ML20062C643
| ML20062C643 | |
| Person / Time | |
|---|---|
| Issue date: | 04/05/1990 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2701, NUDOCS 9011020017 | |
| Download: ML20062C643 (49) | |
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TABLE OF CONTENTS MINUTES OF THE 360TH ACRS MEETING APRIL 5-7 AND 18-19, 1990 l
I.
Chairman's Report (Open)......................................
1 i
II.
Evolutionary Light Water Reactor Certification Issues (Open).
2 i
III.
NRC Regulatory Impact Survey (Open).........................
5 IV.
NRC Safety Research Program (Open)......................~.....
10 V.
NRC Severe Accident Research Program Plan (Open)..............
11 VI.
Nuclear Power Plant License Renewal (Open)...................
14 VII. Appointment of ACRS Members _(Open)...........................
18 VIIT..
Executive Sessions (Open)..................................
18 A.
Reports to the Commission...............................
18 I
1.
Proposed Rule on Nuclear Power Plant: License Renewal (Report to Chairman Carr, dated April 11, 1990).....
18 2.
NRC Safety Research Program Budget (Report to Chairman Carr, dated April 11, 1990)................
18 3.
Severe Accident Research Program (Report to Chairman j
Carr, dated April 24, 1990).........................
19 4.
Evolutionary Light Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements (Report to Chairman Carr, dated April 26, 1990)......................................
19 B.
Subcommittee Report (Open)..............................
20 1.
Containment Systems / Structural Engineering.........
20 C.
Other Matters (Open)....................................
20 1.
Meeting with Japanese Representatives...............
20 2,
Memerandum'from Thomas J. Kenyon, NRR, to Charles R.
Miller, NRR, dated March 26, 1990,
Subject:
, Summary of March 8-10, 1990 ACRS Meeting on SECY-90-016.....
21~
D.
Summary / List of Follow-Up Matters.........'...............
21 E.
Future Activities (Open)................................
24 1.
Future Agenda.......................................
24 2.
Future Subcommittee Activities.......................
24 4
9011020017 900405 If'
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11 i
APPENDICES I
MINUTES OF THE 360TH ACRS MEETING.
APRIL 5-7 AND 18-19, 1990 I.
Attendees II.
Future Agenda
?
i III.
Future Subcommittee Activities i
IV.
Other Documents Received r
i l
i
[
UNITED STATES -
f NUCLEAR REGULATORY COMMISSION g
f ADVISORY COMMITTEE ON REACTOR SAFEQUARDS WASHINGTON, D. C,20666 9*****
,o 4
s Revised: April 5, 1990 SCHEDULE AND OUTLINE FOR DISCUSSION 360TH ACRS MEETING APRIL 5-7, 1990 l
Thursday. Anril 5.
1990. Room. P-110. 7920' Norfolk Avenue. Bethesda. Md.
l 1) 8:30 -
8:45 A.M.
shgirman's Remarks (Open) 1.1)
Opening Remarks (CN/GRQ) 1.2)
Items of current interest - (CM/RFF) 3)
8:45
- 9:30 A.M.
Future Activities (Open)
TAB ------- --------- 3.1 )
Discuss anticipated ACRS subcommittee activities (RPS/RFF)
TAB - - - --- - -- ---- ---- 3. 2 ) Discuss topics proposed for con-sideration by the full Committee (CM/RPS) 3.3)
Revised ACRS subcommittee assignments (CM/RPS) 4)
9:30
- 10:00'A.M.
ACRS Subcommittee Actly M ga (Open) 4.1)
-Briefings and discussion of assigned ACRS-subcommittee activities, in-cluding safety-related matters such as containment design crtieria for i
future plants (DAW / CPS /MDH/EGI) 6)
10:00 -
11:00 A.M.
NRC Safety Research Proaram (Open) 6.1)
Discuss proposed ACRS report to NRC regarding1the impact of budget reductions on the NRC safety research program (IC/SD) 11:15 A.M.
Break
{
11:00 12:15 P.M.
Evolutionary Licht Water Reactor Certifi-5) 11:15 cation Issues (Open).
Discuss proposed ACRS report to NRC (CJW/CM/MME)
-1:15 P.M.
Lunch 12:15 l
I
i i
J c
4:45 P.M.
Evolutionary Licht Water Reactor Certifi-5) 1:15 cation Issues (Open)
TAB 5 ------------- 5.1)
Equipment Survivability - Briefing by representatives of the NRC staff 5.2)
Briefing by representatives of NRC staff and the nuclear industry regarding ABWR containment vent design,(CJW/JCC/MME) 5:30 P.M.
NRC___ Safety Research Procram (Open) 6)
4:45 6.1)
Discuss proposed ACRS report to NRC regarding the impact of budget reductions on the NRC safety research program (IC/SD)
Friday, April 6, 1990, Room P-10, 7920 Norfolk Avenue, Bethesda, Md.
7) 8:30
- 10:30 A.M.
NRC Reaulatory Imnact Survey (Open) t TAB 7 ------------ 7.1)
Briefing by representatives of the NRC staff regarding'results of survey of licensees regarding the impact of regulatory requirements (HWL/GRQ) 10:30 - 10:45 A.M.
Break 8) 10:45 - 12:15 P.M.
V' NRC Severe Accident Research Procram Plan l
(Open)
TAB 8 ------------ 8.1)
Report by ACRS subcommittee chairman regarding March 20-21, 1990' -
i subcommittee meetin.g (WK/MDH) 8.2)
Meeting-with representatives of the NRC staff 12:15 -
1:15 P.M.
LUNCH 9) 1:15 -
3:15 P.M.
vdNuclear Power Plant License Renewal _ (Open).
TAB 9 --------
9.1)
Report by ACRS subcommittee chairman regarding proposed.tutC rule for i
renewal of nuclear. power plant licenses (HWL/GRQ) 9.2)
Meeting with representatives of the' NRC staff and the nuclear: industry, as appropriate 3:15 -
3:30 P.M.
Break 10) 3:30 -
3:45 P.M.
AcDointment of New Membe rg- (Open/ Closed)
L 10.1)
Briefing and-discussion regarding the i
' i o
s e
)
3 status of appointment of new members to the Committee (CM/MFL)
(Portions of this session will be closed as necessary to discuss information the release of which would represent a clearly un-warranted invasion of personal privacy.)
11) 3:45 -
6:45 P.M.
PreDaration of ACRS Renorts (Open) i 11.1)
Discuss proposed ACRS reports to NRC:
_j 11.1-1)
Evolutionary Light Water Reactor certification i
y) 11.1-3 NRC safety research program-budget (IC/SD) paturday, Anril 7, 1990, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.
12) 8:30 - 12:00 Noon Preoaration of ACRS ReDorts (Open)-
12.1)
License renewal for nuclear power plants-(HWL/GRQ)
A 12.2)
NRC severe accident research pro-gram plan (WK/MDH) i 12:00 -
1:00 P.M.
Lunch 1 00 -
3:00 P.M.
12.3)
NRC safety research program budget ocr55 Mo 'D Wg. A 12.4) '
ou onary light water reactor certification issues-(CJW/MME) 1 4
l
l UNITED STATES
'g NUCLEAR REGULATORY COMMISSION L
/
o l.
g l
ADVISORY COMMITTEE ON REACTOR SAFE 00ARDS f
wAsHmoToN.D C,20066 o
Revised:' April 13, 1990 i
SCHEDULE ANDLOUTLINE FOR DISCUSSION 360TH ACRS MEETING APRIL 18-19, 1990 4
Wednesday. Acril 18. 1990. Room. P-110, 7920 Norfol': Avenue. Bethesda.
Ed.a.
3:30 P.M.
Chairman's Remarks (Open) 1)
3:15 1.1)
Opening Remarks'(CM/GRQ)-
1.2)
Items of current interest (CM/RFF) 6:30 P.M.
Preoaration of ACRS Reoorts (Open) 2)
3:30 2.1)
Discuss proposed ACRS reports to NRC:
2-1)
Evolutionary Light Water
. Reactor Certification Issues-(CJW/MME),
2-2)
NRC severe accident research program. plan (WK/MDH)-
Thursday. Acril 19. 1990. Room. P-110. 7920 Norfolk Avenue. Bethesda Md.
- 3) '
8:30 - 12:30 P.M.
Preoaration of ACRS Recorts (Open)
Continue discussion of the proposed ACRS-reports noted above.
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.14023dM' Fed 2ral Ragt
/ Vol. 55, No. 72 / Friday, April 13,1
/ Notices e
i identify other possible sources of FY90 Funds Management. Office of Administration,. d/g financial support for a particular project, For Fiscal Year 90, the U.S. Nuclear Mail Stop P-1042,7920 Norfolk Avenue, T/
and list those sources from which Regulatory Commies!on, Office of Bethesda, MD 20814.
financial support has been or win be Nuclear Regulatory Research,'
(Note:Upon delivery of the opplication to requested, anticipates making a total of $150.000 the NRC guard deok (et the alsove addrees).
The information provided in this available for funding research the guard should be requested to telephone section must be brief and specific-Cooperative Agreements to HBCU the Diviolon of Contracts and Property Detalled background information may Institutions. Because of the limited funds Managent (Extension x24297) for a pick.op of the opptication.)
be included as supporting proposed Cooperative Agreement documentation to the proposal.
budgets should be restricted to no more Nothing in this solicitation should be
%e following format shall be used for than about $50,000 per year, with total construed as committing the NRC to the project description:
project funding not exceeding $100.000 dividing available funds among all (a) Project Cools and Object /res. The over a period of two years.
quahfied applicants.
project's objectives must be clearly and Evaluation Process Dated at Betheeda, MD this eth day of unambiguously atated.The proposal should justify the project including the AU proposals received as a res$lt'of April 1990 For the U.S. Nuclear Regulatory commiselon.
problems it intends to clarify and the this announcement will be evaluated by Mary H. Maca, development it may atimulate.
an NRC review panel.
cmnt Officer, Contact Nesollot/on Smnch (b) Prviect Outline. %e proposal Evaluation Criteria
- L Division ofcontmcts andProperty should show the project format and Management, Office ofAdmlaletztlon.
agenda, including a list of principal areas or topics to be addressed.
Agre cret
- nerally, (m Doc.N N 4-M W am)
, c) N/ect Benefits.The proposal projects are supported in order of merit.
saAsse ces neem
(
g enould indicate the direct and indirect to the extent permitted by avauable.
benefits that the $ reject seeks to fund 'luatio' ' f ^ 'als for resea'rch - W Comme on Reestor Ea achieve and to w om these benefits will projects win emfofimportance is1 y the following Sat M R M W 4 enda
'CC'"
criteria. No leve in accordance with the purposes of -
d)The proposalshould describe implied by the orderin which these sections 29 and 182b.of the Atomic ph(ysical facilities required for the,the criteria are listed.
Energy Act (42 U'S.C. 2039,2232b), tho' conduct of the project. Further, the
- 1. Adequacy of the research design.
Advisory Comm!ttee on Reactor..
groposal shouldinclude brief
- 2. Scientific significance of proposal.
Safeguards will continue its 300th lographical sketches of individuals
- 3. Technical adequacy of the meeting on A ril18-19,1990,la Room P-responsible for planning the project.
investigators and their institutional 110,1920 Norfolk Avenue, Bethesda. -
"M""
C'
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ins itu o I e aa ere to the 4.
elevance to a research area (s) cost principles set forth in OMB Circular described above.
.p hedin th odeest on A-21.
- 5. Reasonableness of estimated cost in
%e propsal must provide a detailed relation to the work to be performed and (55 FR 12432)Ns revised muung ".
schedule of project costs, identifying in anticipated result.
particular-
- 6. Potential benefit of the project to co P e Co ttee d libera (1) Salariee--in proportion to the time the overall benefit of the institution's reg c
a tMs y
or effort directly related to the project; undergraduate and graduate research Evolutionary.lJaht3 Vater Reacto'r (2) Equipment (rental only);
program.
Certification lasues and %eir (3) Travel and Per Diem / Subsistence Disposition of Proposals Relationship to Current Regulatory in relation to the pro}ect; (4) Publication Costs; Notification'of award will be made by Requirements and the proposed NRC the Grant (Cooperative Agreement)
Severe Accident Research Program Plan.
(5) Other Direct Costs (specify}--c.g.,
Officer and organizations whoseg ne schedule for these sessions is noted supplies or registration fees;(Note: Dues proposals are unsuccessful will be so below.
to organizations, federations or 8dvi8 d.
Wednesday April 18,1990, Room P-110, societies, exclusive of registration fees,~
ProposalInstructions and Forms 7920 Norfolk Avenua,Betheeds,Md.,,
are not allowed as a charge.)
(6) Indirect Costa 9.ttach ne8ctlated Quesuons concerning the preceding 3:15 p.m.-6:30 p.m.: Preparation of agreement / cost allocation plan); and information, copies of application forms, ACRS Reports to the NRC (Open)-The (7) Supporting Documentation.The and applicable regulations shall be Committee will continue discussion of.
supporting documentation should obtained from or subm!tted to U.S.
the proposed ACRS reports to the NRC contain any additional information that Nuclear Regulatory Commission. A'ITN: regarding SECY-90-Oto, Evolutionary will strengthen the proposal.
Grant Officer Division of Contracts and IJght Water Reactor Certification issues Proposal Submission and Deadline Pmperty Management, Mall Stop P-and %eir Relationship to Current 1042. Office of Administration, Regulatory Requirements and the The notice is valid for part of the Washington, DC 20555. (Note:
proposed NRC Severe Accident Federal Government Fiscal Year 90 Cooperative Agreement application Research Program Plan.
,' i (March 30,1990 to September 30,1990).
packages. Standard Form 424 must be j
Potential grantees are advised that due requested in writing.)
Thursday, April 19,1990, Room P-110' to the limited funding available.
The address for hand. carried 7920 Norfolk Avenue, Betheeds, Md*
proposals received after June 15,1990 applications is: U.S. Nucleat Regulatory B 30 a.m.-n30p.m.:Prepamtion of may or may not be considered for Commission. A'ITN: Grant Officer, ACRSReports to the NRC(Open)-The funding in Fiscal Year 90.
