ML20133K364
| ML20133K364 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 07/11/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2298, NUDOCS 8510210227 | |
| Download: ML20133K364 (13) | |
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DATE ISSUED: July 11, 1985 MINUTES OF THE MARCH 27, 28, AND 29, 1985 COMBINED MEETING OF TPE ACRS SUBCOMMITTEES ON GESSAR II, RELIABILITY AND PROBABILISTIC ASSESSMENT, AND SAFEGUARDS AND SECURITY ALBUQUERQUE, NEW MEXICO A meeting was held by the ACRS Subconinittees on GESSAR II, Reliability and Probabilistic Assessment and Safeguards and Security on March 27, 28, and 29, 1985 at Sandia Laboratory, Albuquerque, New Mexico. The purpose of this meeting was to continue Subcommittee review of GESSAR II for a Final Design Approval applicable to future plants. The focus of this meeting was on plant security, discussions on value-impact studies regarding mitigation devices and further review of the PRA performed for GESSAR II. Notice of this meeting was published in the Federal Register on March 4, 1985 (Attachment A).
Portions of the meeting which dealt with plant security and General Electric Company (GE) Proprietary information were closed to public attendance. Richard Major was the cognizant staff member for this meeting.
Participants ACRS ACRS Staff Sandia D. Okrent, Co-Chairman C. Thomas S. Hatch C. Mark, Co-Chairman D. Scaletti J. Hickman C. Michelson, Member B. Hardin D. Ericson H. Etherington, Memt,er M. Rubin J. Ebersole, Member M. Carbon, Member C. Wylie, Member A. Camp, Consultant 8510210227 850711 M. Bohn, Consultant
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Summary / Minutes March 27, 1985 2~
MTGS. GESSAR II/RPA & SS General Electric Brookhaven National Lab.
J. Fox K. Shiu D. Foreman R. Villa W. Gilbert J. Maxwell D. Hawkins B. Gou March 27, 1985 The first day of the meeting dealt with plant security considerations.
The entire meeting was closed to the public.
Dr. Mark chaired the security session.
The Subcommittee noted that as they review GESSAR II they could be j
approving a plant which could be operating, fifty years or more into the j
futura. Consideration of possible cond.itions which might be found in the world fifty years hence should have an influence on the design of i
I security measures for GESSAR II in the present review.
Dr. David Ericson, Sandia, presented a review of LWR Sabotage studies.
Included in his presentation were nuclear power plant design concepts, i
damage control for sabotage mitigation, components vulnerability and design changes, insider protection, and BWR insights.
Plant design i
alternatives which can increase a plant's resistance to sabotage were
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reviewed.
i Mr. W. Gilbert of General Electric Company discussed GESSAR II sabotage considerations. GESSAR II is designed to meet regulatory requirements.
GESSAR II also has protection features including: access control, equipment design and layout, damage control, and sabotage mitigation.
It was noted that only access control has a solely safeguards function.
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The other features which contribute to sabotage protection have addi-j tional reasons for being included in the plant design.
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Sumary/ Minutes March 27, 1985 3
MTGS.-GESSAR II/RPA & SS i
Currently requirements for protection against radiological sabotage include: vital equipment located behind two physical barriers, con-I trolled access, and a control room that is bullet resistant. Currently.
GE does not feel additional measures for plant security are warranted l
until required by the NRC.
f The NRC Staff explained that they monitor the intelligence comunity for any threat to nuclear plants.
If the Staff feels there is a threat to a plant, they can and will take immediate actions to counter the threat.
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The Subcomittee suggested additional consideration be given to the types of strategies that could be used for sabotage protection. The use j
i of bunkering and hardening plant equipment was discussed..The contribution UPPS could make to sabotage mitigation was questioned since l
design details for the system have yet to be produced.
l The Subcomittee also discussed security system interface parameters for
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the GESSAR II plant.
Interface parameters supplied to the applicant l
were reviewed. These interface items include ingress points, personnel 4
t and material traffic routes, and the GESSAR II communications system design.
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General Electric noted that for the GESSAR'II design, there are five self-sufficient heat-removal systems in five security areas. Equipment l
separation provides added protection against sabotage.
