ML20003H479
| ML20003H479 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/02/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1825, NUDOCS 8105060088 | |
| Download: ML20003H479 (18) | |
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ISSUE DATE: 3/2/81 MINUTES OF THE
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ACRS SUBCOMMITTEE MEETING ON PLANT FEATURES IMPORTANT TO SAFETY FEBRUARY 3, 1981 1717 H ST., NW, WASHINGTON, DC The ACRS Subcommittee on Plant Features Important to Safety held a meeting or.
February 3,1981 in Room 1167, 1717 H St., NW, Washington, DC. The purpose of the meeting was for the Subcommittee to discuss with the NRC Staff the defini-tions of the tems " safety g.ade," " safety related," and "important to safety" as developed for testimony,related to the Three Mile Island, Unit I restart, as well as review the generic implications of these definitions in the licen-sing process. The NRC Staff had asked for for an ACRS opinion regarding these definitions. The meeting was entirely open to the public. The Designated Federal Employee for this meeting was Richard Major. Mr. J. Gallagher repre-senting an ad hoc group established between the IEEE and the NRC Staff made a brief presentation and submitted related slides. Subsequent to the meeting, Mr. Gallagher has made available a draft version of an IEEE Trial Use Guide:
A Method for Determining Requirements for Instrumentation, Control and Elec-trical Systems Equipment Important to Safety. This is on file at the ACRS Office. Notice of this meeting appeared in the Federal Register, Vol. 46, No.12, on Monday, January 19, 1981. A list of attendees is enclosure 1.
I MEETING WITH NRC STAFF Mr. Ward noted in his opening remarks that as a result of contentions in the TMI-1 restart hearings, the Staff has.found it necessary, as well as helpful, in organizing its own thinking to develop concise definitions for the terms:
"important to safety," " safety grade," and " safety related."
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PLANT FEATURES IMPORTANT February 3,1981 TO SAFETY The term "important to safety" is found in 10 CFR 50, Appendix A of the General Design Criteria. The term applies to those structures, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public.
The term " safety grade" is.not explicitly used in the e egulations, but its It usage as applied by the Staff is derived from 10 CFR 100, Appendix A.
includes structures, systems, and components (designed to remain functional
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for the Safe Shutdown Earthquake) necessary to assure (1) the integrity of the reactor coolan't pressure boundary,(2) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guidelines in 10 CFR 100.
The term " safety related" is defined in the regulations fl0 CFR 50, Appendix B)
The term is used in in the context of quality assurance program requirements.
Regulatory Guides and the Standard Review Plar. In contexts other than quality The Office of Standards Develop.nent (OSD) had proposed a change to assurance.
l the regulations that would establish " safety related" and equivalent to "impor-I tant to safety." The Office of Nuclear Reactor Regulation (NRR) has opposed l
this proposal by Standards because, in other than the quality assurance con-l texts, " safety related" has been widely used as equivalent to " safety grade."
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The At this point, the definition has not been finally decided. [ Note:
attached January 29, 1981 memorandum for H. Denton from D. Ross,
Subject:
I Non-Concurrence on " Proposed Amendment to 10 CFR 50 Appendix A to Clarify l
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PLANT FEATURES IMPORTANT
'3-February 3,198; TO SAFETY P
Quality Assurance Program Requirements," gives a'dditional details on this.
Since the meeting, NRR, OSD, and ELD all agree that the term " safety subject.
related" is equivalent to " safety grade" ad defined in James Conran's TMI-1 restart testimony to UCS.ontention #14.
Proposed changes to 10 CFR 50 Appendix A and Appendix B are given in Enclosure 1 to the January 27, 1981 This documentation was provided to the Subcommittee subsequent to the memo.
meeting.]
Mr. Ward noted that, in general, safety grade is a subset of important to safety.
Mr. Ward saw as a parallel, if not the same issue, the question of a graded quality assurance system. The Staff has expressed some unhappiness with industry's all or nothing approach to quality assurance. Quality assurance philosophers, in general, would like to see quality assurance applied com-mensurate with risk. This suggests defining subsets of "important to safety,"
as one way of starting a graded quality assurance approach. This then serves as a tie-in between the definitions of terms and quality assurance categories.
Mr. Ward noted that the Subcommittee should consider whether to concur with a l
set of well thought out semantics as proposed by the Staff or whether to work l
l with the Staff to develop definitions of a more comprehensive nature which could have some impact on how systems are designed and evaluated in the He noted there was a spectrum of positions the Subcommittee could future.
adopt in between.