Division of Contracts and Property Committee will continue discussion of
[
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14024 Federal Register / Vol. 55, No. 72 / Friday, April 13, 1990 / Notices M
h the pioposed ACRS reports noted The amendment modifies *
(Docket No.60 423) abo,ve.
specifications with respect to section Northeast Nuclear Energy Co, et al.:
t Procedures for the conduct af and 5.12 H!gh Radiation Area.The Consideration of issuance of.
participation in ACRS meetings were amendment addmases the Amendment to Facility Operatin_g pubbshedin the Federal Register on adm'nistrative controls for locked high Ucente and Proposed No 4-u-n l,l Septernber 27,1989 (54 FR 39594).In rediation area access and provides HazaMa ConsidwouonWminaHon accordance with these procedures, oral clarification for detar-tains the high l
or written statements may be presented radiation area dose value. ~
by members of the public, recordings ne application for amendment The U.S. Nuclear Commission (the will be permitted only during those complies with the standards and Commission} !s considering issuance of portions of the meeting when a requirements of the AtomicEnergy Act an amendment to Facility Opereting l
transcript is be kept, and questions of 1954, as amended (the Act), and the ucense No. NPF-49, issued to Northeast j
may be asked o y b members of the Commlulon's rules and regulations. %e Nuclear Energy Corr.pany, et at (the Committee,its cons tants, and stafL Commlulon has made appropriate -
licensee), for operation of Millstone Unit un&ngs as nquiredby se Ad and ee Na 3 WM @w Mn Comy, ma dn e ACRS Com ntolon's rule andreguladona tam Connde Executive Director as far in advance as CFR chapter 1, which ts set forth in the.
On March 15,1990, a leak in the.
license amendment.
Millstone Unit No.3 yard fire water riate practicable so that approde to allow the arrangements canbe ma Notice of Consideration cf.Iss' nance or supply header was detectbd.To make a necessary time during the meeting for Amendment and Opportunity for '
repair,it was determined that an picture and television camaras during Hearing in connection with thfe action -
underground section of the northeast fire such statements. Use of still.motim water header needed to ba lsolated. On this meeting as determined by the was published in the Federal Register on. March 19,1990, bypass jumper 390-166, Chairman. Information regarding the February 8,1990(55 PR 4499). NO..
was approved by the plant operations ',
time to be set aside foe this purpose may request for a hearing or petition foco review committee (PORC)which be hmited to selected portions of the leave to intervene was filed following '
established compensatory measures to ;
Y ' P "' '
meeting may be obtained by a prepaid this notice #.'
- 0 be taken during the isolation and repair -
telephone call to the ACRS Executive e Commis'sion has prepared ant of the northeast fire water supply' from -
header to be teolated and removed Director,Mr.RaymondF.Fraley prior Environmental Assessment and Finding,
to the mee laview of the possibility of No SigniBeant 1mpact (55 FR 12970) '
service for excarstion, location and that the e for ACRS meettngs related to the action and has concluded repair of.the leak. Additionallengths ' f J o
niay be adfasted by the Chartman as that an stronantannpact statemnt - fire hose were supp!Ied to hydrant hose f necessary tn facilitata the conduct of the is not warranted and that the issuance No.4. A continuous fire petrolwas:
meeting, persons planning to attend -
of this amendment willnot have a established at the reserve station should check with the ACRS Executive ' ' significant adverse effect on the quality service transformer and alternata Director if mch reacheduhng would of the human environment sources of Bre protection water were supplied to the fueland engineered result in maiorinconvenience. -
Furtherluformation regarding topics For further' details'with respect to the-safety features buildings to ensure to be doi whether the meeting 1 action see (1)The application for cWBpHam wie se Unnlung Con & don '.
- has been canceDed or reacheduled, the amendment dated December 22.1989 (2) f eOperausofTechnicalSpecmcade Chairman's ruling on retiuests for the-Amendment No.125 to Ucense No..
I opportunity to present oral statements DPR-36 and (3) the Comminalan's -
and the thne aRotted can be obtained by related Safety Evaluation and
- " 8A "
8 a prepaid telephone call to the ACRS '
Environmental Assessm, en.t.o -.
was being operatedwithin ea"Actica Executive Director, Mr.Raymond F.
, All of the,se items are available for-Statement" of TS 35.12.1,the >
- ~
Fraley(telephone SeI/492-0049),
publicInspection at the Commisalon's.
requirements of TS 3.0.4 would not,
between 7:45 a.m. and 4.30 p.m.
Public Document Room.2120 L Street, allow restart of the plant without repair '
Deted: AprG to,199a NW., Washington,DC and atthe of the fire weter supply header..
g, gg,,
Wiscasset Public Ubrary High Street,
' %e NRC staff has recognized that TS Adrisory h=ltree Mamwanent officer.
P.O. Box 367. Wiscasset Maine 04578, 3.0.4 has been applied in an inconsistent f ashion. In this regard, TS which allow
- " "*d " ' **I
' A copy ofitems (2) and (3) may be allmited operation with compensatory obtained upon request addressed to the. measures being taken for inoperable
)
U.S. Nuclear Regulatory Commlaston, equipment, restart of the facility with Washington, DC 20555, Attentiom the same inoperable equipment should -
(Desket No. 50 3091 Director, Division of Reactor Projects If not be prevented.%e NRC stal!
6
.o l
Maine Yankee Atomic Power Co.;
IL position onTS 3.0.4 la contained in leeuance af Amendment to Factitty Generic Letter (GL) 87-09 " Sections 3.0 l
Operating Ucens, Dated at Rockville. Maryland, thia 4th day and 4.0of the Standard Technical l
of Apell,199o.
l The U.S.NuclearRegulatory For the Nuclear Regulbtory Commielon. -
' Specifications (STS) on the Applicability of Umiting Conditions for Operations Commission (the 'ammWon)has and Surveillance Requirements," which r
issued Amendment No.115 to Facility
% ). tande, *-
we issued on June 4.1987. A resolution w
OpereungUcense No.DPR-30 issued to. roject Manager, Divisibn ofasoetoew for gendric problems associated with TS Maine Yankee Atomic Power Station 141. Office ofNuclear neoctoc aegn/otion,
~~
3.0.4 was proposed by GL 87-09.
located in uncoln County, Msine.W amendment was efiective as of the date
[m Doc.90 ee:7 Hled 4-12-eoi 0:44 mm)
By letter dated Aprill,1990 the l
licensee requested a Tenporary Walver sumo coce mm =
i of lascance. '
1
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0%O Fedtral Register / Vol. SS. No. 64 / Tuesday, April 3,1990 / Notices
<=1 b d h
Divlolon of Instrumentation and far in advance as is practicable so that briefing and discuss the status of work R
- s. Room 312, National Science appropriate arrangements can be made, in the NRC Severe Accident Research F
on.1800 G St. NW.,
During the initial portion of the Program. Representatives of the NRC Washington, DC 20550. Telephone: (zo2) meeting the Subcommittees, along with staff and its contractors w.ll particip.stec 3
sabeseo any of their consultants who may be as appropriate.
Purpose of advisorypancl: To provide present, may exchange preliminnry 1:45 p.m.-6 p.m> Evolutionary Light advice and recommendations views regarding matters to be Water Reactor Certification issues -
concerning support for training activities considered during the balance of the (Open}-The Committee will hear h
in raurch areas supported by the
- meeting, briefings regarding selected certification Biological Behavioral and Social The Subcommittees will then hear issues such as equipment survivability l
Sciencies Directorate of the National presentations by and hold d!scussions and ABWR containment vent design.
Science Foundation, with representatives of the NRC staff,its Also, the Committee will continue its Agenda:To review and evaluate consultants, and other inte ested discussion of a proposed report to the proposals as part of the selection persons regarding this review..
Commission on this matter. Members of process for awards.
Further information regarding i pics -
the NRC staff will participate, as -
Reasonforclosing:Th* proposals to be discussed, the schedulinhether the.. appropriate.5pmApm.rNRC 8
being reviewed include intemation of a sessions open to the public, w proprietary or confidential nat,se, meeting has been cancelled or '.
Program (Open)--%e Committee will b - '
. including technicalinformation:
rescheduled. the Chairman's ruling on '.
discuss a proposed ACRS report on thet.
l financial data, such as salaries; and requests for the opportunity to resent-impact of budgeting on the NRC safety.. *-
personalinformation concerning oral statements and the time al etted research program. -
individuals associeled with the therefore can be obtained by a prepaid Friday; April & 7994 Room P-JJR '.
^
. proposals. These matters are within telephone call to the cognizant ACRS 7220 Norfolk Avenue. Bethesd$ Md.
exemptions (4) and (6) of 5 U.S.C.
staff member, Mr. Dean Houston
. A30 A.M.-J230 a.m> NRCRegulatory -
1 552b(c)l Government in the Sunshine i(telephoneact/493-0521)between7:30. ImpactSurvey(Open}-Abriefingwill.
Act..
em and 4:15 p.m. Persons planning to-be given by representatives of the NRC /
Deed March 20.'1980..
attend this meeting are urged to contact.. staff regarding the results of discussions '
g, gg,gi,g,,, 5 the above named indiviudal one or two ; A nelear power plant owners and - ~
Comm/tteeManagementofficerl hbei schedul.
o operators regarding the impact of.
q
[FR Doc. ems 06 Filed 4-2-00; &45 am) s which may have occurred.
- 'E
- 9 power plant operations,8",""
"# ~ '
euses caos mm.m 4p-
[,
,. Dated: March 26,1980..
2&45 cm.-11:15 a.mJ fblure ACRS...,
.L.' 7 Gary R.Sdttechreiber, ;
. : Activities'(Open)-The Committee will..
1 NUCLEAR REGUL.ATORY '
, CMef. Nuclear /lecciorsBroac/L ;
discuss anticipated ACRS subcommittee
~
~
COMMISSION; 1
-(FR Doc. so-/ sos Filed 4-3-so: 645 em] U.. activities and items proposed for ',' ~
. auses coca reem.as considerstion by the full Committeet Advloory Committee on Reactor 11:15 cm-12 Noon: ACRS.
3..
Safeguards, Subcommittee on Seywe
~ Subcommittee Activities (Open)-The -
Accidents and Probabilistic Risk Adyteory Committee on Reactor: >
Committee will hear and discuss reports 1 Assessment; Meeting 8sfeguards;Revloed Meeting Agenda of ACRS subcommittees regarding the -
De Subcommittees on Severe In accordena with the purposes o
. status of des ted activities, including, sections 29 and182b.of the Atomic. f. containment esign criteria for future ;,
Accidents and Probabilistic Risk '.
plants and ACRS consideration of Assessment will hold a joint meeting on Energy Act (42 U.S.C. 2039,2232b), the April 18,1990, Room P-110,7920 Norfolk Advisory' Committee on Reactor.
Sp"ating uclear facultin.
Avenue,Bethesda MD.
Safeguards will hold a meeting on April.~
^1Pm-3Pm> Nuclear hrPlant he entire meetin 5-7,1990, in Room P-110,7920 Norfolk hanse Renwal(Open}4e.
public attendance. g will be open to Avenue, Bethesda, Maryland. Notice of Committee will hear a briefing and.
The agenda for the subject meeting this meeting was published in the.
discuss a proposed NRC rule for shall be aa follows:-
Federal Regia'.or on March 21.1990. %Is renewal of nuclear power plant Wednesday, April JA 1990-&30 a.m.
revised meeting notice incorporates a operating licenses. Representatives of until the conclusion of business.
session on the NRC Regulatory impact the NRC staff will participate, as
%e Subcommittees will continue their Survey and reschedules other sessions appropriate, discussion of NUREG-1150," Severe accordingly.
3 pa-3:25p.ma Appom, itnent of Accident Risks: An Assessment for Five Thursday, April 5,199a Room P-210, ACRSMembers (Open/ Closed)-%o U.S. Nuclear Power Plants."
pp 0 Norfolk Avenue, Rethesda, Md.
Committee will discusa the status of Orel statements may be presented by
&30 om-&45 a.m> Comments by appointment of ACRS members and members of the public with the ACRSChairman(Open~)-.%e ACRS qualifications of candidates proposed,
concurrence of the Subcommittee-Chairman will comment on items of for consideration for ACRS membership.
Chairman; written statements will be current interest. -
Portions of this session will be closed accepted and made available to the -
&ds om.Jais aa lndividualPlant as necessary to discuss information the Committee. Recordings will be permitted Examination forFeterna/ Events release of which would represent a only during those portions of the-(Open}-The Committee will hear a clearly unwarranted invasion of meeting open to the public, and briefing and discuss a proposed NRC personal privacy, questions maybe asked only by generic letter regarding Individual Plant 3:15 p.m.-&30p.rna Preparation of members of the Subcommittee,its Examination for Extemal Events.
ACRS Reports (Open}-The Committee consultants, and staff. Persons desiring 12:om-12:45p.m. NRC Severe -
will discuss proposed ACRS reports to -
to make oral statements should noufy Accident Research Progtum Plan the NRC regarding topics considered the ACRS staff member named below as (Open)-The Committee will hear a during this meeting, including the
Federal R
/ Vd 55, No. 64 / TMy. April 3,
/ Notices 12433 i
(AJSeghulabry Orgelzathns' Deted March as. 2000, evolutionary light water eeactor Statement of the Purpose of, and certificationissues,iPE for enAerna!
lohn C. Itoyle, Statutory Basis for, the Proposed Rule evsnts, and the NRC aafety research Advisory Committee Management Officer.
program budget.
(11t Doc.904:10Ffted 44-to;t46 sm]
Chorges ne proposed rule changes aHow kk f
[
""*****r"*"~
MBSCC and BSECC to become members s.00 a.m.-n Moon and fs p.m..mo d the SCG,he SCC was bud in P.M.:Preparollonef ACRS Asperte SECURfTIES ANDEXCHANGE.