March 28, 1985:
i The Staff discussed-the current status of the severe accident policy statement. Currently the staff would be willing to issue an FDA for a future design which meets the standard review plan and has considered severe accidents in a PRA. GESSAR II would be in this position after the severe' accident policy is finalized. However, no C.P. or 0.L. would be issued to a plant referencing the GESSAR II design until the com-i pletion of the Staff and ACRS review.
Following Staff and ACRS approval I
the Staff's current thinking is that the FDA would be valid for 5 years.
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Summary / Minutes March 27, 1985 4
MTGS. GESSAR II/RPA & SS Design Certification would be valid for 10 years; this step requires rulemaking to approve the design. GE has indicated they would not pursue certification. They are seeking the 5 year FDA.
Both GE and independently the Staff and their. consultant have evaluated a comprehensive list of design modifications. GE's evaluation of the 80 plus items is contained in NEDE-30640. The results of the Staff and their consultant (RDA) review are contained in NUREG/CR documents.
Currently the Comission's policy regarding standardization allows an FDA applicant to define the scope of a new design.
It requires those applicants whose scope of design is less than a complete plant to define the interfaces between the design and the balance of plant. The Staff's review assures the adequacy of interface requirements, and if necessary will identify other items which they believe to be important to safety.
Mr. Jack Fox of GE presented an update on the status of the Ultimate Plant Protection System (UPPS). GE has comitted to provide UPPS on the GESSAR II design Currently the design is in the conceptual phase.
Design details will be deferred until the first applicant references GESSAR II.
It is predicted that UPPS will reduce the overall risk of core damage by a factor of 10.
GE was questioned about a scenario where the reactor core was without water for an extended period of time. When water became available again, should it be used to flood the core? GE believes they have some documentation which leads to the conclusion to always add water to the core. The Staff believes this question is being addressed in the severe accident research program. Dr. Okrent requested the documentation that addresses this issue.
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Dr. Shiu of BNL noted that the Staff had asked BNL to explore the potential benefits of the UPPS system. The look was limited to the conceptual design GE has produced for the system.
Refinements in the i
UPPS design could alter the BNL results. BNL believes an automated i
Category I system gives a greater reduction in core melt frequency (a
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Summary /Minutos March 27, 1985 5
1 MTGS. GESSAR II/RPA & SS factor of 3) than an operator activated non-seismically designed system which adds little reduction to the frequency of core damage.
Dr. Kastenberg, RDA, discussed value/ impact issues relating to mitiga-tion devices.
He explained both RDA and GE use the ratio method of measuring value/ impact which examines person-rem averted divided by system cost. Occasionally the inverse of this ratio is also used.
Differences between GE and RDA on cost estimates can be accounted for by the fact that the RDA value/ impact calculations do not include property cost or use, the costs associated with using nuclear grade material, or the cost of construction financing among others. By adding the costs RDA had previously excluded, RDA and GE estimates of items such as large chilled filter systems more closely agree.
RDA calculated benefit by adding the risk reduction per year contributed by a particular feature and added it over an assumed 40 year plant life.
No discounting of health effects was used. A levelized cost is used which takes the cost of an accident times the frequency times the life of the plant. The effect of discounting the cost of improvements with a discount rate up to 10 per cent would lower the cost of making an improvement by a factor of three to six.
RDA does not believe discount-ing should be used when screening possible improvements and in dealing with health effects.
RDA has recommended the Staff not use discounting.
D. Kunsman of Sandia Laboratories reportea on preliminary work that has been done on Grand Gulf an operating Mark III, BWR-6 plant. The work is entitled severe accident risk rebaselining and risk reduction program.
A report on this work is scheduled to be released this summer. The program will evaluate benefits and costs of various safety options, considering the cost of reactor accidents and the cost of safety options. This report will consider both onsite as well as offsite costs of an accident.
It is felt that large financial risk is dominated by on-site cost and not off-site cost. The uncertainty band is potentially greater for off-site costs than it is for total costs.