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PLANT FEATURES IMPORTANT February 3,1981 TO SAFETY The Staff notes it is their immediate aim to obt'ain ACRS concurrence in the definitions set forth in the TMI-1 testimony. A longer' term goal could be pursued in conjunction with the development of methods for ranking systems, structures, and components with respect to degree of importance to safety and appropriately grading quality assurance procedures.
Mr. Conran noted that conversationally, the Staff tends to use the terms, safety grade, safety related, and important to safety interchangeably a great deal. The terms do however have considerably different meanings in the regulations anc' regulatory guidance. The Staff's objective at the meet-ing was to discuss the two terms that the Staff has defined in the course of the TMI-1 restart hearing that is, safety grade and important to safety, and ask for Committee comments, if any, or concurrence if the Committee sees nothing wrong with the way the terms are defined. Mr. Conran noted the Staff has not arrived at a single definition of the term " safety related."
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[ Note: Subsequent to the meeting, NRR/OSD/ ELD have reached agreement on a l
single definition of " safety relater which equates it to " safety grade".3 Mr. Bender noted that most equipment at a nuclear power plant has some j
I relationship to safety.
It is tile type of relationship that must be ad-l dressed. Mr. Bender suggested that there is a need to establish how to f
discriminate between safety relationships that require certain kinds" of t
engineering provisions, special design treatment, or possibly operational treatment that is different from what would occur under conventional practice.
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PLANT FEATURES IMPORTANT February 3,1981 TO SAFETY Mr. Conran noted that the Rogovin study had said:
"The NRC lacks definitions for safety-related as applied to equipment, systems, structures, and so forth necessary to ensure that Appendix B Quality. Assurance standards are implemented consistently.
The consequence has been an ad hoc uncontrolled application of safety-related requirements to equipment outside the reactor protection system and engineered safety features systems." This problem was addressed in the NRC Action Plan in Section I.F.
The approach is to expand the "Q" list to cover all equipment important to safety, not just structures,, components, or A second cspect of the plan is systers used t,o prevent or mitigate accidents.
to rank equipmer.t in order of its 'importance to safety. There are preliminary steps underway toward developing a graded quality assurance program.
Mr. Conran noted that the term, "important to safety" encompasses the broad class of plant features, covered (not necessarily explicitly) in the General Design Critera, that contribute in important ways to the safe ops.ation and the protection of the public in all phases and aspects of facility operation (i.e., normal operation and transient control, as well as accident prevention and mitigation),
Mr. Haass explained that the Quality Assurance Branch uses the term, " safety i
related" to describe those items on the Q-list. Those items on the Q-list include items considered safety-grade (seismic Category 1) plus other systems considered important to safety such as radioactive waste systems and fire Licensees are free to include such additional items on protection systems.
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PLANT FEATURES IMPORTANT February 3,1981 TO SAFETY the list, even if the Staff doesn't consider the additional systems required for the critical safety functions identified in 10 CFR 100 Appendix A and Regulatory Guide 1.29.
In general, the Q-list for each plant is composed on a case-by-case basis.
Mr. Bender suggested that in setting quality assurance requirements, consid-eration should be given to a piece of equipment's purpose and the conditions under which it must operate.
The Staff suggested in discussing the term, "important to safety" that there is a relationship to the consequences to the plant given a particular com-ponent fails.
The more severe the consequences of a component's failure the more the assurance needed to lower the probability of the component failing.
Since the accident at TMI-2, the Staff noted that the list of safety grade equipment has not been expanded. However, there have been upgrades to the reliability of components important to safety such as the power supply to the pressurizer heaters and PORV position indication; components involved in such upgrading have been added to the "Q" list.
Mr. Bender suggested a set of definitions as follows:
- Importance to safety is a measure of the consequences of failure. -
- Safety grade is a measure of quality needed to serve a safety function.-
Safety related refers to the conditions under which the safety function is to be performed.
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PLANT FEATURES IMPORTANT February 3, 1981 TO SAf.TY
[Following the meeting, the Staff has commented that this is a sensible approach and preferable semantically (from the viewpoint cf common sense usage of the terms) to the set of definitions currently in use.
However, the Staff stressed the fact that the main drawback in going to such a set of definitions in the short term is the enormous amount of editorial effort required to incorporate these definitions into existing standard review plans and regulatory guides.