1986 by seven cleering agencies for the (Opa$ 'Ite Committee will discoes COMMISSM purposes of, among other things,(i) proposed ACRS rgports to'the NRC Ret, No. H4784h March 36,1990 creating procedores to minimise risks posed by porticipants in more than one regarding toples considered deAng this IFue No.en 4sesoc-co41 & SM-89ECC.
mesting. latludirg license renewal for cleedng agency, and (11) confiraning anch so40 clearing agency's authority to pmvede to nuclearpewer plaats,the severe
.. - m other SCG members confidential accident research program plan, gogWetory N evoluGonaryLWR cerutication heues, ohposedglule ChegesW W information concerning the financial end and the NRC safety research psogram en m operating condition of clearing agency budget. Procedures forh conduct of RWanne hMenderWdpin SEnstues participants that are also participarts in andpedicipauonin ACRS other SCG seeseber deadog agencles.
e wsre pubitshadin theFederalR ster Clowing Group
%e edglaat sewnSCG membwe are:
on September it7.19eo f54 HL 39594). In l
tecordance with these procedores, oral Pursuant to section19(b)(t) pf the' Muissest SaceriBuhust Company.
or written statements may be presented SecorttlesExchange Actof1934 Act").
Midwest ClearingCorporation, by members of the public, recordings 15 U.S.C.yes(b ),noticeis DeposhoryThatCompany Notiemal wlD be permitted or@during those giventhat onF 23,1980, and on SecudunOcaring Carpersuon,Opdoes Qeadngh susckGeerlag portions deeinettirig when a March 16,1990,respeedvely.te MBS transertptis kept, andgeestions ClaaringCe pereewa("MBSCC") and CapmumbididdpMaad midd*h o**aaa=vw c = * = r-
"*'m"afe*e,Yis.ons 1 N O.*
C mi $ " n ** $eN b e-
%e originalSCG agreement sets fo 6 d
Persons desiringte make orel Securides andExchange '
w M P"'Penn d es pup,es -8 c
on etatements should notify the AQtS
(" Commission") the 16esitical proposed particl ation and relevantlegal P
Executive Dunctor as far in advance as rule changestF8eNos.SR MBSCC-00 conaMarauens,* and was approsed by praratrahla ao that appropriate 01 andSR-BSECC40-01) as descrfbed the Commission on July 18,1989.s l
errengements canbe made to allow the in items 1 and H below,whidhitems At the November a,1980, moeung.
necessary une duringthe meet %gfor have beenpreparedby the soff.
SCG members unanimously voted to sudistatements Useof sull, motion regulatory aiganisations.De allow BSEOCandMUSOCto become pimure and televtston camerne daring Commluton is pobtishing this metice to parties to the SCG Agreement and tids smeeting may be thalted to adaaad solicit comments onto proposed ride, i
membwe eT SCC.%eSCG believes dial Portins of theseemingasdaneralmed changes frominterested persons, the participation of bothMBSCC and l
by the %t--a InEormation regarding L Self Regulatasyc, dsehstence of BSECCwiuanham b goals d timf r
th) time tobe set aside for this putpose Statessentof theIlumes wguimuonbyapaadingb eenscos may be obtained by a prepaid telephone the Proposed Rule Changes fMMwadimshadas %Iweer can tothe ACRS Executive Director.Mr.
As discuued below, the proposed rule decrusing deka en es Nauonal Clearing i
RaymondF.Fraley, prior to the meeting. changes concernthe agreement of andSe la===tSystem.toadditteeto -
u Irelewof thepossibibty thatthe.
MBSCC andBSECC with severalother egowingNBSCCand BSECC schedule for ACRS meetings maybe adjusted by the Chairman as necessary clearing agencies to become members of pardolpauen la se SCG, b,
to facilitate the conduct of the meeung '
the Secaddes Clearing Group ["SCG").*
sunsedmonts to the SCG Agreeemet also modi (y the metice peovisions as set forth E,* $ P k 'e M d H.Self.Reguldwy Orguindus' in escuan 2(A) and(Clef abe original e
a g
Statementof the of, and..
SCG AF n't,auswisp mere etBcient such r==4ad=34=g weeld teeuk in major StatutoryBasisfor.
L_ M Rule handungof such neuoes or centeelisdag inconv==leine, Changes distributsen threagh the Secretaryof the ibare determinedle== A- = wtth subsection 10(d) Publiciaw e2-4s3 that in their filings wtth abe Ceewnission.,
- SCG, it is n==saaey toenosepartlessof this the self regulatory otstanizations -
De pmpmedrulechansa am meeting as moned above todiscuss inch.dedstatements t m.nl the -
teoststent w6ththe perynes and informoeien the release of adachweeld purpose dandbasisforteproposed Niuimments of sedian17Aef the Act, riipresent soclearly onwarmented -
rule changes and discussedany as esmoed. An thateey fooner -
Asvasion of panemalpdwacy(5 U.4LC.
comments it reedved on the proposed cooperetten andcoonHneton wfth.
552b(c) lod rule changw.the textof dwee Persons engegr.d in the clearance end Further informanon segarding topics statsmaata any be enemined at &e settlement of socorttles transmettoes and to bediscussed,whether the meeting pieces opengged taitems IV below, %e remove impediments to and perfectto has been concound ermachedaled,the sett.,oguleewy'a'T= nee =Honsbege -
mechanism of a national eyenem for ahe.
Chariman's ruling on requests for GW prepend sonenadas, est fare en secdoe proesyt and occarate clearance and Opportunity 1o resentoralstatements (A).(8),and(C)below ofebeeiset settlement of securities transactions, and the time al otted canbe obtained by sigalficant aspecte ef esch etsemments. '
i.
a prepaid telephonecall tothe ACRS Me, secunee rxchanse Act Release sto.arent Executiva Director.Mr.Rayinond F.
y soc,se.seaenees
- FreleyItelephone 3011492-eD49).
swnse Ait Reneese too. 270+4 Outy1s.1ssel. e4 04 saisses.a4 se aossa. -
between M45 a.sa.and 4:30 p.rn.
ra soess.
e s,,, noie t.
i e
,.,g m
m.
/
.o o
W d 10558 Fedtral Rtgister / Vol. 55, No. 55 / Wednesday. March 21, 1990 / Notices M
,f Chairman willcomment onitems of qM 9 requirements for Chilled Water Systems criteria and ACRS consideration of i
design, and (3) criteria being used by the operating nuclear power plants.
current interest. '
NRC staff to review the Chilled Water
' *ll. AppointmentofACRShfembers 845 0.m.-12 Noon: Evolutionary Light Systems design.
(Open/ Closed)-Discuss the status of Water Reactor Certification issues Reliability Assurance, date to be appointment of ACRS members, and (Open)-The Committee will hear determir.ed. Bethesda, MD. 'the qualifications of candidates proposed briefings regarding selected certification issues such as equipment survivability Subcommittee will discuss the status of for consideration as ACRS members.
implementation of the resolution of USI 301st ACRS Meeting, May 10-12, and ABWR containment vent design.
A-46, "Scismic Qualification of gggo.-Agenda to be announced.
Also, the Committee will continue its Equipment in Operating plants," and 362nd ACRS Meeting. June 7-9,1994-.
discussion of a proposed report to the Commission on this matter Members of other related matters.
Agenda to be announced.
Joint Regulatory Activities and the NRC stafi will participate, as Containment Systems, date to be ACNW Full Committee Meetings eppropriate.
(b determined. Bethesda, MD. 'Ihe 19th ACNWhfceting. April 2S-27, I p m.-5p.ma IndividualPlant H
Subcommittees will review the proposed 1990, Bethesda, MD. Items are Examination forExtemalEvents
[
final revition to appendix i to 10 CFR tentatively scheduled.
(Open)-The Committee will hear a briefing and discuss a proposed NRC r
part 50," Primary Reactor Containment d
h teakage Testing for Water-Cooled generic letter regarding Individual Plant Cha a te za Lon o uc a Power Reactors' Examination for External Events.
Quaternary Regionaillydrology Study Representadves oMe EC stan and N
ACRS Full Committee Meetings Pian.
the nuclear industry will participate, as
'B. Review results of the waste 360TilACRShfeeting, April 5-7,1990, appropriate, d
t Bethesda, MD. Items are tentatively confidence review group a final review 5 p.m.-o p.m.:NRCSofety Research l
scheduled.
report which includes the disposition of Pmgmm(OpenJ-The Committee will
- A. Evolutionary Ligh t. Water Reactor 9*
discuss a to sed ACRS report on the impad o eung on 6e MC safety.
C,crfification Issues (OpenJ-Continue rega eath ects research progran discussion of the proposed ACRS to Low Levels of Ionizing Radiation."
comments and recommendations
,D. Briefing by N.E. Todreas, Friday, April 6,1990 Room P-110,7920 Chairman of the NRC's Nuclear Safety Norfolk Avenue,Bethesda,MD.
Reactor Cert fi on asue a d eir Research Review Committee on the 8.30 a.m.-f t145 a.m.:NRCSevere relationships to current regulations.
Representatives of the NRC staff and NRC's radwaste research progran Accident Research Progmm Plan
'E. Continue ACNW considerations of (Open}-The Committee will hear a the nuclear industry will participate, a s appropriate.
EPNs High-lavel Radioactive Weste briefing and discuss the status of work
- B. Nuc/cor Power Plant License Standards, as appropriate.
In the NRC Severe Accident Research l
Renewal'OpenJ-Review and comment
- F. Committee Activitiet-The Program. Representatives of the NRC 1
on the prgosed NRC rule regarding Committee will discuss anticipated and staff and its contractors will participate, renewal of operating licenses for nuclear proposed Committee activities, future as appropriate.
.l
' power r tants. Representatives of the meeting agenda, and organizational JJ a.m.-12 Noon and 1 p.m.-2 p.m.:
NRC st aff and the nuclear industry will matters, as appropriate.
Nuclear PowerPlant License Renewcl particit ate, as appropriate.
20th ACNW Meeting, May 23-25, (Open)-The Committee will hear a
- C.II Efor ExtemalEvents (OpenJ-1994-Agenda to be announced.
briefing and discuss a proposed NRC l
Review (nd comment on the proposed 21st ACNW Meeting. lune 28-20, rule for renewal of nuclear power plant NRC genede letter and supporting 1990-Agenda to be announced.
operating licenses. Representatives of documentation regarding Individual Dated; March 15.1990.
the NRC staff will participate, as Plant Examinations for External Events-appropriate.
le C. it@'
Representatives of the NRC staff and 2p.m.-2:45p.m.: hture ACRS msory Comminee Afanagemen@.cen Activities (Open)-The Committee will the nuclear industry will participate, as i :
appropriate.
[FR Doc. 90 6422 Filed 3-20-04 8;45 am) discuss anticipated ACRS subcommittee 1
- D.Serem Accident Research Plan
m cootrse&e m activities and items proposed for (OpenJ-Briefing and discussion of the [ Advisory Committee on Reactor consideration by the full Committee.
status of work in the NRC Severe 3p.m.-3:30p.m.: ACRS Subcommittee Accident Research Program.
Activities (Open)-The committee will 1 :'
Safeguards; Meeting A8'nda Representatives of the NRC staff and hear and discuss reports of ACRS
' their contractors will participate, as in accordance with the purposes of subcommittees regarding the status of 9
i
)
appropriate. -
sections 29 and 182b. of the Atomic designated activities, including -
'E.NRCSofety Research Program Energy Act (42 U.S.C. 2039,2232b), the contalnment design criteria for future i
(OpenJ-Discuss proposed ACRS report Advisory Committee on Reactor plants and ACRS consideration of h
on the budgeting of the NRC safety Safeguards will hold a meeting on April operating nuclear facilities.
(.
research program.
5-7.1990, in Room P-110,7920 Norfolk -
3:30 p.m.-3:45 p.m.: Appointment of
'F, hture ACRS Acrivities (OpenJ-Avenue, Bethesda, Maryland. Notice of ACRS Members (Open/ Closed)-The.
Ij Discuss anticipated ACRS subcommittee this meeting was published in the-Committee will discuss the status of
.l activities and items proposed for Federal Register on February 23,1990, appointment of ACRS members and -
consideration b the fullCommittee, qualifications of candidates proposed t
'C. ACRSSu committee Activities Thursday, April 5,1994 Room P-110, for consideration for ACRS membership.
7920 Norfolk Avenue,Bethesda,MD.
Portions of this session will be closed I
(OpenJ--Ilear ar.3 discuss the status of assigned subcommittee activities 8:30 a.m.-B:45 a.m.: Comments by as necessary to discuss information the including containment performance ACRS Chairman (Open)-The ACRS release of which would represent a
+
I 4
i
$[
Federal R:gistar Vol.!$5, No.- 55 /.Wednuday..Mitch 2
/ Notices 10559 k
i it i
l has bero c'ancelled or rescheduled. the some were est'ablished at the request of-the Atomic Safety &nd ucensing Board "
, 'r clrstly unwarrantedinvasion of Chairman's ruung on requests for the.
opportunity to present oral statements.i ' or the former Offic'e'of the Executive & '
l personal privacy.. -,,...c s t., -
ACRS Reports (Open)--%e Committee : and the time allotted can be obtained by LegalDirector forin j
..M5 p.m.-6Ja p.m.:Paparation of. '
win discuss proposed ACRS reports to..'
a prepaid telephone call to the ACRS i licensing proceedings. A recent review j
', L.
the NRC regarding toples considered L Executive Director Mr. Raymond P.'.w of these LPDRs found that the < : -
v 9 colle~ctions were nolonger being used by,
'y
'i during this meeting. including the.,c,, Fraley (telephone 301/492-8049).
6e public %e clos!ngs were approved g
evolutionary light water reactor between 7:45 a.m. and 4:30 p.m.- cP by the Agency's A~tomic Safety and u,
a a.
cert:fication issues. IPE for external.
Dated: Mitch 15:1990. ] '
}'r Ucer,ing AppealsIhard Officeof
'h jq e
Advisory Committe'e MonogeSent Officerf /*, Nuclear Reactor Reguhuon, k
n i
events, and the NRC safety research John C.lloyle programbudgey libraries have been given de tion of g
[FR Doc. 90-6423 Flied 4-20-em 8:45 aml Saturday April 7,1990. Room P-110. -
7920 Notfolk Avenue,Bethesda~,MD ew,,o coog r, w
storing or discarding the reto s.The.
o\\
locations and hours of opers tion of the.
8:30 a.m.-M Noon and f p.m.-3p.m.:
fuB service LPDRs maintair ed for each.
Pmparation of ACRS Reports (Open)-- - E39Mk'Y e m hgi of these facilities can be ot tained by e.o
.h' The committee will discuss proposed
. Rooms for N ar Power Reactors,far. contacting the NRC local l ublice.v d.