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Summary / Minutes March 27, 1985 6
MTGS. GESSAR II/RPA & SS In closed session Mr. Knecht of GE presented a summary of GE's Value/ Impact analysis and basis. GE believes their approach is more realistic than RDAs and accounts for more benefits. Among approach differences in analytical methods between GE and the Staff are: GE discounts health effects, gives more credit for pool scrubbing, and uses risk reduction factors. Value benefits GE claims include reduced off-site costs and reduced utility losses which are due in large part to the effects of pool scrubbing. GESSAR was compared to a list of 73 possible design improvement concepts, 23 were already in the GESSAR II design. Three concepts had cost benefit ratios below 5.
These three concepts were ten hour station blackout provisions, the ultimate plant protection system and improved maintenance procedures.
GE noted there are not containment performance-criteria for severe accidents.
It was also felt to be reasonable not to assume safety grade equipment in determining costs of design improvements. Dr. Okrent 3
suggested that based on the PRA, thought be given to containment perfor-mance criteria.
Dr. Hankins, GE, discussed some of the limitations and uncertainties associated with the PRA. Accident initiators with frequencies less than 10-8 are considered insignificant contributors to core damage frequency and risk. Some limitations and uncertainties include the fact that sabotage is treated deterministically. Sensitivity studies have showed only a small effect associated with considering a range of plant sites.
Regarding design and construction error's adequate methodology to include these effects in the PRA is non-existent. The PRA has no basemat penetration failure mode; the aim is to maximize airborne releases.
Human error is treated according to guidance in the " Handbook of Human Reliability Analyses" A.D. Swain /H.E. Guttman.
Mr. Michelson requested a copy of an analysis of an ex-containment LOCA for the reactor water cleanup system. Mr. Michelson is concerned over a scenario where the isolation valves in the system fail to close.
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MTGS. GESSAR II/RPA & SS Mr. Maxwell, GE, made a presentation on the external events of floods and fires.
F. ire protection equipment is part of GE's scope of suppl for the nuclear plant. GE calculated a frequency of core damage of
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,s acceptable. The adequacy of the design was confinned by a fire-hazard analysis on a room _by room basis.
Regarding floods, GE has performed studies to confirm that floods are confined to the area of initiation and the consequences of internal floods are acceptable. GE concludes thehighestprobabilityofcoredamageduetofloodingisf3 which is acceptable.
Friday, March 29, 1985 Mr. Etherington was also concerned that high probability low impact events would equal low probability of occurrence high health impact events in a value impact analysis. GE noted the frequency of occurrence is taken into account and judgement is used in plant design. Mr.
Etherington felt some weighting for high probability events should be considered.
During the Subcommittee's introduction to the third day of the session, a brief discussion of the effect of economic loss to health took place.
A correlation between life expectancy and standard of living (which could increase with cheap electric power) would add perspective to value/ impact studies if such a relationship could be quantified.
Mr. Hardin of the NRC briefly reviewed the role of pool scrubbing for the subcommittee. He noted that pool scrubbing is considered in all accident scenarios except those involving a severe eaithquake. The Staff believes their estimates of decontamination factors (DFs) for GESSAR are conservative, however due to uncertainties in the particle size distribution, refinements in DFs have not been made.
Pool bypass situations under study include an RHR line break, a RCIC steamline break and bypass resulting from a severe earthquake.
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Summary / Minutes March 27, 1985 8
MTGS GESSAR II/RPA & SS In closed session ACRS consultant Mike Bohn discussed the results of his review of the General Electric GESSAR seismic risk assessment. He compared the GE analysis to the BNL (NRC Staff's consultant) analysis.
There is a factor of 200 difference between the results obtained by GE and the Staff.
Dr. Bohn accounts for the differences due to differences in assumptions that underlie each analysis. He noted that if GE had used the same fragility values BNL had used, the GE and BNL analyses would be nearly the same.
In the BNL analysis relay chatter contributes 51% of the total core damage frequency. Dr. Bohn felt this was conservative since it was assumed there was no time delay protection in the circuits; secondly it is assumed a momentary contact will lock the circuit; and no credit is taken for solid state devices which can probably undergo higher levels of acceleration without accidently energizing.
