. Dated: December 12.1985.
Ilse: T2 ptify the National Enduwment NSFReports Cleomece Oficer.
Morton W.11barkin.
forine Humantiles Division of State
[G Doc. 85-2Wm Fded 12-16-a5. 8 45 am]Assistant ExecutiveDimerorforPrvicet Programs of the agency a compliance
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with the Endowment's authon,zmg
[FR Doc. 85-29838 Fded 12-1645: 8.45 em) legislation so that the agency can NUCLEAR REGULATORY remain eligible for funding.
COMMISSION Estimated Number of Respondents: 53 i/
the maximum possible number of Advisory Ccmmittee on Resctor IDocket No. 50-312) respc.d*ts.To date the:v are none.
SafcmrJ3; 2_ n.r-AM: on Estimated Hours for Respunants to S E2d ?.'d Pir.7.. MGui.'.tR!!n9 Sscramento i.We'.o.C '.h j We Envi.onmcatal ksmmer.t snu Provide Information: 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per The ACRS Subcommittee on Standard Finding of No Significant impact Plant Design will hold a renting on l
respondent for 5.300 total hours if all states were state agencies.
January 6.19ES. Room 10 0.1717 H The U.S. Nuclear Regulatory 3.
Title:
Division of State Programs Street. NW.. Washmgto,n. DC.
Commission (the Commissior. is considering issuance of an exe)mption Interim Progress Report Format The entire meetm Form Number: 3136-0077 pubhc attendance. g will be open to from a requirement of 10 CFR Frequency of Co!!ection: Biennially The agenda for subject meetm.g shall 50.44(c)(3)(iii) to the Sacramento R;s ondents:Statehumanities councils be as follows: Mondoy.fanuary 6.
hiunicipal Utility District (the licensee).
Use Provide progress update on the 1986-1-Jap.m. until the conclusion of for the Rancho Seco Nuclear Cencrating during the previous year and is he$u'bcommittee will review the Station. located in Sacramento County, two-year grant approved for funding California.
necessary to for use by the NRC Staff paper on standard plants and Endowment's chairman to determine discuss the status of standard plants.
Environmental Assessment
" adequacy ** (as required by NFAH Oral statements may be presented by Identificallon 0fProPosedAction: The Cuthorizing legislation) in order to members of the public with the exemptmn would permit the licensee not concurrence of the Subcommittee to install a reactor vessel head vent as receive second-year funding.
Chairman: writtin statements will be required by to CFR 50.44(c)(3)(iii).
- Estimated Number of Respondents:26-accepted and made available to the The exemption is responsive to, the 28 Committee. Reccedings will be permitted licensee e application for exemption Estimated Hours for Respondents to only during those portions of the dated April 12.1985.
Provide Information:20 hours per' meeting when a transcript is being kept.
The Needforthe Propose,dActionr, respondent for 480-560 total hours for and questions may be asked only by The licensee has performed tests using d
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members of the Subcommittee. Its the Once.Through integral System 8"" M*"
consultants, and Staff. Persons desiring (OTIS) facility. The purpose of these ActingDirectorofAdatimstation.
to make oral statements should notify tests was to determine if reactor core
[R Doc. 85-29815 Filed 12-1645; 8.45 emi the ACRS staff member named below as cooldown can be maintained in the
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far in' advance as is practicable so that absence of a vessel head vent to release appropriate arrangements can be made.
noncondensible gases from the vessel I
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TENTATIVE SCHEDULE ACRS STANDARD PLANT DESIGN SUBCOMMITTEE JANUARY 6, 1986 1:30 p.m.
Introductory Statement Subcommittee Chairman 1:40 p.m.
Background of Nuclear Power NRC Staff Power Plant Standardization 2:15 p.m.
Standardization Policy Statement of August 1978 BREAK 3:00 p.m.
3:10 p.m.
Standardization Policy Statement of December 4, 1985 3:40 p.m.
Status and Implementation of Nuclear Power Plant Standardization 4:00 p.m.
Subcommittee Discussion 4:30 p.m.
Adjourn 1
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H. ALDERMAN
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