4 ACRS reports to the NRC regardingy' i ; f mi i,.Lp p e.g.3.ni, A DocumentRoomstaff at8004&a08t G.
M,
cl4 {
topics considered during this meeting. -
.,p, includin license renewal for nuclear AosNcy:NuclearRegulatoryh a
'S'C,Tou Free,l.p o. tr.la dmu. :.w g power p ants, the severe accident Commission.a
.o. 4
.e., 9 :y<. p,ied at Betheeds. Maryland, this 14th of a h' k i
J !~..
Acnosc Notice of closing of eight' auxiliary local public document rooms research program plan. evolutionary.
ceru on issue'*
NRC.
mb i e nuclear power reactors-kha D.Phlupa,,.' m n % m.
.L Procedures to nductof and De tyDimetor, Division of Jrnedom of sueseaAny:Noticeis hereby given thatvt 1""88'" *d M O 8'*l"5O/I Ec - <.1 participation in ACRS meetings were '"
the UA Nuclear Regulatory Commission Ad"'8'88"d"' M d (NRC) has closed eight auxiliary localu *[F published in the Federal Registee on i
.2 m
September 27.1980 (54 FR 30504). In y..
public document rooms (LPDRs)forG anisse caos 7ses.*w #W
, accordance with these procedures, oral,
nuclear power reactors that had been%
or written statements may.be presented i by members of the public, recordings maintained for selectivo documents. A
...W
'M willbe permitted only during those. m, complete, full-service LPDR continues to; IDoeket Nos.50445,80 336; and SW. '
d portions of the meeting when a..
bemaintainedforeachof these ' m..,
~
- N*# M d " *'
- facilities.W v....ew. <,N w wesi A
These partial LPDRs were located in g HN Nuckw W WWg transcript is being kept. and questions o
the followinglibraries: Miami-Dade y M9sto6uolear h MWm.].
may be asked only by members of the j Relocation of Local Puhte Document;o Committee,its consultants, and staff.
PublicLibrary. Homestead FL(Turkey Room-Persons desiring to make oral -
~
statements should noufy the ACRS point Planth University ofluinois Noticeis hereby given that thy Executive Director as !ar in advance as, Library, Champaign. IL (Clinton Power practicable so that appro riate Station): Founders Ubrary. Northern '
NuclearRegulatory r'"*lon(NRC)2
- Try t gtfw'm%W g P "phla, ' ['
m fr N
n u
adon r such statements.Use of still, motion Philadelphla, PA (Limerick Generating '
Power Station from the Waterford. ?
{
Public brary d [ fta e ty'U ty Pa P N:
mee limi t se e
(Susquehanna Steam Electric Station %'
Thames Valley State Technical CoHege," -
N I,
and BeaverVaBey Powr Stationh Seth Norwich. Connecticut.The relocatforn i
e mee es f as o the time tobe set aside for this 6e c
A T as a ein v
.e couention. Members of the pubha may Projecth andSan Antelo PubUc o
in view of the possibility that the rary, San Antmio.TX(SathTexas now inspect and copy documents and y corraspondence related to the op tration,
schedule for ACRS meetings may be Nc4 adjusted by the Chairman as necessary. DATs:These partialLPDRs were closed - of the Millstone Nuclear Power! Nation,
. at the Learning Resources Center.
c......,
to faciutate the conduct of the meeting.
efiective February 23,1990.. -.'
Dames Valley State Technical College,a persons planning to attend should check. POR FuRTHEA WIPORBsATION CONTACT:, 574 New LondonTurnpike, No.wich.# 1 with the ACRS Executive Directorif
- Ms.TeaD.unton.Infmetin j'
. Connecticut 083eo.%e ubrary is open,,i 1
such rescheduling would result in major Services Librarian. Freedom of ' "
on the foHowing schede: Monday;., a inconvenience....
. Information Act/ Local Pubhc Document throughThursday 8 am to 8:33 pm; and i Ihave determinedin accordance with Room Branch, Division of Freedom of J
subsection 10(d), Pubhc Law 92-463 that Information and Publications Services. -
Friday 8 am to 4:30 pm. -.
itis necessary to closa portions of this Office of Administration.U.S Nuclear.
For further information, interested e parties in the Norwich area may contact-,
meeting as noted above to discuss 5
information the release of which would. Regulatory Comndssion. Washington. ;,
the LPDR directly through Dr. Paul Price.i DC 20555.Telephne 301,-492-7143, or,
' telephone number (203) 88Mn77. Parties -
represent a clearly unwarranted ToU-Free 800-638-8081.
~",
~
outside the service area of the LPDR.mii invasion of personal privacy (5 U.S.C.,
supptautwfAny sepOnesAvi0ic E4ch of -.
Further information regarding topics -
these partial LpDRs was established to
- may address their requests for recordsi s 552b(c)(6)).y....,
~.....
~
to be discussed,whether the meeting meet a specific need for a limited timec to the NRC's Pubuc Document Room..e Y
4 a7 J.
k b
k l t
w ab we MINUTES OF THE 360TH ACRS. MEETING APRIL 5-7 AND 18-19, 1990 The 360th meeting of the Advisory Committee on Reactor Safeguards (ACRS) was held at Room P-110, 7920. Norfolk Avenue, Bethesda, Md.,
between April 5-7 and 18-19, 1990.
The purpose of this meeting was to discuss and take appropriate actions on the items-listed in the attached agenda.
Owing-to lack of time during the April 5-7, 1990-session, the Committee was not able to complete a report to the~
Commission, that was due on April 20,.1990, related to evolutionary light water reactor certification issues proposed by the NRC staff in SECY-90-016.
Consequently, the meeting was recessed at 2:30 p.m..
on April 7, 1990 and reconvened at 3:15 p.m. on April 18, 1990.
A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room.
(Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd.,. 1612' K Street, N.W., Washington, D.C.
20006.)
I.
Chairman's Reoort (open)
(NOTE:
Mr.
R.
Fraley was the Designated Federal Official for this portion of the meeting.]
l Mr. Michelson, the full Committee Chairman, convened the: meeting at 8:30 a.m. with a brief summary of the planned meeting schedule and the provisions under which the discussions.were to be held.
He stated that the Committee had received neither-written comments nor requests for time to make oral statements from members of.the public.
Items of Current Interest Mr.
Michelson stated that the following items are of current interest:
o Dr. Wilkins has been appointed recently to the ACRS by the Commission and he will be attending this meeting as an observer, o
All the paper work, including security clearance,. associated with Mr. Minnick's appointment to the ACRS has been completed and he is now a voting member of the ACRS.
o Tennessee Valley Authority (TVA) has reduced 1430 positions, effective March 1, 1990, from its nuclear power organization..
This reduction is distributed as shown below:
Browns Ferry 415 I
Sequoyah 230.
Watts Bar 220-Nuclear power headquarters ~in Knoxville 300 Nuclear power headquarters in Chattanooga 265 i
e w
360th ACRS Meeting.
2 The schedules propoced by, the staff for restart of Nine Mile o
Point Unit 1 and Browns Ferry are May 5, 1990 and September 9, 1990, respectively.
o The International Commission on Radiological Protection (ICRP) is expected to recommend-limits for hot particles and the NRC staf f believes that these limits may be significantly lower than those recommended by the National Council on-Radiation-Protection and Measurements (NCRP) in the NCRP Report No.:6..
Mr. Carroll stated that he does not believe that the difference between the ICRP-and NCRP limits will be significant as has been envisioned.
An Incident Investigation Team has been formed to investigate -
o the loss-of-ac-power incident at the Vogtle Nuclear Plant Unit 1.
II.
Evolutionary Licht Water Reactor Certification Issues (Open)
(NOTE:
Dr.
M.
El-Zeftawy was the Designated Federal Official for this portion of the meeting.)
ABWR Containment Vent Desian The Committee heard presentations from representatives of~the NRC staff and the General Electric Company (GE) regarding;the staff's proposal that the Commission approve ' the use of a containment overpressure protection system in. the ABWR design certification process.
GE presented a summary of the ABWR containment-vent design and the operation of the overpressure protection system.
In addition,-GE l
presented a summary of the results of PRAs that have been performed for this system.
GE's analysis indicates that the' vent would provide l
a reduction in estimated risks, although ABWR. plants could operate within the Commission's safety goal guidelines with or without the vent.
Dr.
- Sawyer, GE, stated that the ABWR containment overpressure protection system (Seismic Category I) incorporates a pressure relief path from wetwell vapor space to the plant stack, and it is designed for 150 psig.
The rupture disks relieve at pressure less than ultimate capability.
The pressure relief operation is automatic and passive and does not require operator decision.
After; pressure is:
relieved and suppression pool-cooling. is regained, the operator closes air-operated valves : to regain containment integrity.
Dr.
Sawyer noted that the desirability o'f venting a BWR containment to mitigate multiple-failure accidents'far beyond the design basis has been accepted for some time.
Since 1981, the BWR emergency-procedure
"o 360th ACRS Meeting 3
guidelines (EPGs), developed by the BWR Owners Group and approved by the NRC for existing BWRs, have called for venting the containment wetwell air space.
GE believes that containment overpressure protection represents a
practical and beneficial feature to incorporate in the ABWR design.
The overpressure protection system is relatively inexpensive in a new plant and provides insurance against the consequences and financial risks associated with end-of-spectrum accident scenarios.
q GE has established two severe accident goals in the risk analysis submitted to the staff.
The first goal states that the frequency of J
a severe accident release resulting in a whole body dose of g5 rem beyond one-half mile from the reactor should not exceed 10 /Ryr.
This goal is basically the same as that specified in the EPRI ALWR Requirements Document.- The second goal states that the conditional containment failure probability (CCFP) should be less than 0.1.
The ABWR design with the vent system is expected to meet these goals.
GE has performed an analysis that indicates the CCFP for the ABWR design without the vent is 0.5; however, with a vent system, the CCFP was calculated to be 0.06.
Mr. Scaletti,-NRR, stated that the staff's review of the containment overpressure protection system proposed by GE.is not yet complete.
However, based upon a preliminary review of the ABWR severe accident design, the staff has determined that, as far as the-overall risk impact is concerned, the GE ABWR public safety goal is significantly more stringent than the Commission's quantitative health objectives.
Currently, the staff recommends that the Commission approve the use of the vent system in the ABWR design certification process.
Mr. De Vine, EPRI, stated that the EPRI Utility Steering Committee opposes inclusion of a requirement for a containment vent in advanced LWRs because it is philosophically inconsistent for advanced plants to design in a vent path when technical rationale for venting is addressed by other design features.
In
- addition, there is significant concern for institutional issues related to actual operation of a containment vent.
No clear regulatory policy exists on vent operation.
Mr. De Vine stated that the NRC staff's draft SER related to Chapter 5 of the EPRI ALWR Requirements Document includes the staff's position in favor of CCFP or other equivalent containment performance criterion.
He noted also that the staff's interpretation of containment failure as unisolable leakage (as opposed to definition based on dose) has the effect of requiring a vent.
The Utility i
Steering Committee is opposing;the use of CCFP.
However, EPRI has looked at the implications and concluded that:
l i
i
360th ACRS Meeting 4
Requiring the ALWR to meet a 0.1 CCFP where failure is defined o
in terms of a safety-significant dose is consistent with other safety goals and 0.1 CCFP can be met without a vent.
Reqdiring the ALWR to meet a 0.1 CCFP where failure is defined o
in terms of-ability to control the leakage pathway is inconsis-tent with other safety goals and is a de facto requirement for a vent.
Mr. De Vine referred to the February'16, 1989-ACRS report on the Safety Goal Policy that states "...each subordinate level of the safety goal hierarchy should be consistent with the level above and' should not be so conservative as to create a de facto new policy."
(
Mr. Carroll said it is impertant to note that GE has provided in the j
ABWR design additional means of decay heht removal.
This would reduce the frequency of tha sequences involving loss of containment heat removal function, thuo reducing the benefit of the ABWR vent i
system for these types of accident sequences.
Mr. Carroll expressed several concerns regarding the design of the containment overpressure protection as proposed by GE.
Some of these concerns are:
o The potential that such a system might' increase the risk through spurious actuation or malfunction, o
The sizing of the system (a system with lower. flow capability may be more centrollable and. result in less release of radioactivity).
o The need for - a demisting device in the system to reduce the release of radioactive aerosols if the system'is ever actuated, o
The reliability and testability of.the rupture-disks that will be used in the system.
During the April 18-19, -1990 meeting, the. Committee decided to recommend that use of a containment overpressure protection. system be approved subject to the results of the regulatory review.
EauiDment Survivability Mr. Taylor and Mr. Scaletti summarized the staff'c position regarding the " equipment survivability". issue specified in SECY-90-016.
They stated that the staff believes that features provided in the ELWR designs that are intended only for severe accident protection need not be subject to 10 CFR 50.49 (Environmental Qualification-Requirements),
10 CFR 50, Appendix A (Redundancy and Diversity Requirements),
(Quality Assurance Requirements).
The reason for this judgment'is that-the staff does not believe that severe core damage accidents should be design basis i
.J
360th ACRS Meeting 5
accidents (DBA) in the traditional sense that DBAs have been treated 1
in the past.
With reference to a statement in SECY-90-016 which states that-
"Notwithstanding that judgment, however, mitigation features must be designed so there is reasonable assurance that they will operate in-the severe-accident environment for which they are intended and over the time span for which they are needed," Dr. Siess stated that this implies that the staff's position on this issue includes much more 1
than the underlined portion of.the enclosure to SECY-90-016.
He believes that this statement should have been underlined as part of the staff position on this issue.
The ACRS, however, endorsed the stafi's position on this issue.
ACRS Action i
The Committee provided comments and recommendations on the proposed staff positions related to the 15 ELWR certification issues that are delineated in SECY-90-016, and issued a report to the Commission, dated April 26, 1990, discussed in Section VIII.
The Committee concurred in the proposed staff positions for certain issues.
For j
several other issues, it agreed with the proposed staff positions with additions and clarifications.
Additional remarks provided by ACRS members Dr. Lewis and Mr. Carroll and by ACRS members Dr. Kerr, Mr. Ward, and Mr. Carroll' were appended to the April 26, 1990 report to the Commission.