In closed session D. Knecht of GE presented a summary of GE's position on relay chatter. Sandia's expressed concern was that relay chatter causes a common mode failure. All ECCS systems would be lost and there would be insufficient time to reset trips. GE believes comon mode relay chatter effects are avoided by equipment diversity and ease of trip reset.
It was further noted the GESSAR II designs is basically solid state except for switchgear protective relays.
Dr. Bob Gou of General Electric made a presentation on seismic struc-tural fragilities. The main emphasis was on foundation fragilities, foundation sliding and rocking.
It was noted soft soil is excluded because of soil bearing capacity requirements.
The foundation _ sliding mode governs. However, GE claims foundation sliding does not cause simultaneous failure of the drywell, containment and shield building.
Relative displacement resulting from building sliding is very unlikely to fail all interconnecting piping. A core cooling avenue would remain.
Dr. Okrent discussed presentations for upcoming full ACRS meetings. He also noted that he expects to hold at least one more subcommittee meeting following the Staff's issuance of SSER-4.
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Summary / Minutes March 27, 1985 9
MTGS. GESSAR II/RPA & SS The meeting was adjourned at 12:07 p.m.
NOTE:
A transcript of the open portfors of the meeting is on file at the NRC Public Document Roem at 1717 H St., NW.,
Washington, D.C. or can be obtained at cost from ACE Federal Reporter, Inc., 444 N. Capitol St., Washington, D.C. 20001,
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r Federal Register / Vol. 50. No. 42 / Mor. day M:rch 4.'1985 / Notices mens ErracT;vt DATE: March 4.1965.
For the Board.
the cognizul ACRS sieff member Mr.
ron rumtm wronMAfto88 C00(TACT *.
Hartnert F. Ethagwood.
Elpidio E Igne (telephone 702/634-1;413) l Ada R. Kimsey. Office of the Clerk of Chairman.
be. wen 8.15 aan. 520 pan, ts.L the Board. Ment Systems Protection (FR Doc. 85-412o Filed 3-1-45; as5 am)
Tersons planning to attend ills amoeting are urged to contact the abois named j
Board. (202) 653-7200.
caos r w,,
Individual one or two days before the
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suret.tnetmar sesronuAT>osc With the publication of Volume 13. Decisions of scheduled meeting to be advised of any the UnitgdStates Merit Systems NUCLEAR REGULATORY changes in schedule, etc which may,
l Protection Board, covering the period COtfhilSSION have occurred.
Deted. February ze. teas.
Dnuary through March 1983 (see 49 FR Advisory Committee on Reactor Mortos W.therum.
49158), the Board cessed publication of SMeguarda Comtpined Extra o
I Board decisions volumes. Volume 1,2 its final orders and precedential External Phnomena, Structural Ass /stant Ex ecutne Direcsorfor Mo/ sci interlocutory orders Of the series of Enginee ing, and D6etplo Canyon; Open h'*
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(FR Doc. 45-41 4 %d 3-1-45,648 am)
Afeetings (October through December 1982) as
=m = come resse,.m l
will as Volume 13. is in print. Both may ne ACRS Subcommittees on Extreme y
be obtained from the Superintendent of Extemal Phenomena. Structural 4
g Documents ne ordering information is: Engineen'ng and Diablo Canyon will Adyteory Committee on Reector Vtlume 12; stock nurnber 06A'0Q-hold a combined meetm' g on March 21 Sofeguards Comtpined Sutpoemmittees a
00017-1. 316. and Volume 13. stock and 22,1965, at the Pacifica Hotel. 6161 en GESSAR li, Renatselit*, and c umber 062-00M0016-c. $11.
Centinels Avenue. Culver City. CA.
Prohebiustic Aseeeement and He Board continues to publish The ne entire meeting will be open to
' Safeguards and Securtty; Nottoe of Digest, a monthly summary and hating Public attendance.
Isoetings of opinions and orders. and 'Tederal ne agenda for the subject meeting Employee Appeals Decisions." quarterly shall be as foHows:
ne ACRS Subcommittees on microfiche with paper index ofinitial Thursday. March 21. Iss5-AM a.m.
