ML20059C724
| ML20059C724 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/10/1992 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2854, NUDOCS 9311010280 | |
| Download: ML20059C724 (51) | |
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TABLE OF CONTENTS MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10, 1992 I.
Chairman's Report 1
II.
Boiling Water Reactor Stability.........................
.1 III. Design Acceptance-Criteria..............................
4 IV.
Environmental Qualification of Electrical Equipment for License Renewal.....................................
5 V.
Form and Content for a Design Certification Rule........
6 VI.
Reconciliation of ACRS Comments and Recommendations.....
7 VII. Maintenance of Nuclear Power Plants.....................
9 VIII.
Renewal of Nuclear Power Plant Operator Licenses and Requalification..........................
11 IX.
Use of PRA in the Regulatory Process....................
13 i
X.
Environmental Qualification of Safety-Grade Digital Computer Protection and Control Systems.................
15 XI.
Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for GE ABWR Design.....................
16 XII.
Yankee Rowe Nuclear Power Plant........................
16' XIII.
Miscellaneous Candidates for the "NRC Thermal Hydraulic" Review Group.......................................
18 Availability and Adequacy of Design Bases e
Information........................................
18 Visit to Eastern European Nuclear Power Plants e
by the ACRS Chairman...............................
18 XIV. ACRS Subcommittee Activities Appointment of ACRS Members........................
19 e
e Election of ACRS Officer...........................
19 020002 IC :GIE ED ORIGINAL g
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4 ii e
Editing ACRS Reports...............................
19 e
" Stock" Ownership by ACRS Members..................
19 e
ACRS Meeting Calendar for 1992.....................
19 e
Report on the International Meeting on Computers Held on September 22, 1992.........................
20 XV.
Preparation of Other ACRS Reports and Memoranda........
20 YVI. Executive Session e
Reports 20 Memoranda.........................................
21 XVII.
Future ACRS Activities................................
21 e
Second Quadripartite Meeting of Advisory Committees.........................................
21 XVIII. Summary / List of Follow-Up Matters.....................
22 Supplement - Proprietary (SUPPLEMENTS REMOVED FOIA EX(b) (4)]
~
Supplement - Official Use Only
(
?
'ii.
APPENDICES MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10, 1992
'F I.
Attendees II.
Future Agenda l
III.
Future Subcommittee Activities IV.
List of Documents Provided to the Committee i
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Federal Registir7oli 57cNo.190 / Thursday, October r-~p92 / Notices'E.gfh46411-
[
.k
. With regard to pot 6ntial non?.
proposed positions and actions, as Dated: october 1.1992..
r radiologicalimpacts, the proposed i~ - appropriata, for deliberation by the full R_K. Major.
I
.,.. exemptions involve features located Committee. '
Chief. Nuclear Wade Bronch.
.)
~
entirely within the restricted areas as-
..ne entire meeung will be open to
[rR Doc 92-2N99 riled 1o-7-42; 8:45 ml i
. defined in 10 CIR part 20.Dey do not ' public attendance.
}
affect non-radiological plant elliuents <
ne agenda for the subject meeting and have no other environmental -
shall be as follows:
impact: therefore the Commission Tuesday OctoberM 1992---B:30a m.
Advisory Committee on Reactor concludes that there are no significant Untilthe Conclusian ofBusiness Safeguards; Revised Meeting Agends non-radiological environmental impacts associated with the proposed
%e Working Group will discuss the in accordance with the purposes of exemption.
potential for the presence of significant Sections 29 and 182 b. of the Atomic resources at the proposed Yucca Energy Act (42 U.S.C. 2039,2232b) the Altemative Use ofResourres Mountain high-level waste repository.