III.
NRC Reaulatory Imoact Survey (Open)'
(NOTE:
Mr. P. Boehnert was the Designated Federal Official for this portion of the meeting.)
Dr.
- Lewis, Chairman of the Regulatory Policies and. Practices Subcommittee, noted that the NRC had, initiated a survey.of selected licensees regarding the impact of the agency's regulatory policy.
l This survey was initiated in response to expressed concerns that I
there was a lack of feedback from licensees as to how the agency goes about its business.
Dr.
Lewis said the. Commission is to be congratulated for launching this effort.
He noted<that the survey results are delineated in draft NUREG-1395, " Summary of Significant Survey Comments,". that is appended to SECY-90-080, " Initial Staff Assessment."
Dr. Lewis stated that the above NRC staff documents were "well done."
Need for the Survey - Dr. T.-Murley, NRR Dr. Murley reviewed the origins of the survey.
He said that the agency's concern over the impact of regulatory policies began after the issuance of numerous requirements subsequent to the TMI-2
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360th ACP's Meeting 6,
accident.
This concern led to a reorganization of NRC's senior management structure and the issuance of the Backfit Rule.
The loss-of-feedwater event at Davis-Base and the overcooling event at Rancho Seco in 1985 led the agency to conclude that it needed to get more involved in plant diagnostic activities and. closer monitoring of plant operations.
Dr. Murley showed statistics to make the point that the agency's move in the above direction has resulted in both improved plant performance and consistently fewer accident precursor events.
Dr. hurley stated that data from the NRC Accident Sequence Precursor Study (ASPS) also indicate an improving trend in plant safety. The ASPS provides an overall estimate of mean core damage frequency (CDF) in RYs for the current population of U.S. plants.
Figures cited by Dr. Murley show a stead) decrease in CDF estimates from 1969 to 1988.
In response to a question from Dr. Shewmon, Dr. Murley stated that the ASPS, evaluates LER data; events that evidence a potential-CDF below 10-are ignored.
-l In response to a question from Dr. Kerr, the NRR staff stated that evaluations performed in conjunction with the ASPS lead them to believe that the CD? values are "rgal".
Dr. Murley said that
~ 40 events / year exceed the 10
." cutoff" value.
Considering NRC's conduct of its business, Dr. Murley acknowledged that NRC is now more intrusive in the licensees' affairs.
He stated I
also that the use of the Systematic Assessment of Licensee l
Performance (SALP) ratings by " Wall Street" is resulting in unfair pressure on licensees; the agency needs to consider changes to the SALP process to rectify this situation..
Dr. Murley said that, prior to this survey, licensee criticisms were unfocused and largely anecdotal.
The agency does not feel the need to apologize for its current regulatory policies.
However, given the need to ensure " checks and balances" in the NRC's operations, the i
subject survey was performed.
He noted that the survey lacks balance, as the NRC sought criticisms only from selected licensees.
Process and Results of the Survey - Mr.-B. Davis, Region III Mr. Davis, Regional Administrator, Region III, discussed the process and the results of the survey.
He stated that thirteen utilities were interviewed for this survey:
Alabama Power, Arizona Nuclear Power, Commonwealth Edison, Duke Power, Illinois Power, Louisiana Power and Light, Nebraska Public Power, Northeast Utilities, Northern States Power, Pacific Gas and Electric, Pennsylvania Power and Light, South Carolina Electric' and Gas, and Vermont Yankee.
Mr. Davis stated that, with the exception of the utilities surveyed in his l
360th ACRS Meeting 7
Region, he and his co-worker (Ms.
C. Pederson) attended all the interview sessions.
For each utility interviewed, NRC held discussions with representatives ranging from the CEOs to plant operators.
All comments were taken as confidential to assure no fear i
of retribution.
Mr. Davis noted that the principal themes - that emerged from the survey are:
o Licensees acquiesce to NRC requests, (both formal and informal), in order to avoid poor SALP ratings and the consequent financial and public relations problems that result.
o NRC's demands on licensees' resources, resulting from both formal and informal requirements, impact to such a degree that licensees feel their plants would be more reliable, and per-hape more safe, if they were freer to manage their own assets.
The comments were grouped into ten categories as noted below. The key concerns / complaints raised by the licensees are also noted under each category:
o Reauirements and Perceived Recuirements The NRC is issuing so - many new requirements that it is actually managing the utilities' resources rather than regulating the industry.
The licensees consider informal guidance, such as generic correspondence, policy statements,.and inspector and reviewer comments, as formal requirements since they do not want to appear unresponsive to NRC initiatives.
The NRC does not consider the cumulative impact of all of its initiatives on the industry.
o NRC Licensino Activities The NRC -review of licensing submittals is untimely.
Technical Specifications are poorly written, resulting in excessive surveillance.
There is no effective appeal process for technical-issues.
The NRC inspectors impose many unauthorized backfits by setting successively higher standards of performance.
360th ACRS Meeting 8
o NRC Insoection Activities Team inspections place a 'large resource burden on the licensees.
i When reviewing an event, the Augmented. Inspection Tean so dominates the licensee's resources that the licensee's ability to investigate the event independently. is impaired.-
o Performance Evaluations The SALP process is an improper mechanism for obtaining improved performance, and the public-and outside organizations (e.g., Wall Street). misuse and misinterpret' SALP results.
H Licensees are afraid that complaining about these issues to the NRC will result in retaliatory action.
1 o
Imoact of Multinle Oversicht Oraanizations Regulation and oversight by multiple organizations have significant impact on. licensee resources -and also have potential adverse safety implications.
Involvement of State Governments is unnecessary and the NRC should control such involvement.
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The NRC should establish minimum requirements' and leave the l
l pursuit of-excellence to the-licensees and, industry.
organizations.
'I o
ODerator Licensina i
Examiner standards.are continually changing and not implemented uniformly.
]
Too many organizations are involved in the requalification process.
The NRC should.not conduct examinations but should merely.'
monitor the performance ofLan INPO-accredited' program.
o Enforcement and Investications-l Enforcement actions taken for-violations are inconsistent l
among the regions.
Even 'though licensee performance is improving, the~
enforcement actions are also increasing.
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Licensees are reluctant to challenge the enforcement actions because of the fear that the NRC inspectors may lower the licensees' SALP ratings.
o Reoortina Events The NRC needs to examine its requirements ~ for' reporting-events because reporting thresholds are too low.
{
Interpretations of what is reportable are inconsistent.
The agency's call recipients sometimes lack adequate j
know.'. edge, o
communications l
The verbal communications skills of NRC personnel during exit meetings could be improved, and written products were of poor quality.
Licensees are afraid to communicate their concerns about unfair and s~ong actions - of NRC employees to the. NRC -
management beer..use they fear retaliation.
o Oualification Trainina and Professionalism of NRC Personnel 1
While NRC, as an organization, ratesLhigh marks, some NRC j
staff members lack adequate knowledge and interpersonal skills.
Some NRC inspectors have difficulty in distinguishing.
between significant and less significant items.
Mr. Carroll.said he was troubled that some utilities don't seem to be aware of Nuclear Management and Resource Council (NUMARC) activities that directly impact them.
Mr. Davis agreed with the remark.
Dr. Lewis inquired whether the integrity of the survey was corrupted
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Mr.' Davis stated that, i
-based on the interpersonal-actions he observed, only one of the 65 L
groups interviewed didn't level with them.
In response to a question from Mr.' Carroll, Mr.-Davis said the level of interviewees' preparedness varied; some discussions-were orchestrated by the cognizant management.
Mr. Minnick asked Mr. Davis if this survey left him feeling any-i t
better or worse about plant safety.
Mr. Davis stated.that the survey i
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i 360th ACRS Meeting 10 confirmed his view that there is a spectrum of utility capability across the country vis-a-vis operation of nuclear plants.
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Staff's Plans in Response to the Survey - Dr. T. Hurley Dr. Murley discussed NRC's plans to respond.to the survey.
Three areas are under consideration for regulatory improvements.
.These involve examination of means and methods for:
o Accounting for the cumulative impact of generic communications /
requirements o
Better scheduling and control of inspections, especially team inspections o
Improved training, preparation, and management of inspectors.
Drs. Kerr and Lewis complimented the Staff for the survey effort.
Mr. Michelson indicated ti.at the Committee will discuss this item at future ACRS Meetings as the staff's actions progress.
IV.
NRC Safety Research Procram (Open)
(NOTE:
Mr.
S.
Duraiswamy was the Designated Federal Official-for this portion of the meeting.]
The Committee issued a report to the Commission on this matter as discussed in Section VIII.
The Committee expressed concern about the continually dwindling NRC Safety Research Program budget, and provided bases for its belief that a viable research program should be an essential part of the NRC regulatory process.
The Committee stated that unless the trend of continually diminishing funding for the NRC research program is arrested, the-overall effectiveness ~of the agency will be seriously compromised.
The Committee stated that, in its judgment, the present research funding level is below the minimum, and if there are any further reductions RES will not-be able to support and maintain an effective research program.
The' Committee 4
suggested that a guideline of at least one quarter of the agency budget is more appropriate for a viable research program..
The Committee suggested also that the Nuclear Safety-Research Review Committee advise the RES Director on general safety research philosophy and long-range strategy, rather than on the details of specific ongoing research programs.
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360th ACRS Meeting 11 V.
NRC Severe Accident Research Procram Plan (Open)
(NOTE:
Mr. D.
Houston was the Desianated Federal Official for this portion of the meeting.)
Dr. Kerr, Chairman of the Severe Accidents Subcommittee, indicated that the subcommittee had met with the staf f on March 30 and 21, 1990 to review the Severe Accident Research Program - (SARP).
He stated that most of the review was devoted to the-short-term program, defined as those issues related to early~ containment failure.
He stated also that the staff had provided responses to two questions posed by Dr. Shewmon in regard to depressurization and core melt progression.
Dr. Speis, RES, mentioned that the questions raised by Dr.. Kerr regarding two issues included in the Severe Accident Policy Statement-will be discussed later by Dr. Sheron, or a response provided in writing.
Dr.
Kerr agreed that a
written response would be satisfactory.
Dr. Sheron, RES, presented an overview of the status of the SARP.
He stated that the SARP was a major supporting element of the severe accident integration plan and would provide technical input in the areas of Individual Plant Examinations (IPEs),.
containment performance improvement (CPI), and accident management. He discussed the elements of the short-term and long-term programs.
The. issues given higher priority were those associated with early containment
- failure, e.g.,
Mark I liner attack or-direct containment heating (DCH).
Dr. Sheron next discussed the status,of activities in the following areas:
o BWR Mark I Liner Issue A report, NUREG/CR-5423, "The Probability of. Liner Failure in a
Mark-I Containment,"
prepared by. RES contractor Dr.
Theofanous, has been issued.
Peer-review comments on this report are being reviewed and assessed by the. staff.
A final workshop is planned to be held to discuss remaining issues.
o QIrect Containment Heatina All DCH tests were stopped in 1989.
A workshop was held during.
December 1989 at Annapolis, Md.,
to ' discuss DCH issues.
Conclusions of this workshop include:
i 360th ACRS Meeting 12 Scaling of initial and, boundary conditions is very l
important to the ability to interpret and utilize - test results.
A key phenomenon that plays a critical role in determining l
the severity of a DCH event is the fragmentation and-o entrainment/deentrainment of corium as it enters the lower i
cavity.
i Current thinking is to determine fragmentation and entrainment/
deentrainment through separate effect.s' tests in which particle size and distribution can be measured.
o Code DeveloDment A letcer has been issued to code developers to apportion funding-l such that codes would be documented by the end of FY 1989.
Specific actions taken on major codes include:-
,I Development of MELPROG code has-been essentially terminated.
Development of COMMIX code has-been stopped pending completion of the assessment.
3 Contract has been issued to Scientech to evaluate other severe accident codes with respect to status, need for further develo,.nent, etc.
o Scalina Methodoloav Dr. Zuber headed up a team of experts to address scaling of severe accident experiments.
The basic approach was to develop an equation describing the rate of pressure change in the cavity accounting for all heat sources and. sinks.
SNL and ANL are currently developing detailed scaling rationale for further testing.
o Accident Manacement The major issue is the consequences of adding water to a degraded core.
_The Reactor and-Plant Systems -Branch is performing some bounding calculations on hydrogen and steam production resulting from adding water to a degraded core.
The Accident Evaluation Branch is examining whether the FARO facility can perform tests to determine the consequences of adding water to a degraded core.
360th ACRS Meeting 13 Dr. Shuron indicated that 40 percent of his Division's budget has been allocated for SARP, and SARP is the largest single budget item in the agency.
He highlighted some of the international participa-tion, namely in France, Italy, Japan, and Russia.
He also noted that NRC and EPRI have been working closely together to ensure that there will be no duplication of programs and that the programs are complementary.
Dr. Sheron indicated that a commission briefing on the status of SARP had been scheduled for May 14, 1990.
He stated that a Committee letter on this matter would be helpful to the staff.
Mr. Michelson asked where accident initiators are being studied. Dr.
Sheron replied that this is being done by the PRA Branch, and it is not part of the SARP.
Dr.
Kerr expressed enthusiasm about the results of the Severe Accident Scaling Methodology (SASM) effort and asked if a SASM-type approach could be applied to other elements of the SARP.
Dr. Sheron stated that contractors are being asked to apply the SASM approach to all experiments.
s Mr. Minnick asked whether any requirement is baing proposed to ensure water in the Mark I cavity since the Mark I liner study has shown this to be very beneficial.
Dr. Speis stated that utilities have been aware of this benefit but that NRC has not proposed any requirements in this area.
Dr. Catton expressed a concern about the deletion of melt spreading studies at BNL.
Dr. Sheron indicated that this was due to the lack of a BNL response when they were asked to show how further experiments could be related to actual nuclear plants.
Dr. Sheron indicated that the MELTSPREAD code was being developed at EPRI with some small experiments at ANL.
In response to Dr. Catton's inquiry, Dr. Eltawile agreed to send him a copy of the ANL report on this matter.
Dr. Shewmon asked for clarification regarding natural circulation, intentional and unintentional depressurization, and the effect on i
heat transfer that is ascribed to hydrogen generation.
In their response, the staff cited studies at INEL and SNL on these issues.
Also, Dr.