The set of definitions presented in James Conran's TMI-1 testimony have been established by practice and would not require significa.it editorial iffort.]
Mr. Haass explained that the Quality Assurance Branch for the purposes of 10 CFR 50, Appendix B. applicability separates plant structures, systems, and componen*s into two groups - "important to safety" and its subgroup.
" safety related." The safety related grouping contains those structures, systems, and components needed to prevent or mitigate the conseq'uences of postulated accidents as defined by 10 CFR 50, Appendix B and Regulatory Guide 1.29. QA controls satisfy Appendix B and it is requin!d that they be applied in a manner consistent with an item's importance to safety as stated in Criterion 2 of Appendix B.
Items important to safety are those remaining structures, systems, and components in the plant that have some effect on safety (needed to provide reasonable assurance that the facility can be i
l operated without undue risk. Quality assurance controls satis,fy General Design Criterion 1 of Appendix A (the Staff has not developed detailed requirements for such a QA program).
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Febru y 3, 1981 a
PLANT FEATURES IMPORTAhT -
TO SAFETY Mr. Haass noted that the Staff is proposing for the future to clarify the The applicability of 10 CFR 50, Appendix B to all items important to safety.
basis for this action is derived from Appendix A to 10 CFR 50.
Currently, the Staff does not have such a list. The TMI Action Plan describes such a list.
The Staff has issued a position to TMI-1, Zion 112, and Indian Point 213 to develop an expanded Q-list to include al' teuctures, systers, and components The Staff has commented since the meeting that they do important to safety.
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have the basis for such a list.
It would include structures, systems, and components identified explicitly in the General Design Criteria, the Standard Review Plans, and Regulatory Guides.
Mr. Gallagher, who chairs an ad hoc group that was established through a joint agreement with the NRC Office of of Standards Development and the IEEE, made a brief cresentation. The scope of this group (IEEE P827) is to prepare a document that ets criteria for determining the level of importance to safety of the instrumentation, control, and electrical portions of nuclear power Methods are provided generating station systems not covered by IEEE Std. 603.
for determining the design basis for each of these systems and for determining the degree of applicability of the requirements of other standards to each of This determination is based on the level of importance to thesa systems.
safety of each system.
The purpose of the document to be prepared by the group is to present a uniform classification approach for determining the applicability of design criteria and design requirements for nuclear power generating station systems, based on the level of their importance to safety.
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FLANT FEATURES IMPORTANT February 3, 1981 TO SAFETY The basic thought was to develop a graded approach.
In this light, requirements already in place could be judged for applicability, in some cases restrictions could be relaxed if safety functions were not as important with respect to the consequences of failure.
Mr. Medeiros from the NRC Office of Standards Development made a statement.
He said it was his opinion that there is a lack of technical excellence in the area of plant control. He was also disturbed at the level of review for instrumentation and control equipment. He noted control room' design needs attention.
The meeting was adjourned at 4:45 p.m.
For additional details, a complete transcript of the meeting is available NOTE:
in the NRC Public Document Room, 1717 H St., NW, Washington, DC 20555 or from Alderson Reporters, 300 7th St., SW, Washington, DC, (202) 554-2345.
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19,1981/ N: tic:s Fedird Regist:r / Vol. 46. ko.12 / Mondiy, January 5108 operation er licensing activities may be ap; Further information regarding topics discussed following this session.
to 4 the NRC Draft Long-Range Research to be discussed. whether the meeting Persons wishing to submit written me Further information regarding topics his been cancelled or rescheduled. the statements regarding Regulatory Guides
wt to be discussed. whether the meeting opportunity to present oral statements and Regulatory Guide 1.136. Revision 2.
g has been cancelled or rescheduled, the and the tirne allotted therefor can be may do so by providing a readilY be Chainnen's ruling on requesta for the obtained by a prepaid telephone call to reproducible copy to the Subcommittee M
opportunity to present oral statements
! the cognizant Designated Federal at the beg +nning of the meeting..
Un and the time allotted therefor can be obtained by a prepaid telephone call to ' Empicyee. Mr. Paul Boehnert (telephone However, to insure that adequate time is the cognizant Designated Federal
=02/634-32671 between 8;15 san. and available for full consideration of these I
Employee. Mr. Sam Duraiswamy 540 pan, EST.
comments at the meeting. it is desirable me (telephone 200/634-3267) be* ween 4:15 D%emary tem to send a readily reproducible copy of an-a.m. and 500 pan EST.