CESSAR II. Reliability and Probabilistic,
decisions issued in its 11 regional unt;l the conclusion of business Assessment and Safeguards and offices. Further, the Board has published hiday. March 22.1985-dM a.m. until Security will hold a combined meeting a special microfiche edition of initial the mnclusion ofbusiness on March 27,28 and 29.1965, at the decisions resulting from the air traffic ne Subcommittees will discuss the Sandia National Laboratory.
oontroller strike of 1981: *Tederal status of the NRC Staff seismic design Albuquerque NM.
Employee Appeals Decisions. Air Traffic margins programs and PGaE's program To the extent practical the meeting i.
Controuer Cases."
plan for a seismic reevaluation of Diablo will be open to public attendanca.
L Meanwhile, researchers may contact Canyon.
However, portions of the meeting will be the following organizations which offer Oral statements may be presented by closed to discuss proprietary c variety of services regardmg Board members of the public with the information relating to the GESSAR P
decisions:
concurrence of the Subcommittee Probabilistic risk assessment and plant r.
Federal Merit Systems Reporter. labor Chairman; written statements will be security.
4 Relations Press.1725 K St NW.,
accepted and made available to the ne agenda for subject meeting shaU E
Washington. D C. 20006. (202) 833-Comnudee. Recordings will be permitted be as follows:
only d, those portions of the Wednesday, March 27, Jea5--Am o.m.
1122 F11TE (FederalInformation nrough muting w en a transcript is being kept, surtilthe conclusion ofbusiness Electronics).' HQUSAF/J AS. Denver
"" {uestions may be asked only by Dursday. March M. 2985-42 am.
1 CO 80279-5000. (303) 370-7531-
"'Iul n a untilthe conclusion ofbusiness con dt,
ns' sM
- 'W AlfrOVON. 926-7531 to make oral statements should notify mne usso'n 09us2 ness He Hawkins Ment Systems Protection the ACRS staff member named below as Board Service. Hawkins Pubbshing far in advance as is practicable so that ne Subcommittees will continue their
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Co Inc., Suite 220,933 N. Kevnore appropriate arrangements can be made.
review of GESSAR D for a Final Design SL Arlington. VA 22201. (703) 525-During the initial portion of the Approval applicable to future plants, l'
0000 meeting. the Subcommittee, along with and review design features for
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!.exis. Mead Data Central.1050 any ofits consu!'. ants who may be Protection against sabotage at Connecticut Ave., NW., Suite 1090.
present, may eTchange preliminary commercial nucles f power reactors.%e b;
Washington. D.C. 20036. (202) 785-views regardMg matters to be Principal topics to be discussed are U
4550 considered during the balance of the plant security and the GESSAR D and Merit Systems Protection Board Case meeting.
Probabilistic risk assessment.
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Service. Information Handling ne Subcommittee will then bear Oral statements may be presented by i
Services.1700 N. Moore St., Suite presentations by and hold discussions members of the public with the 3100. Arlington VA 22209. (703) 524-With representatives of the NRC Staff, concurrence of the Subcommittee I
its consultants, and other interested Chairman; written statements will be 9002 United States Merit Systems Protection Persons reganiing this rMem accepted and made available to the I*
Board Reporter. West Publishing Co Furth,er information regarding topics Committee. Recordin:,s will be permitted to be discussed. whether the meeting only during those portions of the k
P.O. Box 64528. St. Paul, MN 55164-has been cancelled or rescheduled. the meeting when a transcript is being kept.
9628.1-80 N 28-0352 h
Chairman's ruling on requests for the and questions may be asked only by A
pated. February as.1ses.
opportunity to present oral statements members of the Subcommittee.Its k-and the time al!otted therefor can be consultants, and Staff. Persons desiring l*
'rtire is mit.tae only in rednei sende, obtained by a prepaid telephone call to to make oral statements should notify I,
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Federal Regist:r / Vol 50. No. 42 / Mond y. Much 4.1985 / N:tices 3686 tiw ACRS rtaff member named below as the ACKS staff member naald bel w ce th) ACRS st:ff member named b f.iin connce as is practicable so that far in advance as is practicable ao that far in advance as is psacticable so that priate arrangements can be made appropriate arrangements can be made.
appropriate arrangements can be made.