Sheron indicated that much of this effort was being conducted in regard to accident management, an area not discussed or presented at this meeting.
Dr. Shewmon asked why there was apparently little effort in the current studies to translate hydrogen detonation load into containment failure values.
Dr. Sheron indicated that there are codes currently developed that will do this.
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i l-360th ACRS Meeting 14 During the meeting, the Committee discussed and approved a report on the SARP activities.
The context of this report is discussed in Section VIII.
VI.
Nuclear Power Plant License Renewal (Open) i (NOTE:
Mr.
G. Quittschreiber was the Designated Federal official for this portion of the meeting.)
Dr.
- Lewis, Chairman of the Regulatory Policie.
and Practices Subcommittee, stated that the Subcommittee met on March 26, 1990 to review the proposed license renewal rule.
j Staf f's Proposed License Renewal Rulemakina Packnae, Mr. Karl Kniel,.
RES Mr. Kniel summarized the proposed License Renewal Rulemaking package that was provided to the ACRS on March 7,
1990.
The staff is planning to publish the proposed rule (10 CFR 54) during June 1990.
A proposed regulatory guide describing the content, format, and other details of license renewal submittal is scheduled to be published during December 1990.
The final rule will be published during May 1991 and the final regulatory guide during April 1992.
Mr. Kniel noted that a major industry technical report program is under way to cover the license renewal problems associated with the major components and structures.
Three of the ten reports have already been submitted to the NRC and to the ACRS for review and comment.
The staff plans to write an SER on each of these industry reports.
The first lead plant seeki N license renewal is scheduled to come to the Commission during June 1991 and the second during December 1991.
Current Licensino Basis, Mr. Karl Kniel, RES Mr. Kniel stated that the basic regulatory philosophy for the rule is that except for age-related concerns, the current licensing basis (CLB) is sufficient ta provide reasonable assurance of adequate protection of the public health and safety. The licensing basis that was originally accepted and then modified over the years will continue to be modified and will be the licensing basis for the plant when it is brought in for license renewal.
This is acceptable to the staff for life extension.
Age-related degradation will be managed so that' structures, systems, and components important to safety will perform in accordance with and maintain the current licensing basis.
In response to a question from Mr. Michelson concerning the present performance of cost benefit for potential backfits, assuming a 40-year life instead of an extended life, Mr. Kniel stated that the additional 20-year period would have a small effect (factor of about
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360th ACRS Meeting 15 i
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- 2) which would not be significant.
Old issues will not be reopened to perform a cost-benefit with the extended life.
The staff is not proposing that licensees be required to submit the CLB as documents or by reference to documents already submitted to the NRC.
The rule will require that licensees compile the CLB for their own use in the screening process for structures, systems, and components important to license renewal.
In response to questions from the Committee concerning the CLB, Mr.
Kniel stated that it would include any document submitted to the NRC during the plant life which specify requirements; howcVer, the utility is not required to submit documents or to reference documents for purposes of providing the NRC with a definition of the CLB for the plant life extension.
In response to a
question from Mr.
Michelson concerning the industry's responsibilities, it was noted that it is the intent of the Nr.C that whatever is needed to justify the continuation of operation will be up to the utility to do and to provide the basis to the NRC for the additinnal license renewal period.
Systems. Structures and Components Important to License Renewal, Mr.
Karl Kniel, RES Mr. Kniel stated that the term " systems, structures, and components (SSCs) important to license renewal" 'is defined in the rule in terms of the need to ensure integrity of pressure boundary and safe shutdown for the design basis.
It is also defined to include all SSCs used in safety analysis for the licensing basis including ATWS and station blackout; SScr. in the balance of plant would only be addressed to the extent they are included in the FSAR.
The screening process specified in the draft rule is meant to be an effective program to identify all SSCs important to license renewal which contribute to performance of a safety function or whose failure could preclude an SSC from performing a safety function.
The process is meant to identify effective programs to control aging and/or to describe actions taken to manage aging.
Aeolication of the Backfit Rule, Mr. Karl Kniel, RES Mr. Kniel stated that the staff is proposing that the Backfit Rule not be applied to the license renewal process.
The Commission has recommended that the Backfit Rule be applied during the individual plant license renewal proceeding. Age-related requirements to ensure conformance with the CLB, and adequate protection would be permitted without respect to cost.
Any related requirements that go beyond the CLB would be subject to cost / benefit analysis and justification provisions of the Backfit I:ula.
The proposed Rule on License Renewal
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360th ACRS Meeting 16 specifies that the Backfit Rule is applied again after the licenso l
has been renewed.
Industry Anoroach to License Renewal, Mr. Bill Rasin, NUMARC Mr.
Rasin discussed the industry effort with regard to license renewal.
NUMARC has established a working group that includes representatives from the lead plants and other utilities in the industry.
The industry effort dates back to the late 1970 and the EPRI economic feasibility study shows that life extension should be pursued.
Pilot studies performed on the Surry and Monticello plants looked at the technical feasibility and licensing problems.
Mr. Rasin noted that the technical reports being prepared by the industry focus on the major components in the plant, selected from the pilot studies.
There is no technical basis for the selection of the 20-year extension period.
The industry is in " agreement" with the direction being taken by the staff with regard to license extension.
Mr. ?asin stated that the industry has performed a detailed time dependency study to look at regulations which contain a time dependency element and they provided the results of this study to the NRC.
Mr. Rasin mentioned the concerns that the industry has with the proposed License Renewal Rule, such a compiling the CLB upfront, along with possible misuse and mischief in the process.
If the CLB is required in a rule, then all the information that is compiled is subject to discovery in a hearing.
Northern States Power ConDany, Mr. Terry Pickens Mr. Pickens stated that the Monticello plant, which is the lead BWR plant for license renewal, has been. active in the area of license renewal and plant life extension since 1984.
Through pilot plant studies, the Northern States Power Company (NSP) has identified a set of critical components.
They have not identified any major obstacle to extending the plant life of Monticello by up to 35 years.
In response to a question from Mr. Michelson concerning whether they would look at degradation of materials, for example electrical insulation and its flammability with time, Mr. Pickens stated that looking at such things is part of their CLB.
Mr. Pickens stated that they intend to forward a letter to the staff repesting that they consider a changed definition of effective programs addressing aging that differ from that described in the FS.iR.
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Mr. Pickens mentioned several concerns he has with the conceptual l
rule presented to the Commissioners on January 30, 1990.
Some of these concerns included documenting the
- CLB, the amount of information required on the SSCs, and the methods for controlling activities necessary to manage aging.
The rule shouJd not be used to resolve issues beyond the scope of aging and its impact during the license renewal term and should focus on reviet-of age-related degradation for those components that can direct 1.y affect the public health and safety.
4 Yankee Atomic Electric Connany, Mr. Don Edwards Mr. Edwards noted that the Yankee Atomic Electric Company (YAEC) has followed the pilot plant studies very closely.
It is a member of the industry advisory committees, and by and large feels that its plants are "not getting older but are getting better."
The average plant capacity factor has been going up with time and that there are major improvements being m-de to the plants.
Mr. Edwards expresseo agreement in principle with the NRC's approach to the license renewal process in that the staff is focussing primarily on hardware and that the current level of safety and licensing basis are acceptable.
He indicated that based on SECY-90-021, " Report on License Renewal Workshop and Proposed Revisions to the Program Plan and Schedule for Rulemaking,"
the NRC's evaluation method is cumbersome and essentially ignores the existing NRC oversight of the current license.
He also felt that the rule provides no controls over the scope of backfits.
Mr. Edwards noted that changes to the CLB imposed by the staff, except for those proposed as a result of the analysis, should be justified as necessary for adequate safety or cost justified as meaningful safety improvements.
Renewal should focus in on age degradation of long-lived equipment.
The plant should only be reviewed to ensure that the identified hardware continues to perform its intended function.
In response to questions from Dr. Shewmon concerning licensing the Yankee Rowe pressure vessel for another 20 years, Mr. Edwards stated that a great deal of thinking and work have been and are being done with regard to the Yankee Rowe pressure vessel.
The YAEC met with the staff a few weeks earlier to lay out the program to ensure _that the pressure vessel would not be on'the critical path for license extension.
In response to a question from Mr. Michelson concerning whether the CLB is also the current Design Basis for the plant, the answer was yes.
It was noted that the 40-year design basis can be extended.
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360th ACRS Meeting 18 ACRS Action I
The Committee issued a report to the Commission on this matter which is discussed in Section VIII.
VII.
Accointment of ACRS Members (Open)
(NOTE:
Mr. R. F. Fraley was the Designated Federal Official for this 4
portion of the meeting.)
The Committee discussed briefly the new procedures approved by Chairman carr for appointment of new ACRS members that were trans-mitted through a memorandum from Sandy Showman, SECY, to Ray Fraley, ACRS, dated March 23, 1990.
These procedures apparently supersede the previous procedures approved by then NRC Chairman Zech that are delineated in memoranda dated March 14, 1988 and February 8, 1989.
These procedures require that vacancies be filled on a case-by-case i
basis from a panel of applicants to be considered for each position.
They require also that a public announcement be made in the Federal Register and/or other publications for initial and replacement membership vacancies so as to provide an opportunity to the public to suggest nominees.
The Committee decided that the ACRS Subcommittee on Planning and t
Procedures should review these new procedures and develop a
recommendation for consideration by the full Committee during the May 10-12, 1990 ACRS meeting.
A meeting of the Planning and Procedures Subcommittee scheduled for May 9, 1990 to discuss this matter was subsequently postponed to June 6, 1990.
Therefore, this matter is expected to be discussed by the committee during the June 7-9, 1990 meeting.
VIII.
Executive Sessions (Open)
A.
ReDorts to the Commission (Open) 1.
ProDosed Rule on Nuclear Power Plant License Renewal (Report to Chairman Carr, dated April 11, 1990)
The Committee concurred in the approach being propored by the NRC staff for dealing with the nuclear power plant license renewal with several observations and comments.
2.
NRC Safety Research Procram Budaet (Report to Chairman Carr, dated April 11, 1990)
The Committee expressed concern about the continually dwindling NRC Safety Research Program budget, and provided bases for its belief that a viable research program should-be an essential part of the NRC regulatory process.
The l
4 360th ACRS Meeting 19 ll Committee stated that, in its
- judgment, the present research funding level is below the minimum, and if thero are any further reductions RES will not be able to support and maintain an effective research program.
The Committee suggested that a guideline of at least one-quarter of the agency budget is more appropriate for a viable research.
program.
The Committee suggested also that the Nuclear Safety Research Review Committee advise the RES Director on general safety research philosophy and long-range strategy, rather than on the details of specific ongoing research programs.
3.
Severe Accident Research Proaram (Report to Chairman Carr, dated April 24, 1990)
The Committee provided comments and recommendations on several elements of the NRC Severe Accident Research Program (SARP).
The Committee pointed out that the same areas that were being explored ten years ago are still being investigated under SARP.
However, there is little assurance that the proposed research would reduce uncertainties to an acceptable value. The Committee stated that, in its perception, various elements of the SARP lack focus and it is probably not altogether the fault of the office of Nuclear Regulatory Research.
Part of this lack of focus comes from the inability of the agency to deal with severe accidents in a regulatory context.
4.
Evolutionary Licht Water Reactor Certification Issues and Their Relationshio to Current Reculatory Reauirements (Report to Chairman Carr, dated April 26, 1990)
The Committee provided comments and recommendations on the-proposed staff positions related to the 15 evolutionary light water reactor certification issues that are delineated in SECY-90-016 and an associated enclosure. The Committee concurred in the proposed staff positions for certain issues.
For several other issues, it agreed with the proposed staff positions with additions, clarifica-tions, and comments.
Additional remarks provided by ACRS members H.
W.
Lewis and J.
C.
Carroll.and ACRS members W.
- Kerr, D.
A.
- Ward, and J.
C.
Carroll were appended to this report.
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360th ACRS Heeting 20 B.
Subcommittee Reoort (Open) 1.
containment systems / Structural Enaineerina (NOTE:
Mr. D. Houston was the Designated Federal Official for this portion of the meeting.)
l Mr. Ward, Chairman of the Containment Systems subcommittee, reported on the joint subcommittee meeting held on April 4, 1990.
He indicated that this was the fifth in a series of meetings which had been held to gather information from experts in the containment design field.
This information is to be used by the ACRS in its effort to develop new containment design criteria for future plants.
At this i
- meeting, invited speakers addressed design features of
During this Committee meeting and the April 4,
1990 subcommittee meeting, Mr. Ward distributed the following draft documents that he had prepared:
o Summary of Preser,tations by Invited Speakers o
Summary of Existing NRC Requirements for Containment Design o
Matrix of Containment Functions / Features / Issues; current position by NRC and Industry and Proposed ACRS Position o
Comparison or Positions on Implementation of the Safety Goal Policy.
In conclusion, Mr. Ward requested written comments from members in regard to the third document in the above list.
These comments will be evaluated in the development of the ACRS paper on proposed containment design criteria for future plants.
C.
Other Mattern (Open) 1.
Meetina with Jacanese Reoresentatives During this meeting, which is tentatively scheduled to be held between September 16-21, 1990 in Japan, the Committee plans to meet with representatives of Hitachi, Toshiba, Tokyo Electric, and MITTI.
Items tentatively proposed for discussion include:
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360th ACRS Meeting 21 I
APWR ABWR, including the basis for containment selection Seismic issues, including seismic design basis Siting Quality assurance Maintenance.
The Committee decided to discuss this matter and develop a detailed agenda during the May 10-12, 1990 ACRS meeting.
2.
Memorandum from Thomas J.
Kenyon.
NRR.
to Charles L.
Miller. NRR. dated March 26, 1990. Subiect Summary of
}igrch 8-10. 1990 ACRS Meetino on SECY-90-016 The Committee felt that the summary report prepared by Mr.
Kenyon does not reflect accurately the Committee's deliberations and preliminary decisions related to the ELWR certification issues included in SECY-90-016.
The committee expressed concern about the potential impact of this summary report on ACRS activities.
The Committee instructed Mr. Michelson, ACRS Chairman, to call Mr.
- Taylor, EDO, and bring this matter to his attention as well as the' Committee's concern.
D.