John Gods' the commenta as far In advance of the ri Dueg aty 14.19et.
Advisory Committee Management Cficar.
meeting as practicable to Mt. Sem e
Duraiswamy, the Designated Federal co*
In on si-m m i-met " *l gyg&ymywwg y
Advisory Committee Mancgement W,.
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AD" * " * '-**'" "I Washmgton. DC 20555 or telecepy them prt l
Committee on Reactor to the Designated Federal Employee w-Advi**U th-
[200/634-3319) as far in advance of the Nt A i t es meeting as practicable. Such cemments pe Advisory Committee on Reactor
---.The ACRS Scbcommittee on and avadable for public Inspection at Safeguards, Subcommittee organg shall be based upon documents on file i
to Festures Imoe" ant m sa'ev Weeting Regulatory Activities will hold a the NRC Public Document Room.171? H ha The ACRS Subcommittee on Plant meeting on Fa' -"-v i "W in Room Features Important to Safety wul hold a 1048. In7 N Street. N.W. Washington, Street. N.W, Washington. DC 20533.
CF Further information about topics to be o-mteting at 1-00 pm on Fa'wuary 1198L DC. Notice of this meeting was discussed. whether the meeting has J
in Room 1157. in7 H Saeet, d.n,,
published December 22.19W.
been cancelled or rescheduled. the oi Washington. DC to beg:n d2scussion of In accordance with the procedures Chairman's ruling on requesta for the th the NRC definitions of plant features.
' outlined in the Federal Register on opportunity to present oral statements i
v important to safety and related critena October 7,1980 (45 FR 66535), oral or and the time allotted therefor can be for such systems developed by the NRC l written statements may be presented by obtained by a prepaid telephone call to 5:
Staff in connection with the n0-1 l members of the public. recordings will the ccgnizant Designated Fed.eral restart dw.
t be permitted only during those portions Employee. Mr. Sam Duraiswamy.
In 1ccordance wM the pmcedures l of the meeting when a transcript is being (telephone 202/634-3267) between 8:15 kept, and questions may be asked only be* 19 {5 5
a or b
f the Subcommittee.its a.m. and 5.00 pm.EST.
w :tten statements may be presented by,; by mem ers oconsultants, and StaH. Persons desir6g Dated January 14. iset.
,{
mmbers of the public. recordings wil!
- to make oral statements should notify te John C. Hoyle, e
Advisory Comaunee Menegement Oficer.
of the meeting when a transcript is being ; Designated Federal Employee as far in be permitted only during those portions j advance se practicable so that p o,,,,.1,,,g,,,_- g I
kept, and questions may be asked only ! appmpriate arrangements can k made onuss cosa resses.es C
by members of the Subcommittee.its
- to allow the necessary time during the E
consultants. and Staff. Persons desiring ] meeting for such statements.
Advisory Committee on Reactor j
to make oral statements should notify The entire meeting wul be open to Safeguarda, Subcommittee on Safety the Designated Federal Employee as far public attendance.
in advance as practicable so that The agenda for subject meeting shall pe*echy. Teenetecy mad Criteria; t
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appropriate arrangements can be made l( be as foHows:
I The ACRS Subcommittee on Safety to allow the necessary time during the 7besday, febetrary11961 Philosophy. Technology and Cnteria meeting for such statements.
f The entire meeting will be opt.to p & mu% w2H commence atihm.
wdlhold a meeting at 300 pm on E
The agenda for subject meeting shall ! The Subcommittee willhear F6v 4 19U in Room 1048.1717 H pub!ic attendance.
7 l presentations from the NRC Staff and btreet. N.W, W ashington. DC to discuss be as follows:
wdl hold discussions with this group requirements for new Near-Term j
Construction Permit reactor plants.
Tuesday. february l 1961 pertinent to the foUowing-In accordance with the procedures 140p.m. until the conclusion of busm, eas,r (1) Regulatory Guide (Task No.RS outlined in the Federal Register on 7c5-4). "I.Jghtning Protection for Nuclear October 7.1980 (45 FR 66535), oral or During the initial pertion of the Power P! ants"(Post comment).
written statements may be presented by meeting. the ~ubcommittee, along with (2) Regulatery Guide 1.138. Revision 2, members of the public, recordings will l
any of its consultants who may be
" Materials. Construction and Testing of present, will exchange preliminary Concrete Containments"(Post be permitted only during those portions views regstding matters to be of the meeting when a transcriptis being considered dunng the balance of the comment).
kut, and questions may be asked only (3) Regulatory Guide (Task No. SC I
meeting.