Advisory Committee on Reactor
%ie action does no't involve use of Applicable NRC and DOE regulations Safeguards will hold a meeting on resources not previously considered in contain statements regarding the need to October 8-10.1992, in room P-110,7920 the Final Environmental Statement for avoid sites with significant natural Norfolk Avenue.Bethesda, Maryland.
tl e H.B.. Robinson Steam Electric Plant, resources.%e presence of significant Notice of this meeting was published in natural resourcescincluding the FederalRegister on September 23 Unit No.2. dated April 1975.
groundwater, at or near the site of a -
1992. Portions of this meeting on Friday Agencies andPeisces Corrsulted proposed high-level waste repository is and Saturday. October 9 and 10.1992 He staff reviewed the licensee's an adverse situation, that could have been revised to accommodate request and did not consult other potentially lead to a disqualifying additional sessions.
agencies or persons.
condition. lt is perceived that the presence of such resources in the Friday, October 9.1992 Finding of No S.ignificant impact vicinity of the site could give rise to B.30 a.m.-10 a.ma Afaintenance of ne Commission has determined not activities that would eventually lead to NuclearPowerPlants (Open)-ne -
to prepare an environmentalimpact inadvertent human intrusion into the Committee will review and comment on statement for the pmposed exemption.
repository..
a proposed Regulatory Analysis and a Based upon the foregoing envimnmental Oral statements may be presented by draft Regulatory Guide. " Monitoring the assessment, the staff concludes that the members of the pubhc with the Effectiveness of Maintenance at Nuclear proposed action will not have a concurrence of the ACNW Working Power Plants." and an associated significant,effect on the quality of the Group Chairman; wntten statements NUMARC document 93-01. Revision 2A.
human envimnment.
will be accepted and made available to
" industry Guideline for Monitoring the For further details with respect to this the Working Group. Reconiings will be Effectiveness of Maintenance at Nuclear acnon. see the request for exemption permitted only during those sessions of Power Plants." -
dated January 22.1992, which is the meeting when a transcript is being Representatives of the NRC staff and available for public inspection at the kept, and questions may be asked only Commission's Publ;c Document Room, by members of the ACNW Working the nuclear industry will participate, as -
appropriate..
the Gelman Building. 2120 L Street. NW., Group,its consultants, and staff.
Washington. DC 20555 and 'at the local Persons desiring to make oral W5 a.m.-W5 a.ma Pieparofw, n of statements should notif the ACNW '
- ACRSRePorts (Open)-ne Comrmttee Public Document Room located at the staff member named befow as far inwm discuss the scope and content of Hartsville Memorial Library, Home and Fifth Avenues,Hartsville. South advance as is practicable so that reports to be considered during th,s i
Carolina 29535.
appropriate arrangements can be made. muting.
During the initial portion of the 10:45 a.m.-11:15 a.ma Trom, m.gand D ted at Roc'kville. Maryland this 2nd day meeting.the ACNW Working Group.
' RequalificationafNuclearPowerPlant along with any ofits consultants who Operators (Open)-%,e Committee will
^ * * * * *
- may be present, may exchange hear a briefing, discuss, and report as Director. Pmject Directomte Il-1. Division of preliminary views regardi matters to appropriate on results of the NRC pilot N' O/I'#' #I.#"d"'
be considered during the b71ance of thesimulator examination program and.
"d#'8#8 h#8-meeting '
proposed changes to NRC rule (10 CFR (G Doc. 92-24504 Filed W7-92; 8.45 am)
Further information regarding the part 55) regarding recertification of nuclear powe' plant operators.
agenda for this meeting, whether the r
meeting has been cancelled or
. Representatives of the NRC staff and ACNW Working Group on Potential for rescheduled, the Chairman's ruling on the nuclear industry will participate, as Presence of Natural Fiesources at a requests for the opportunity to present appropriate.-
tal statements and the time allotted 11:15 a.m.-12:15p.m.:Use of f/UL in High-Level Waste Repository Site, Meeting therefor can be obtained by a prepaid the RegulatoryProcess (Open)-The telephone call to the cognizant ACNW Committee will hear a briefing by he ACNW Working Group on staff engineer. Mr. Howard J. Larson, representatives of the NRC Working Potential for Presence of Natural ACNW (telephone 301/492-7707)
Croup on the status of tasks related to Resources at a High-Level Waste between 7:30 a.m. and 5:00 p.m. (EST).
use of PRA in the NRC regulatory Repository Site will hold a meeting on Persons planning to attend this meeting process.