During the tretial portion of the ng the initial portion of the During the initial portion of the ng. he Subcommittee, along with meeting. the Subcommittee along with meeting the Subcommittee, along with.
any cf its consultants who may b.e any,of its consultants who may be.
any of its consultants whe may be present, may exchange preliminary present, may exchange prelin'inary present. may exchange pre'.iminary views regtrding meters to be views regarding matters to be views regarding matters 9 be considered dunng the balance of the considered during the balanca of the considered during the balance of the meeting.
i ne Subcommittee will ther. hear The Subcommittee will then hear ne Subcommittee will then hear presentations by and hold discussions presentations by and hold discussions presentations by and hold discussions with representatives of the NRC Statf.
with representativs of the NRC Staff.
with representatives of the NRC Staff, its consult:nts, and other interested its consultants and other interested its consultanta. and other interested persons regarding this review.
persons regarding this review.
persons regarding this review.
Furthst information regarding topica Further information regarding topics Further information regarding topics p
to be discussed, whether the meeting to be discussed, whether the meeting to be discussed, whether the meeting v
has be:n cancelled or rescheduled, the has been cancelled or rescheduled, the hea been canceled or escheduled, the c
Chairman's ruling on requests for the Chairman's ruling on requests for the C.Mr' nan's ruling on requests for the y
opportunity to present oral statements opportunity to present oral statements opportuttity to present cral statements and th] time allotted therefor can be and the time allotted therefer can be and the time allotted therefor can be p;
obt:ined by a prepaid telephone call to obtained by a prepaid telephone call to obtained by a prepaid telephone call to w
the cognizant ACRS staff member. Mr.
the cognizant ACRS staff menber Mr.
the cognizant ACRS staff member. Mr.
ft.
Rich:rd Major (telephone 202/6M-1414)
M. D.Zeftawy (telephone 202/634-3267)
A. Wang (telephone 202/6M-3267) p, between 8.15 a.m. and 500 p.m e.s.t.
between 815 a m. and 500 p.m.. e.s.t.
between c:15 a.m. and 500 p.m.. e.a.t.
Persons planning to attend this meeting persons planning to attend this meeting Persons planning to attend this meetin8 to are urged to contact the above named are urged to contact the above named are urged to contact the above named ha individu:1 one of two days before the individual one or two days before the individual one or two days before the Cl acheduled meeting to be advised of any scheduled meeting to be advised of any scheduled meeting to be advised of any o
changes in schedule. etc., which may changes in schedule, etc., which may changes in schedule, etc which may a
have occurred.
have occurred-have occurred.
ob the Dated. F;btr ary 27,1985 Dated February 27.1985 DM February 27.198&
Rh Merton W.1/aarkan.
Morton W. Ubarkin.
Morton W. Ubarkin.
bet 1pL Earcuthe Direcsorfor Protea A ssisunt becutive Durecwrfor Project w g gg g g.yg,,,gy.,cw q,pp,jecg Nel NUe" R niew.
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(HL Doc. SMHrr Filed M-46, aL45 am) ind suase eren riswus anAsso coo "*""'
a u siacoes ris w us och cha hav Advlaory Commluee on Reactor Advisory Committee on Reacto' Advisory Committee on Reactor Safeguards Subcommittee on Safeguards Subcommittee on Class 9 Safeguarda Subcommittee on a
Doctrical Systems; Open Meeting Accidenta; Open Meeting Rollabl!!ty Assurance;Open Meeting ne,,
- Ass,
& ACRS Subcommittee on Dectrical b ACRS Subcommittee on Class 9 ACRS Subcommutu on 3,n Syst:ms will hold a meeting on March Accidents will hold a meeting on March Reliability Assurance will hold a 20.1985. Room 1(Mo 171711 Street. NW.
14.1985. Room 1046.1717 H Street. NW.
aus Washington. DC.
Washington. DC.