705-4). t:ltrasonic Testing of Reactor by members of the Subcommittee,its ne Subcommittee will then hear Vessel Weids During Pre-Service and constltants, and Stnff. persons desiring presentations by and hold discussions Inservice Exacdnation"(Post comment). to make oral statements should notify with representatives of the NRC StaiT. '
Other matters which may be of a the Designated Federal Employee as far their consultants, and other interested in advance as practicable 30 that predecisional nature relevant to reactor
. persons regarding this review,
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1/26/81 ACR5 5US OdETTEE rEETING ON PLANT FEATURES Iw.700. TANT R00 1157,1717 H St., W, WASHINGTON, DC FEBRUARY 3, 1981 TENTATIVE SCHEDULE AP:ROXIFATE TIME I.
ODENING REMA?XS 1:00 p Discussion of Schedule a.
b.
Goals for the Meeting II. BACKGROU*C DISCUSSION i
1:15 p 1MI-1 Restart Hearing a.
b.
Defintion of Tems:
1.
important to safety - safety related
- 11. safety grade
'Jhere are these tems defined?
What is the purpose / scope of these definitions?
c.
d.
III. T0FICS FO?. DISCU5510N 2:00 p Is the list of ite s defined as " safety-grade" given in Req. Guide 1.29 an adequate list?
a.
Does it require additions / deletions?
i W.C argues in testimony that improper operator b.
action towards safety systems resulted in re-What liance on non-safety systems at TMI-2.
is the implications of this line of reasoning concerning such topics as operator action (before or after 10 minutes into an incident) to mitigate or end a transient?
What is the relaticeship between definitions of safety terms and Quality Assurance (QA) c.
requirements, Should the NRC or Industry develop a graded d.
QA approach using multiple tiers of QA categories depending on the safety importance l
of the equipnent?
- i. How would such graded QA schemes be ci ssified?
What classification should be given I
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to systtes that could be used to mitigate accidents in lieu of a safety system?
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2 PPR011MP E TIME iii. What classification should be given to systens d ose failure or misuse could challenge a safety system?
How does systems interaction fit in?
How would the creation of a quantitative e.
safety goal effect the distinction between various p1 ant systems?
SUMMATION - Briefly dat the Subcorr.ittee intends IV.
4:00 p to report to the full ACRS.. Need for future discussion.
ADJOURNMENT 4: 15 o c
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ENCLOSURE 1 ATTENDANCE LIST OF THE ACRS SUBCOMMITTEE MEETING ON PLANT FEATURES IMPORTANT TO SAFETY FEBRUARY 3, 1981 1717 H ST., NW, WASHINGTM, DC ACRS DOE D. Ward, Chairman P. Davis M. Bender, Member E. Epler, Consultant EPRI R. Major, ACRS Staff R. Leyse NRC STAFF J. Stolz, NRR WESTINGHOUSE J. Conran, NRR W. Haass, NRR J. Spraul, NRR J. Gallagher T. Dunning, NRR H. Levin, DE ALDERSON REPORTERS E. Rossi. NRR H. Ornstein, AEOD P. Minson M. Medieros, SD E. Davidson, RES S. Clinkson W. Morrison, SD
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LIST OF DOCUMENTS AND SLIDES PROVIDED AT MEETING 1.
Tentative Meeting Schedule Background Slides by J. Conran, NRR Defintion of Terms (10 Slides) 2.
Slide used by(W. Haass, Quality Assurance Branch - Quality Assuranc 3.
Requirements 1 Slide)
Slides used by John Gallagher (IEEE)
IEEE P827 Criterion for Determining 4.
Requirements for Systems Important to Safety (7 Slides)
LIST OF 00CtMEkiS PROVIDED SUBSEQUENT TO MEETING 5.
Memorandum fcr H. Denton from D. Ross,
Subject:
Non-Concrrence on Proposed Anendment to 10 CFR 50 Appendix A to Clarify Quality Assurance Program Requirements (Attached)
IEEE Trial Use Ca:de: A Method for Determining Requirements for Instru-6.
mentation, Control and Electrical Systems and Equipment Important to Safety (Distributed to 53) committee on February 23,1981)
These documents were filed with the Office Copy of tnese Minutes.