October 70.1992, at the St.Tropez Hotel, are urged to contact the above named 1:15 a.m.-3:15 p.ma Design 455 East Harmon Avenue. Las Vegas.
Individual one or two days before the Acceptance Criteria (Open)-The NV.The purpose of this meeting is to scheduled meeting to be advised of any Committee will review and comment on gather information, analyze relevant changes in schedule, etc.. that may have proposed Design Acceptance Criteria issues and facts. and to formulate occurred.
(DAC)in the areas of man / machine
46412 Federal Regiew / Vol. 57. No.190 / Thursday. Octob9,1992 / Noticeo interface and cuntrol and protection candidates for the NRC
- Thermal.
Dated. Octotier 2. wn.
systems.
Ilydraulic" review group and matters lohn C. lforla.
Representatives of the NRC staff and which were not completed at previous Advisory committee Management Officn the nuclearindustry will participate as meetings as time and availability of lFR Doc.92-24498 Fded 10-7-02: 8:45 ami appropriete.
information permit.
-l a coag,s gg J:15 p.mA;15 p.m r YonAce Rowe Portions of this session will be closed Nuclear Power Plant (Open)-n" as necessary to discuss information Committee will hear a brichng by reganling the qualifications of Fifth Hecting of ttle SCDAP/RELAP5 '
representatives of the NRC staff candidates proposed for appointment to Peer Review Committee regarding lessons learned from the this review group, the release of which review and evaluation of the Yankee would represent a clearly unwarranted AGENm Nuclear Regulatory Howe nuclear plant reactor pressure invasion of personal privacy.
Comnussion.
pr sen t es iJ the NRC staff and Procedures for the conduct of and ACTION: Notice of meeting.
O2e nuclear industry wiil participate, as participation in ACRS meetings were 1
published in the Federal Register on suusdARY: %e SCDAP/RELAPS Peer 415 p
-3:15p.m.r Subcommittee and October 1.1991 (50 FR 49800). In Review Committee will hold its fifth Members Activities (Open/ Closed}--.
accordance with these procedures, oral yt2jcyto re w e I
The Commitlet will discuss the report or written statements may be presented q
and recommendations of the ACRS by members of the public, recordings caTrs: November 341992.
Pianning and procedures Subcommittee will be permitted only during those open regarding conduct of Committee portions of the meeting when a 73,g. 87 on each day.
business, the international meeting on transcnpt is being kept, and questions ADDRESSES:One White Flint North..
computers on September 22.1992, and may be asked only by members of the Rockville.
the visit to Eastern European nuclear Committee, its consultants, and staff.
FOR FURTHER $NFORasATION CONTACT:
f..
power plants by the ACRS Chairman Persons desiring to make oral Dr. Y.S. Chen. Office of Nuclear
.I and information provided to him by statements should notify the ACRS Regulatory Research. U.S. Nuclear representatives of the organizations Executive Director Mr. Raymond F.
Regulatory Commission. Washington.
responsible for the operation of these Fraley, as far in advance as practicable DC 20555, (301) 492-3566 facilities.
so that appropriate arrangements can be SUPPLEMENTARY WORMAN ne Portions of this session will be closed made to allow the necessary time during SCDAP/RELAPS Peer Review as necessary to discuss information thameeting for such statements. Use of Committee will hold its fifth meeting to provided in confidence by a foreign still motion picture, and television review the technical adequacy of the source.
cameras during this meeting may be SCDAP/RELAPS code on 5:15p.m.-6 Ap.m.: Election ofACRS limited to selected portions of the November 3-4.1992,in Rockville.
Officer (Closed)--The Committee will meeting as determined by the Chairman. Maryland.The SCDAP/RELAPS code discuss qualifications of candidates Information regarding the time to be set has been developed for best-estimate nocunated for Member-at-Large of the aside for this purpose may be obtained transient simulation oflight water Planning and Pmcedures Subcommittee, by a prepaid telephone call to the ACRS reactor coolant systems during severe This session will be closed to discuss Executive Director prior to the meeting.
accidents as well as large and small information the release of which would In view of the possibility that the break loss-of. coolant accident, and represent a clearly unwarranted schedule for ACRS meetings may be operational' transients such as mvaston of personal privacy.,
adjusted by the Chairman as necessary anticipated transient without SCRAM.