1717 H Street NW. Washington,DC.
Re entire meeting wiIl be open to N entire metting will be open to W enure muung wtllbe open to public attendance.
public attendance.
public attendance.
go.c W agenda for the subieet meeting W agenda for the subject meeting h agenda for the subject meeting shall be as follows-shall be as fo!!aws:
shall be as followa:
Miss Wedn:sday. March 20.19&S-8 M a.m Thursday. March H.1965-tmp.m.
Tuesday, March si 19ss--&M a m. until Tem untilthe conclusion of business until 7mp.m.
com the conclusion of busines, W Subcommittee will discus recent ne Subcommittee will discuss New NRC actions related to diesel generator York Power Authority's Source Testp.
De Subcommittee will begin its.
As a Co. M reli:bility.
studies.
investigation of salue reliability.
M ash Ord statements may be presented by Oral statements may be presented by Programs under way by various NRC IG'**
members of the public with the members of the public with the offices will be discussed. A presentation concurrence of the Subcommittee concurrence of the Subcommittee by industry on methods to enhance the g'
Chairtnan; written statements will be reliability of motor operated valves is i
Chairman; written statements will be accepted and made available to the accepted and made available to the anticipated. Re Subcommittee Will also d,,
9 Committee.jtecordings will be permitted Committee. Recordings will be permitted discuss several opertions! occurrences gem only during those portions of the onis d ' those portions of the that involved the failure of valves. It is th meeting when a transcript is being kept, meeting en a transcript is being kept, expected that the Subcommittee will plan its future activities.
g," d and qu:stions may be asked only by and questions may be asked only by members of the Subcommittee,its members of the Subcommittee.its Oral statements may be presented by
--(ultants, and Staff. Persons desiring consultants, and Staff. Persons desiring members of the public with the h"th*
ke oral statements should notify to make oral statements should notify concurrcaca of the Subcommittee.
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UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION
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,E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g
WASHINGTON, D. C. 20555 October 17, 1985 MEMORANDUM FOR: Jim McKnight Document Control Sys s
FROM:
Beverly Roberts Advisory Commit eactor Safeguards The attached ACRS Documents are being provi ed to you for listing on the accessions list.
Please forward to the Public Document Room.
' Attachments:
As Stated 1
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1 ACRS MEETING MINUTES AND CONSULTANT REPORTS CT-1819 Tien ltr 090985 to Boehnert, Comments on the ECCS Subcte Meeting i
held 082785 PDR 101785 CT-1820 Shepherd ltr 091085 to Savio, Comments on the Hydrogen Control for River Bend PDR 101785 i
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ACRS-2292 ACRS Subcte Meeting Minutes on Class 9 Accidents held 031485 POR 101785 h
ACRS-2298 ACRS Combined Subcte Meeting Minutes on GESSAR II, Reliability and Probabilistic Assessment, and Safeguards and Security held 0327-2985 l
PDR 101785 i
l ACRS-2312 ACRS Subcte Meeting Minutes on Safeguards and Security held 050785 PDR 101785 I
ACRS-2328 ACRS Combined Subcte Meeting Minutes on Waste Management and Site jl Evaluation held 0618-1985 PDR 101785 ACRS-2330' ACRS Subcte Meeting Minutes on Human Factors held 062085 PDR 101785 l
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l ACRS-2335 ACRS Subcte Meeting Minutes on A Long Range Plan for the NRC held 0710-1185 PDR 101785 ACRS-2336 ACRS 303rd Meeting Minutes held 0711-1385 PDR 101785 i
l ACRS-2340 ACRS Subcte Meeting Minutes on Reactor Radiological Effects held 073184 PDR 101.785 3
j ACRS-2342 ACRS Subcte Meeting Minutes on Class 9 Accidents held 080185 PDR 101785 ACRS-2343 ACRS Subcte Meeting Minutes on Class 9 Accidents held 080285 l
PDR 101785 ACRS-2348 ACRS Combined Subcte Meeting Minutes on ECCS/ Fluid Dynamics held j
080785 PDR 101785 I
ACRS Subcte Meeting Minutes on Human Factors held 0917-1885 ACRS-2354 PDR 101785 i