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5108 cperati:n erlicensing activities m::y be Further information regarding t: pics discussed following this session.
to i
. the NRC Draft Long. Range Research to be discussed, whether the meeting Persons wishing to submit written 1
me.
has been cancelled or rescheduled. the statements regardmg Regu! story Guides eut Plan.
Furt'rer information regarding topics Chairman'a ruhng on requesta for the with Task numbers RS 705-4. SC 70*>4.
- 1 to be discussed. whether the meeting opportunity to present oral statements and Regalatory Guide 1.136. Revision 2.
hss ban canceUed or rescheduled, the and the time allotted therefor can be may do so by providing a readily bc-Chairman's ruling on requests for the obtained by a prepaid telephene call to reproducible copy to the Subcommittee M
r cpportunity to / resent oral statements the cognizant Designated Federal at the beginning of the meeting.
Un-cnd the tirne a!!otted 'herefor can be Em;icyee. Mr. Paul Boehnert (telephone However, to insure that adequeto time is t
obtained by a prepaid telephone call to 202!6>3267) between 8.15 a.m. and available for fu!! consideration of these the cognizant Designated Federal 5.00 p.m EST.
co-ments at the meeting, it is desirable me a readily reproducible copy of an3 Employee. Mr. Sam Duraiswamy Ded Imary 1(1 set.
t (teie; hone 202/634-3267) between 8.15 Pk' s.m. and $40 p.m EST.
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m gnag pm pn ngt n.DC 20555 or telecopy them A D= ss-mn N s-i+Ce =1
' Advisory Committee on Reactee to the Designated Federal Employee the wie as Safeguards. Subcommittee on (202/6343319) as far in advance of the pe:
Requfatory Activities; Meeting meeting as practicable. Such commenta l
shall be based upon documents on file dvisory Committee on Reactof A
to afsguards, Subcommittee o@
The ACRS Subcommittee on an;l available for public inspection at ha Sestures impe&t to Weh: Meeting Regulatory Actrvities wd! hold t the NRC Public Document Room.1717 H Ch F
The ACRS Subcommittee onPlant meeting on 8%' ~"v i W* in Room Street. N.W, Washington. DC 20535.
eatures Important to Safety will hold a 1046,1717 }{ Street N.W., Washington.
Further information about topics to be op an eeting at 1:00 p.m. on Meuarv 3.1981 DC. Notice of this meeting was discussed. whether the meeting has ob F
published December 22.1980.
been canceHed or rescheduled, the mm Room 1167.1717 H SItreet. N.6, th.
In accordance with the procedures Chairman's ruling on requests for the Washington. DC to begin discussion of outlined in the Federal Register on opportunity to present oral statements En he NRC definitions of plant features
, October 7.1980 (45 FR 66535), oral er and the time aDotted therefor can be y
t tmportant to safety and related criteria
! written statements may be presented byobtained by a prepaid telephone call to g
for such systems developed by the NRC Staff m cormection with the ThC-1 members of the public, recordings will the cognizant Des:gnated Federal be permitted only during those portions E=p!cyee. Mr. Sam Dura!swamy.
l acfordaIce with the precedures of the meeting when a transcript is being (telephone 202/634-3267) between 8:15
- kept. and questions may be asked only a.m. and 5.00 p.m EST.
F' by members of the Subcommittee.its Dated:!anuary to test.
cb 71 0 5 51 a or wntten statements may be presented by, c nsultants. and Staff. Persons desiring l to ma r
members of the public. recordings wi!I I Designated Federal Employee as far in Advisory Committee Menegement Micer.
be permitted only during those portions Si advance se practicable so that p %,, %,,,,
of the meeting when a tr:nscript is being Ct i appropriate arrangements can be made m ano, mg f
kept, and questions may be asked only by members of the Subcommittee.Its
, to aUow the necessary time during the j meeting for such statements.The entire meeting wdlbe open to' Advfoory Committee on Reseter consultants, and Staff. Persons desiring Safeguards. Subcommittee on Safety to make oral statements should notify public attendance.
eohv. Te*efoey s4 Criterta; g
the Designated Federal Employee as far in advance sa practicable so that ne agenda for subject meeting shah
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D appropriate. rangements can be made be as foHows-
_The ACRS Subcommittee on Safety to allow the necessary time during the Tuesday, Februory11982 Philosophy. Technology and Criteria e
meeting for such statements.