Summarv/ List of Follow-UD Matters (Open) o The Committee instructed Mr. Michelson, ACRS Chairman, to bring to the attention of Mr. Taylor, EDO, the potential impact on ACRS activities of the summary report dated March 26, 1990 that was prepared by Mr. Kenyon, NRR, regarding the Committee's deliberations and preliminary decisions related to the ELWR certification issues.
-(Mr. Michelson has already brought this matter to the attention of the EDO.)
o During the May 10-12, 1990 ACRS meeting, the Committee decided to discuss additional issues, other than those identified by the staff in SECY-90-016, that it believes should be considered by the staff for the ELWRs.
(Mr.
Quittschreiber has the follow-up action on this matter.)
t o
Tha Committee decided that the planning and Procedures Subcommittee should review the new procedures approved by Chairman Carr for appointment of new ACRS Members - and develop a recommendation for consideration by the full Committee during the May 10-12, 1990 ACRS meeting.
A meeting of the Planning-and Procedures Subcommittee scheduled for May 9,
1990 to discuss this. matter was subsequently postponed to June 6, 1990.
Therefore, this
i i,
f-360th ACRS Meeting 22 l
i l
matter is expected to be discussed by the committee during the June 7-9, 1990 ACRS meeting.
(Mr. Fraley has. the follow-up action on this matter.)
o During the May 10-12, 1990 meeting, the Committee will try 1
to develop a detailed agenda for the meeting. with the Japanese representatives which.is tentatively scheduled to be held between September 16-21, 1990.
(Mr. Fraley and Mr.
Quittschreiber have the follow-up action on this matter.)
Mr. Fraley informed the Members that if they want to visit o
the MDH containment facility on June 29, 1990 during their visit to Germany, they would not be able to depart for the t
U.S.
on June 29, 1990 as sc.5edu.ied previously.
He suggested that those who want to vf pit the MDH f acility let him know as soon as possible.
(Mr.
Fraley and Mr.
Quittschreiber have the follow-up action on this matter.)
o The Committee decided to discuss further the NRC staff's Regulatory Impact Survey of Selected Utilities after the staff has completed its final assessment of the results of the survey and taken a position whether the NRC should change its regulatory approach to ensure continued safe i
operation of nuclear power plants.
(Mr. Quittschreiber has the follow-up action on this matter.)
o Mr.
Ward requested that the Members provide written comments within two weeks on a draft paper, prepared by
- him, regardingt Matrix of Containment Functions /
Features / Issues; current NRC'and Iridustry Position, and Proposed ACRS Position.
(Mr. Houston has the follow-up action on this matter.)
l l
o The Committee decided to review the restart of Browns Ferry Unit 2.
Mr. Wylie, Chairma6 of the TVA Plant Licensing and Restart Subcommittee, agreed to hold a meeting to review
~
the restart and TVA organizational issues associated with this plcnt.
A Subcommittee meeting, including site visit, has been scheduled tentatively for July 24-25, 1990.
(Mr.
Houston has the follow-up action on this matter.)
o The Committee suggested that the ACRS Subcommittees on Computers in Nuclear Power Plant Operations and on Instrumentation and Control Systems hold a joint meeting to discuss the CE, GE, and Westinghouse approaches to advanced solid state control systems and control room l
designs.
(Mr. Boehnert and Dr. El-Zeftawy have the follow-up action on this matter.)
c 4
e
a 360th ACRS Meeting 23 o
Dr. Sheron, RES, agreed to provide written information, as requested by Dr. Kerr, regarding the progress being made i
by RES in addressing the following issues included in the Severe Accident Policy Statement.
(1:r. Houston has the follow-up action on this matter):
"A clarification of containment performance j
expectations will be made including a decision on whether to establish new performance criteria for i
containment systems and, if so, what these should be."
l "The Severe Accident Research Program as well as NRC's extensive severe accident studies of certain individual plants will aid in determining the extent to which carefully analyzed reference plants can appropriately serve as surrogates for a class of similar plants as the basis for_
any generic conclusions.
Any generic changes that are identified as necessary for public health and safety will be required through rulemaking and will be consistent with the commission's backfit policy."
o During the discussion of SARP, Dr. Catton requested a copy of the ANL report on core melt spreading experiments.
Dr. Eltawila, RES, agreed to provide a copy of this report.
(Mr. Houston has the follow-up action on this matter.)
Mr. Michelson suggested tha't the ACRS staff provide copies o
of NUREG/CR-4674 related to the Accident Sequence Precursor Program to all ACRS membc"s.
(Mr. Alderman has distributed copies of this document to all members on April 16, 1990.)
o Mr. Carroll proposed, and the Committee agreed, that there is no need to discuss the Proposed Rulemaking on the Emergency Response Data System at a subcommittee meeting; staff presentation to the full Committee would be sufficient.
This matter is tentatively scheduled for discussion by the full Committee during the June 1990 ACRS meeting.
(Mr. Boehnert has the follow-up action on this matter.)
o Mr. Michelson requested that the Members provide comments within a week on.the proposed revisions to subcommittee assignments.
Comments received from the members have been incorporated and a revised list of subcommittee assignments f
< *. ~.
w m
e 360th ACRS Meeting 24 distributed on April 27, 1990.
(Dr. Savio has the follow-
,?
up action, if any, on this matter.)
E.
Future Activities (Open) 1.
Future Aaanda The Committee agreed on a tent stive future agenda for the 361st ACRS meeting as shown in Appendix II.
2.
Future Subcommittee Activities A list of future ACRS subcommittee meetings was distributed to Committee members (Appendix III).
The meeting was recessed at 2:30 p.m. on April 7, 1990, reconvened on April 18, 1990 at 3:15 p.m.
for further discussion of proposed ACRS reports, and adjourned on April 19, 1990 at 2:30 p.m.
O e
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f 6
t APPENDICES MINUTES OF THE 360TH ACRS MEETING f
APRIL 5-7 AND 18-19, 1990 I.
Attendees II.
Future Agenda t
III.
Future Subcommittee ~ Activities-I IV.
Other Documents Received r
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APPENDIX I ATTENDEES 360711 ACRS MEETING APRIL 5-7, 1990 TillfRS D AY. APRIL 5.
1990 l'gblic Attendees NRC Attendees Eve Potopoulos, SERCil Licensing, Bechtel J. L. Caron, RES Margo Barron, NUS Corp.
K. Olive, OC Darius Depa, Illinois Dept. of Nucl. Safety E. lieumann, OC L. N. R. S,
[ sic), ABCLT A. Vietti-Cook, 001/EC i
J. F. Quirk, GE
- 11. Pactis, NRR C. D. Sawyer, GE M. Taylor, OEDO J. D. Trottor, EPRI R. Archittel, NRR R. Marriott, GE J. Kudrick, NRR W. T. Pratt, BNL D. Scaletti, NRR S. L. Additon, TENERA J. Rogge, OEDO L. Corinor, The NRC Calendar L. Norrholm, OCM/KC B. Claudia, NRC C. L. Miller, NRR A. Burda, RES E. Beckjord, RES PRIDAY. APRIL 5. 1990 Public Attendees NRC Attendeen l'hyllis Rich, NUMARC C. D..Pederson, III Margo Barron, NUS Corp.
A. Bert Davis, R III John MacEvoy, Bishop Cook Purcell& Reynolds Tom Cox, NRR Dave Noonan, SERCll Lic., Bechtel M. Virgilio, NRC Masashi Yokoler, Tokyo Electric PWR L. Plisco, NRR R. Borsum, BWNS Co.
J. hopkins, NRR David Modeen, HUMARC T. Murley, NRR Claudia Guild, Bishop Cook Purcell&Reynolds H. Pastis,- NRR B. Virg, Wright & Talisman R. Virgilio, GPA Darius Depa, Illinois Dept. of Nucl. Safety E. Doolittle, OCM/PR Edward P. Griffing, NUMARC V. Clifford, OEDO Bill Rasin, NUMARC G. Grant, NRR Kurt Cozens, NUMARC L. Whitney NRR Don Edwards, YAEC G. Mizunno, OGC Tricia tieroux, NUMARC W. Farmer, RES Terry olckens, Northern States Power Co.
R. Bosnak, RES Patrick Ward, Grove Engr.
J. J. Burry, RES John Trotter, EPRI J. W. Crcig, NRR D. Calandre, Bishop Cook Purcell&Reynolds Gerry Gears, NRR B. Pranklin, McGraw-flill Bill Borchardt, OEDO Dan Glossing, DOE F. Akstulewicz, NRR Scott llumphries, SCIENTEC11 Karl Kniel, RE3 Vince Panciera, SCIENTECll Paul Norlan, RES John O.~ Thoma, NRR Don Cleary, RES George Sege, RES William Travers, NRR Tom King, RES Elise lieumann, OC A. Vietti-Cook, OCM/KC Beth Doolittle, OCMliR Jack lleltomes, RES J. Vora, RES Dave Trimble, OCM/JC M. Taylor, OEDO L. Norrholm, OCM/KC h
APRIL 18. 1990, lQUJ;SJ1AY.
John Trotter, EPh1 D. Scaletti, NRR K. ilart, SECY TilDR?iD11 M lli 19. 19M :
John Trott gr, l'.P R I D. Sealott1, IIRR
360th ACRS Mseting Minutos APPENDIX II TENTATIVE SCHEDULE FOR Ti!E 361ST ACRS MEETING, MAY 10-12, 1990
\\
The Committee agreed to the tentative schedule for the 361st ACRS meeting, May 10-12, 1990 Briefing and o
Reactor _Oneratina Ernerience (Ocen) discussion of NRC activities related to reactor operations and nuclear plant operating events.
o Sitina of Nuclear Power Plants (Onen) - Briefing by NRC staf f representatives regarding their efforts to decouple nuclear plant siting and source term.
o Decommissionina of Nuclear Power Plants (Onen),- Briefing by representatives of the NRC staff regarding the status of decommissioning of the Shoreham Nuclear Power Station (SECY-90-084).
o Individual Plant Examination for External Events (Onen)
The Committee will hear a briefing and discuss a proposed NRC generic letter regarding consideration of external events in Individual Plant Examinations (IPEs).
o Maintenance Performance. Indicators (Ocen) - Briefing by NRC staff representatives on the status of work related to the development of maintenance performance indicators.
o Accident Secuence Precursor Procram (Onen) - Briefing on the status of the NRC-sponsored Accident Sequence Precursor Program.
Representatives of the NRC staff and the ORNL will participate as appropriate.
(NOTE:
This item has been deferred to the June 7-9, 1990 ACRS meeting.)
o NRC Acina Research Procram (Onen) - Briefing by repre-sentatives of NRC staff and industry, as appropriate, regarding the NRC research program on aging of nuclear power plants.
o ACRS Subcommittee Activities (Ocen) - Status of report.s and discussion of designated ACRS subcommittee activities including evaluation of BWR core power instabilities at reduced power / flow conditions.
o future b.CRS Activities (Open) - Discv ; anticipated ACRS subcommittee activities and-iti.as proposed for i.
consideration by the full Committee.
o Jygparathn of ACRS Reports (Open) - The Committee will 1
discuss comments and recommendations resulting irom matters considered during this meeting.
a 360TH ACRS MEETING APPENDIX III FUTURE SUBCOMMITTEE ACTIVITIES l
Revised: April 7,1990 3
ACRS/ACNW COMMITTEE & SUBC.QMMITTEE MEETf 4
+
i April 7, 1990 J,oint Severe Aggfidents and Prohgbilistic Risk Assessment, April 18, 1990, 7920 Norfolk Avenue, Bethesda, MD (Houston), 8:30 a.m., Room P-110.
The Subcommittees will continue their discussion of NUREG-1150, " Severe Accident Riskst An Assessment. for Five U.S.
Nuclear Power Plants." Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of April 172 Dr. Kerr
.NONE Dr. Siess(tent.) HOLIDAY INN Dr. Lewis EMBASSY SUITES Mr. Bender HOLIDAY INN Dr. Catton HOLIDAY INN Nr. Davis NONE Mr. Ward HOLIDAY INN Dr. Lee HOLIDAY INN Mr. Wylie HOLIDAY INN Dr. Okrent(tent.)NONE Mr. Michelson DAYS INN (CONGR)
Dr. Saunders HOLIDAY INN i
Dr. Shewson NONE Dr. Johnson NONS qccunational a:vi Environmental Pggtection Systems, April 25, 1990,
- POSTPONED:
Per J. Bell, RES, slipped to May/ June timeframe.
, Joint Advanced Pressurized Water Reactors and Advanced Boilina Water Reactgrg, April 26, 1990 - POSTPONED.
t 19th ACNW Meetina, April 26-27, 1990, Bethesda, MD, Room P-110.
Joint Thermal Hydraulic Phenomena and Core Performance, April 27, 1990, Bethesda Holiday Inn, 8120 Wisconsin Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Pennsylvania Room.
The subcommittees will continue their review of boiling water reactor core power stabil-ity pursuant to the core power oscillation event at LaSalle County Station, Unit 2.
Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of April 26:
Dr. Kerr NONE Dr. Lipinski HOLIDAY INN -
Dr. Catton HOLIDAY INN Dr. Plesset HOLIDAY INN Mr. Ward HOLIDAY INN Mr. Schrock HOLIDAY INN Mr. Wylie HOLIDAY INN Dr. Sullivan liOLIDAY INN Dr. Lee llOLIDAY INN Materials and Metallurav, May 1, 1990 - POSTPONED.
e.
1 l
2 Advanced Reactor Desians, May 2, 1990 POSTPONED Reliability Aggurance/ Materials and Meta 11urav, May 8,-1990, 7920 Norfolk Avenue, Bethesda, MD (Igne), 8:30 a.m., Room P-110.
The Subcommittees will discuss the status of the Nuclear Plant Aging l
Research (NPAR) Program and the industry efforts for dealing with the aging-related issues with regard to license renewal.
Lodging will be announced later.
Attendance by the following is anticipated:
Mr. Wylie Mr. Carroll Dr. Shewmon Dr. Siess (tent.)
Mr. Ward Mr. Michelson Imoroved Licht-Water _Reacto.ra, May 9,
- 1990, 7920 Norfolk Avenue, Bethesda, MD (El-Zof tawy), 8 : 30 a.m., Room P-110. The subcommittee will review the "pansive plant" designs of Westinghouse, combustion Engineering, General Electric and the EPRI's future passive plant requirements document.