5:30 p.m.-6; Jap.m.:Paparation of to facilitate the conduct of the meeting.
loss of offsite power. loss of feedwater.
ACRS Reports (Open)--The Committee persons planning to attend should check and loss of flow.The code is based on will discuss proposed ACRS reports his with the ACRS Executive Director if three separate codes: FILAPS. SCDAP.
regarding matters considered during t such rescheduling would result in major and TRAP-MELT, which are combined meet ng.
Inconvenience.
to model the coupled interactions that Saturday October 10.1992 I have determined in accordance with occur betwoen the. Reactor Coolant 8:30 a.m.-f1:15 a.m.r Preparation of Subsection 10(d) Public Law 92-463 that System (RCS), the core, and the fission A CRS Reports (Open)--%e Committee it is riecessary to close portions of this products during a severe accident.%e wil! discuss proposed ACRS reports meeting noted above to discuss newest version of the code is SCDAP/
regarding matters considered during th!s Information provided in confidence by a RELAPS/ MOD 3. A number of meeting.
foreign source in accordance with 5 organizat? cms inride and outside the 11:15 can.-12 Noon: Appointment of U.S.C. 552(c)(4) and information the NRC are using or planning to use the ACRS Members (Closed)---The release of which would represent a current version. Although the quality Committee will discuss qualifications of clearly unwarranted invasion of control and validation efforts are seen candidates proposed for appointment as personal privacy per 5 U.S.C. 552(w(0).
to be proceeding, there is a need to have members of the Committee.
Further information regarding topics a broad technical review by recognized This session will be closed to discuss to be discussed, whether the meeting experts to determine the technical information the release of which would has been cancelled or rescheduled, the adequacy of the SCDAP and TRAP-i represent a clearly unwarranted Chairman's ruling on requests for the MELT portions of SCDAP/RELAP5 for invasion of personal privacy, opportunity to present oral statements the serious and mmplex analyses it is 1 p.m.-2;J0 p.m. Mescelloneous and the time allotted can be obtained by expected to perform.
+
(Open/ Closed}--%e Committee will
~a prepaid telephone call to the ACRS This meeting will focus on completmg complete discussions of items Executive Director. Mr. Raymond F.
the review, finalizing the summary considered during this snecting.
Fraley (telephone 301-492-8049),
report and receiving comments from the
'f,
including recommendations regarding between 8 a.m. and 4:30 p.m. EST.
NRC.
t r
/
%o, UNITED STATES NUCLEAR REGULATORY COMMISSION 3
E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS I
W ASHINGTON, D, C. 20686 o
%...*/
October.5, 1992, SCHEDUT1 AND. OUTLINE FOR DISCUSSION.
390TM ACRS MEETING OCTOBER 8-10, 1992 Thursday. October 8, 1992. Room P-110, 7920 Norfolk Avenue. Bethesda, Md; 8:45 A.M.
Ocenina Remarks by ACRE Chairman (Open) 1)
8:30 1.1)
Opening Statement (DAW /SD) 1.2)
Items of current interest (DAW /RFF) 1.3)
Discuss priorities for ACRS reports to be considered during this meeting (DAW /SD) 2)
8:45 9:45 A.M.
Boilina Water Reactor Stability (Open/ Closed)
TAB 2 ---------
2.1)
Report of ACRS subcommittee chairmen on issues pertaining to BWR core power stability (IC/ JEW /PAB) 2.2)
Meeting with representatives of the NRC staff and the nuclear industry, as appropriate (Portions of this session will be closed as-necessary to discuss Proprietary Information applicable to this matter.)
9:45
- 10:00 A.M.
BREAK 3) 10:00
- 12:00 Noon Desian Accentance Criteria (DAC), - (Open) 3.1)
Comments by ACRS subcommittee-chairman regarding DAC related.to TAB 3---------
Man / Machine Interface.and control and Prot'ection Systems (SECY-92-299).