WII ence W h wn! hc!d a meeting at 3 00 p m. on E
The entire meeting wd! be open t F&nev 4 3er in Room 1046.1717 H e
F ne Subcommittee wi!! hear itreet. N.W., w ashington. DC to discuss public attendance.The agenda for subject meeQ:s shall presentations from the NRC Staff and - requirements for new Near. Term I
f be as foUows:
- iU hcid discussions with this group Construction Permit teactor plants.
1 pertment to the following' In accordance with the procedures Tuesday. februcry J. 2981 s
(1) Regulatory Guide (Task No. RS outlined in the Federal Register on Imp.m. until13e conclusion of busm, ess 705-4). "Ughtning Protection for Nuclear October 7,1980 (45 FR 66535). oral or During the initial portion of the Power Plants"(Post commentJ.
written statements may be presented by i
meeting. the Subcommittee, along with (2) Regulatory Guide 1.136. Revision 1 members of the public, recordings will any of its consultants who may be
" Materials. Construction and Testing of be permitted only during those portions present. wdl exchange preliminary Concrete Containments'(Post of the meeting when a transcript is being views regarding matters to be comment).
kept. and questions may be asked only considered dursng the ba!ance of the (3) Regulatory Guide (Task No. SC by members of the Subcommittee. Its 705-4)."tutrasonic Testing of Reactor conscitants, and Staff. Persons desiring meeting' bcommittee will then hear The Su VesselWe!ds During Fre. Service and to make oral statements should notify presentations by and hold discussions Inservice Examination" (Post cocument). the Designated Federal Employee se far with repreaentatives of the NRC StafI Other matters which may be of a In advance as practicable so that their consu. ants. and other ir*ee*%i predecisional nature relevant to reactor persons regarding this review.
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TTEE MEETING Off Pi. ANT FEATURES IMP 3: TANT TO ACP.5 S'3 CMM:
RODY 1167, 1717 H St., NW, WASHINI*0N, DC FE5RUARY 3,1951 TENTATIVE SCHEDU' {
Ae:ttt'K'TE TINE I.
00ENING REMARKS 1:00 p Discussion of Schedule a.
b.
Goals for the Meeting II. BACK32.03NO DISCUSSION 1:15 p THI-1 Restart Hearing a.
b.
Defintion of Terns:
important to safety -- safety related 1.
ii. safety grade Where hre these terms defined?
What is the purpose / scope of these definitions?
c.
d.
III. TOPICS FOR DISCUS $10N 2:00 p Is the list of items defined as " safety-grade" given in Reg. Guide 1.29 an adequate list?
a.
Does it require additions / deletions?
NRC argues in testimony that improper operator action towards safety systems resulted in re-b.
What liance on non-safety systems at TMI-2.
is the implications of this line of reasoning concerning such topics as operator action (before or after 10 minutes is:to an inciden to mitigate or end a transient?
What is the relationship between definitions of safety terms and Quality Assurance (QA) c.
requi rements.
Should the NRC or Industry develop a graded QA approach using multiple tiers of QA d.
categories depending on the safety importance of the equipnent?
How would such graded QA schemes i.
be classified?
What classification should be given 11.
to systees that could be used to w tigate accidents in lieu of a safety system?
Z.
N P.07.IM1 E T!4 What classification should be given iii.
to systems whose failure or misuse could challenge a safety systen?
How does systems interaction fit in?
How would the creation of a quantitative safety goal effect the distinction between e.
various plant systems?
SUMMATION - Briefly what the Subcomittee intends to report to the full ACR5. - Need for future IV.
4:00 p discussion.
ADJOURMENT 4:15 p 0
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ATTENDANCE LIST 0F THE ACRS SUSCCeci1TTEE MEETIN3 0'i PLANT FEATURES IMPORTANT TO SAFETY p
FEBRUARY 3, 1981 1717 H ST., NW, WASHINGTON, DC g
DOE ACRS P. Davis D. Ward, Chairman M. Bender, Member E. Epler, Consaltant EPRI R. Major, ACRS Staff R. Leyse NRC STAFF J. Stolz, NRR RESTIN F OUSE J. Conran, NRR W. Haass, NRR J. Gallagher J. Spraul, NRR T. Dunning, NRR H. Levin, DE ALDERSON REPCRTERS E. Rossi, NP.R H. Ornstein, AIOD P. Minson M. Medieros. SD
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