Lodging will be announced later.
Attendance by the following is anticipated:
Mr. Wylie Dr. Siess Dr. Catton Mr. Ward l
Mr. Michelson l
Plannino and Procedures (Closed), May 9, 1990, 7920 Norfolk Avenue, l
- Bethesda, MD (Fraley),
(est.
5:30 p.m.
6:30 p.m.),
after completion of Improved LWR's Subcommittee meeting, Room P-110.
The Subcommitten will discuss procedures for-appointment /
reappointmont of ACRS members and for election of Committee Officers.
Lodging will be announced later.
Attendance by the following is anticipated:
1 Mr. Michelson Mr. Carroll Mr. Wylie 361st ACRS Meetino, May 10-12, 1990, Bethesda, MD, Room P-110.
20th ACNW Moetina, May 23-25, 1990, Bethesda, MD, Room P-110.
I 3
1 Materials and Meta 11urov, May 24, 1990, Royce Hotel,1601 Belvedere Road, West Palm Beach, FL (Igne). 8:30 a.m., Atrium Room.
The i
Subcommittee will review low charpy upper shelf energy matters relating to the integrity of reactor pressure vessels.
Attendance by the following is anticipated, and reservations have been made at the Royce Hotel (407/689-6400) for the night of May 23:
Dr. Shewmon Mr. Wylie (tent.)
Dr. Lewis Dr. Bush Mr. Michelson Mr. Etherington NONE Mr. Ward i
Thermal Hydraulic Phenomena, May 31-June 1,
1990, Bgthesda, MD (Boehnert) The Subcommittee will discuss the status of several research programs including:
the 2D/3D Program, Calculational Capability for Accident Management, and the RELAP/SCDAP and TRAC /MELCOR codes.
Lodging will be announced later.
Attendance by the following is anticipated.
Dr. Catton Dr. Plesset Dr. Kerr (tent.)
Mr. Schrock Mr. Ward Dr. Sullivan Mr. Wylie Quality and Ouality Assurance in Desian and Construction, Date to be determined (May/ June)
(tentative), Bethesda, MD (Igne).
The Subcommittee will discuss the performance-based concept of quality, l
What it means, its implementation, and preliminary results.
Attendance by the following is anticipated:
Dr. Siess Dr. Stevenson Mr. Ward Mr. Cerzosimo (tent.)
l Mr. Wylie I
Jnoroved Licht-Water Reactorg, Date to be determined (May),
l Hgthesda, MD (El-Zeftawy).
The Subcommittee will review the draft SER for Chapter 5
of the EPRI ALWR Requirements Document.
Attendance by the following is anticipated:
l Mr. Wylie Dr. Siess Dr. Catton Mr. Ward Mr. Michelson l
l
j 4
1 Decay Heat Removal Systems, Date to be determined (May), Bethesda, MQ (Boehnert).
The Subcommittee will continue its review of the proposed resolution of Generic Issue 23, "RCP Seal Failures."
Attendance by the following is anticipated:
Mr. Ward Mr. Michelson (tent.)
Dr. Catton Mr. Wylie Dr. Kerr Mr. Davis Joint Advanced Pressurized Water Reactors and Advanced Boilina Water Reactors, Date to be determined (May/ June), Bethesda, MD (El-Zeftawy/ Alderman).
The Subcommittees will discuss the licensing review basis documents for CE System 80+ and GE ABWR designs.
Attendance by the following is anticipated:
Mr. Carroll Mr. Ward Mr. Mi :helson Mr. Wylie Dr. Catton Dr. Shewmon Dr. Kerr Joint Severe Accidents and Probabilistic_ Risk Assessment, Date to i
be determined (May/ June), Bethesda, MD (Houston).
The Subcom-mittees will continue their review of NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants." Attend-ance by the following is anticipated:
Dr. Kerr Mr. Wylie Dr. Lewis Mr. Bender Dr. Catton Mr. Davis Mr. Michelson Dr. Lee Dr. Shewmon Dr. Okrent Dr. Siess Dr. Saunders Mr. Ward Occuoational and Environmental Protection Systems, Date to be determined (May/ June), Bethesda, MD (Igne).
The Subcommittee will review the Advance Notice of Proposed Rulemaking on hot particles.
Attendance by the following is anticipated:
Mr. Carroll Dr. Moeller Mr. Wylie I-
i a
5 Materials and Metallurov, Date to be determined, Bethesda, MD (Igne).
The Subcommittee will review the proposed resolution of Generic Issue 29, " Bolting Degradation or Failure in Nuclear Power Plants."
Attendance by the following is anticipated:
Dr. Shewmon Mr. Ward Dr. Lewis Mr. Bender Mr. Michelson Dr. Kassner Thermal Hydraulic Phenomena, Date to be determined (July?), Idaho Falls, ID (Boehnert).
The Subcommittee will review the details of the modifications made to the RELAP-5 MOD-2 code as specified in the MOD-3 version.
Attendance by the following is anticipated:
Dr. Catton Dr. Plesset Dr. Kerr Mr. Schrock Mr. Ward Dr. Sullivan Mr. Wylie Dr. Tien Decay Heat Removal Systems, Date to be determined, Eethesda, MD (Boehnert).
The Subcommittee will explore the use of feed and bleed for decay heat removal in PWRs.
Attendance by the following is anticipated:
Mr. Ward Mr. Michelson (tent.)
Dr. Catton Mr. Wylie i
Dr. Kerr Mr. Davis Decay Heat Removal Systems, Date to be determined, Bethesda, MD (Boehnert).
The Subcommittee will review the NRC staff's proposed resolution of Generic Issue 84, "CE PORVs."
Attendance by the following is anticipated.
Mr. Ward Mr. Wylie Dr. Catton Mr. Davis Dr. Kerr
, Auxiliary and Secondary Systems, Date to be determined, Bethesda, MD (Duraiswamy).
The Subcommittee will discuss:
(1) criteria being used by utilities to design Chilled Water Systems, (2) regu-latory requirements for chilled Water Systems design, and (3) criteria being used by the NRC staff to review the Chilled Water Systems design.
Attendance by the following is anticipated:
Dr. Catton Mr. Michelson Mr. Carroll Mr. Wylio
i s
s 4.
6 I
Reliability Assurance, Dato to be determined, Bethesda.
MD (Duraiswamy).
The Subcommittee will discuss the status of imple-montation of the resolution of USI A-46, " Seismic Qualificatien of Equipment in Operating Plants,"
and other related matters.
Attendance by the following is anticipated:
Mr. Wylie Mr. Michelson Mr. Carroll Dr. OMos Joint neaulatory Activities and Containment Systems, Date to be determined, Bethesda, MD (Duraiswamy/ Houston).
The Subcommittees will review the proposed final revision to Appendix J to 10 CFR Part 50, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors."
Attendance by the following is antic-ipated:
Dr. Siess Dr. Kerr Mr. Ward Mr. Michelson Mr. Carroll Mr. Wylie Dr. Catton
(
.,e t
i e
i APPENDIX IV MINUTES OF THE 360TH ACRS MEETING APRIL 5-7 AND APRIL 18-19, 1990 OTNER DOCUMENTS RECEIVED MEETING NOTEBOOK Tab 2
INDIVIDUAL PLANT EXAMINATION FOR EXTERNAL EVENTS PROGRAM e
Tentative Schedule Status Report with attachments:
o Memorandum to R. Fraley from W. Minners, RES, dated March 8, 1990,
Subject:
Proposed Generic Letter on Individual Plant Examination for Severe Accident vulnerabilities Due to External Events (IPEEE) with Attachments:
PROPOSED SECY paper,
Subject:
Individual Plant Examination for Severe Accident Vulnerabilities Due to External Events (IPEEE)
(INTERNAL f&MMITTEE USE ON_L L DRAFT NUREG-xxx,
" Procedural and Submittal Guidance for IPEEE for Severe Accident Vulnerabilities,"
dated February 27, 1990.
(INTERNAL COMMITTEE USE ONLY)
Letter to C. P. Siess, Subcommittee Chairman, ACRS, I
from W.
- Rasin, NUMARC, regarding invitation to address April 5, 1990 ACRS full Committee meeting te IPEEE, dated April 2, 1990 3.1 List of Future ACRS Subcommittee Meetinas- & ACRS and ACNW-l Meetinas 5
EVOLUTIONARY LIGHT WATER REACTOR CERTIUCATION ISSUES Tentative Agenda Status Report with Attachments:
" Evolutionary Light Attachment I Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory. Requirements,"
dated January 12, 1990 Attachment II - Memorandum from S. Chilk, Secretary for J.
Taylor, EDO and C.
Michelson, ACRS, Re:
" Staff Requirements SECY-89-334 Recommended Priorities for Review of Standard Plant. Designs,"
dated December 15, 1989.
l l
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360th ACRS Meeting Minutes Appendix IV-2 Attachment III Memorandum from S.
- Chilk, Secretary, for J.
Taylor, EDO and C.
Michelson,
- ACRS, Re:
" Staff Requirements SECY-89-311,
" Resolution Process for Cevere Accident Issues on Evolutionary Light Water Reactors," dated December 15, 1989 Attachment IV - Memorandum from R. Fraley, ACRS to ACRS
- Members, Re:
Certi:*iction Issues for Evolutionary LWRs, dated March 1, 1990 SECY-90-056, "Evoplutionary and Attachment VI Passive Advanced Light Water Reactor Resources and Scheduled," dated March 17,.-1990.
Presentation materials provided during the meeting.
e 7
NRC REGULATORY IMPACT SURVEY e
Presentation Schedule Project Status Report with Attachments:
e Excerpt from DRAFT NUREG-1395, Summary of Significant Survey Comments (IRTERNAL COMMITTEE U S E O N I,d(,L Excerpt from SECY 90-080 " Initial Staff Ar.sessment" (INTERNAL COMMITTEE USE ONLYL Presentation materials provided during the meeting e
8 SEVERE ACCIDENT RESEARCH PROGRAM PLAN Tentative Agenda e
e Status Report with Attachments:
NUREG-1365, Revised Severe Accident Research Program, August 1989 ACRS Report on Severe Accident Res 3 arch Program, March 15, 1989 Overview of Status of Severe AcciCent Research Program - Handout by B.
Sheron for March 20, 1989 Severe Accident Subcommittee meeting Presentation materials provided during the meeting.
e 9
LICENSE RENEWAL DRAFT RULE o
Presentation Schedule e
Status Report with Attachments:
Existing 10 CFR 50.51 Requirements for License and License Renewal.
DRAFT Proposed Rule " Requirements for Renewal of Operating Licenses for-Nuclear Power Plants" (INTERNAL COMMITTEE USE ONLY)
Backfit Considerations - Staff's discussion in the Statement of Considerations (JNTERNAL COMMITTEE USE ONLY)
,.s 360th ACRS Meeting Minutes Appendix IV-3 MEETING ljANDOUTS penda Item i
3.1 List of Scheduled ACRS/ACNW Committee & Subcommittee Meetings (same as distributed in April 5-7, 1989, 360th ACRS Meeting Notebook) 3.2 Memorandum for ACRS Members from R.
Savio, ACRS,
Subject:
Future ACRS Activities - 361st ACRS MEETING, MAY 10-12, 1990 with attachments, dated April 4, 1990.
i 3-3 Memorandum to ACRS Members from R. Savio,
Subject:
Proposed Revised ACRS Subcommittee Assignment / Adopted Plants Lists PHO-IIT-90-02A, date.d March 29, 1990 - Vogtle Unit 1 - truck backing into support post for 230kV line i
Nuclear Regulatory Commission - Charter - Nuclear Safety Research Review Committee, Filing Date February 9, 1990 /s/ Js C.
Subject:
Summary of March 8-10, 1990 ACRS meeting on SECY-l 90-0\\6, dated March 26,'1990 with Enclosure 5-2 Memorandum to Mr. Kenyon, NRR, from L. A. Keller, forwarding Optimization Subject papers that were originally given to NRC 3
for the Evolutimary ALWR, undated with " Enclosure 3: Advanced LWR Plant Optimitation Subjects for Chapter 1
of the Requirements Document, dated March 12, 1986, Contents 1.0, Introduction and Summary; 2.0 ALWR Approach, 3.0 Plant optimization Subjects.
10-1 Memorandum dated March 30, 1990 to C. Michelson, ACRS from R.
Fraley,
Subject:
Appointment of New Committee Members with Attachments - INTERNAL COMMITTEE USE ONLY I
l j
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360th ACRS Meeting Appendix IV-4 CatCtIEUATION OF 360TH ACRS MEET 7NG, APRIL 18-19, 1990 Meetina Rotebook 2.1 EVOLUTIONARY LICitT Jf4TER REACTOR CERTIFICATION ISSUES Tentative Agenda e
Status Report with Attachments:
e SECY-90-016,
" Evolutionary Light Attachment I Water Reactor (LWR) Certification Issues and Their Relationship to current Regula ory Requirements,"
dated January 12, 1990 Attachment II - Memorandum from S. Chilk, Secretary for J.
Taylor, EDO and C.
Michelson, ACRS, Re:
SECY-89-334 Recommended
" Staff Requirements Priorities for Review of Standard Plant Designs,"
dated December 15, 1989.
Memorandum from S.
- Chilk, Attachment III Secretary, for J.
Taylor, EDO and C.
Michelson,
- ACRS, Re:
" Staff Requirements SECY-89-311,
" Resolution Process for Severe Accident Issues on Evolutionary Light Water Peactors," dated December 15, 1989 Attachment IV - Memorandum from R.
- Members, Re:
Certifiction Issues for
)
Evolutionary LWRs, dated March 1, 1990 SECY-90-056,
" Evolutionary and Attachment VI Passive Advanced Light Water Reactor Resources and Schedules," dated March 17, 1990.
l l
l 2.2 GEVERE ACCIDENT RESEARCH PROGRAM PLAN Table of Contents Tentative Agenda Status Report with attachments (see Agenda Item Tab 8 on p.
2 above of Appendix IV re April 5-7, 1990 meeting notebook and i
l handouts): NUREG-1365, ACRS Report of March 15, 1989, and_B.
j Sheron, NRR, April 6, 1990 Slides.
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