Also, comments regarding updated information on-DAC.related:to pip,ing systema and radiation,.
prctection (JCC/MME).
c 3.2).
Meeting with representati.ves.of the..
NRC-staff and-the, nuclear. Industry, as appropriate-,
4 12:00 1:00 P.M.
LUNCH 2:30 P.M.
Environmental'OualificationofElectbcal 4) 1:00 Eauiement for License., Renewal-(Open) 4.1)
Comments by ACRS subcommittee UB W---
. ~.
2 1
chairman regarding proposed NRR Branch Technical Position on environmental qualificationJof electrical' equipment for license i
renewal (DAW /EGI) 4.2)-
Meeting:with representatives'of'the' NRC staffiand the nuclear industry, as appropriate 2:30 2:45 P.M.
BREAK
')
5) 2:45 4:45 P.M.
Form'and Content'for a Desian Certification-Rule (Open) 5.1)
Comments by ACRS subcommittee TAB 5---------
chairman on.SECY-92-287, Form and Content for a Design Certification' Rule (CJW/MME) 5.2)
Meeting with' representatives of the NRC staff and the nuclear industry, as appropriate 6) 4:45 5:30 P.M.
Future ACRS Activities (Open) 6.1)
Report of ACRS Planning and Procedures Subcommittee meeting on items proposed for consideration by the full Committee (DAW /RPS) 7)
5:30 6:00 P.M.
Reconciliation of Acan Co===nts and Recommendations (Open) 7.1)
Discuss replies fron-the NRC Executive Director for Operations regarding proposed reconciliation of ACRS comments and recommendations (DAW, et al./SD) 8)
6:00 6:30 P.M.
Discussion of Pronosed ACRB Positions'(Open) 8.1)
' Discuss proposed ACRS positions regarding matters considered during ~
this session,' including:
8.1-1)
BWR Stability. Issues (IC/ JEW /PAB) 8.1-2)
Environmental Qualification.
of Electrical Equipment for i
-(DAW /EGI) 1 8.1-3)
Form and Content for a' Design certification Rule (CJW/MME) i 8.1-4)
Design AcceptanceLCriteria (JCC/MME) 1
1 3
)
Friday, Og_tg_bo r 9, 1992. Room P-110. 7920 Norfolk Avenue, Bethesda, Maryland l
9) 8:30
- 10:00 A.M.
Maintenance of Nucigar Po'ger Plants (Open) 9.1)
Comments by ACRS subcommittee chairman regarding proposed TAB 9----------
regulatory analysis and draft regulatory guide, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and an associated NUMARC document 93-01, Rev. 2A, " Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" (JCC/HA) 9.2)
Meeting with representatives of the NRC staff and the nuclear industry, as appropriate 10:00
- 10:15 A.M.
BREAK
- 10) 10:15
- 10:45 A.M.
Scoce and Content of Procosed ACRS ReDorts (Open) j 10.1)
Discuss the scope and content of reports to be considered during this meeting (DAW, et al./SD)
- 11) 10:45
- 11:15 A.M.
Trainina and Oualification of Nuclear Power EJant ODerators (Open) 11.1)
Comments by ACRS subcommittee TAB 11---------
chairman regarding the NRC pilot program to examine use of simulators i
for operator training and requalifi-fication and changes to 10 CFR Part 55 regarding racertification of nuclear power plant operators (JCC/MA/VH) 11.2)
Briefing by representatives of the NRC staff, as appropriate
- 12) 11:15
- 12:15 P.M.
Use of PRA in the Reculatory Process (Open) 12.1)
Comments by ACRS subcommittee TAB 12---------
chairman regarding NRC program to use PRA in the regulatory process (HWL/MDH) 12.2)
Briefing by and discussion with representatives of the NRC staff regarding the status of the PRA Working Group activities 12:15 1:15 P.M.
LUNCH
l
~.
a 4
13) 1:15 2:15 P.M.
Environmental ouglifica' tion of Safety-Gradg Dioital Comouter Protection and Contral Systems (open)
TAB 13---------
13.1)
Comments by ACRS Subcommittee Chairman regarding proposed ACRS report on the NRC sponsored research program on environmental qualification of safety-grade digital computer protection and control systems (HWL/DC)~
13.2)
Briefing by and discussionsLwith representatives of the NRC staff, as appropriate i
14) 2:15
- 3 :d5 P. M.
Insoections. Tests, Analyses, and Accentance' (2:30 - 2:45: Break)
Criteria (ITAAC) for GE ABWR Desian (Open) 14.1)
Comments by ACRS subcommittee chairman regarding proposed ACRS.
report on NRC staff's review process with respect to the ITAAC for the GE j3 24 4 c 3%- 3 :, f-~
ABWR (CJW/EGI)
{
4:15 P.M.
Yankee R'ove Nuclear Power Plant (Open) 15) 3:15 15.1)
Comments by ACRS subcommittee chairman regarding lessons learned TAB 15----------
from the review and evaluation of the Yankee Rowe reactor pressure vessel integrity (PGS/EGI/MDH) 15.2)
Briefing by and discussions with representatives of the-NRC staff and the nuclear industry, as appropriate 16) 4:15 5:15 P.M.
ACRS Subcommittee and Mm=hers Activities (open/ Closed) 16.1)
Reports of ACRS subcommittee activities regarding:
16.1-1)
ACRS Planning and Pro-cadures, October 7, 1992 meeting (DAW /RFF) 16.1-2)
International Meeting on Computers in Nuclear Power Plant Operations, 9/22/92 meeting (HWL/DC)-
16.1-3)
Visit to Eastern European nuclear plants, Sept.-oct., 1992 (DAW /GRQ)
(Note:
Portions of this session will be-closed as necessary to discuss information provided in confidence by a foreign source.)
5 5:30 P.M.
Election of ACRS Officer (Closed) 17) 5:15 17.1).
Election of Member-at-Large of the ACRS Planning and Procedures Subcommittee meeting (DAW /RFF)
(Note:
This session will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.)
6:00 P.M.
Precaration of ACRS Recorts (Open) 18) 5:30 18.1)
Discuss proposed comments and recom-mandations regarding matters considered during this session, including:
18.1-1)
Maintenance of Nuclear Power Plants (JCC/HA) 18.1-2)
Design Acceptance criteria (JCC/MME)
Saturday, October 10, 1992, Room P-110, 7920 Norfolk Avenue, Bethesda.
Maryland 19) 8:30
- 11:15 A.M.
Precaration of ACRS Reoorts (Open) 19.1)
Discuss proposed ACRS reports regarding:
19.1-1)
BWR Stability (JCC/ JEW /PAB) 19.1-2)
Environmental Qualification of Safety-Grade Digital computer Protection and Control Systems (HWL/DC) 19.1-3)
Environmental Qualification of Electrical Equipment for License Renewal (DAW /EGI) 19.1-4)
Form and Content of a Design Certification Rule (CJW/MME) 19.1-5)
ITAAC for GE ABWR (CJW/EGI) 19.1-6)
Maintenance of Nuclear Power Plants (JCC/HA) 19.1-7)
Design Acceptance Criteria (JCC/MME) 19.1-8)
Proposed changes to 10 CFR Part 55 (JCC/HA/VH)
- 20) 11:15
- 12:00 Noon Anoointment of ACRS Members (Closed) 20.1)
Discuss qualifications of candidates proposed for consideration (DAW /MFL) 20.2)
Discuss proposed press release requesting nominations (Note:
This session will be closed to discuss information the release of which
6 would represent a clearly unwarranted invasion of personal privacy.)
1:00 P.M.
LUNCH 12:00 21) 1:00 2:30 P.M.
Miscellanggua (Open/ Closed)
I 21.1)
Proposed comments to OGC regarding limitations on " Stock" ownership by Committee members (10 CFR 0.735-28a)
(DAW /RFF) 21.2)
Recommendations regarding candidates for NRC Thermal-Hydraulic Review Group (JCC/IC/TSK/PAB) 21.3)
Proposed changes in ACRS Bylaws regarding:
21.3-1)
Editing ACRS reports (DAW /JCC/HWL/RFF) 21.3-2)
Suspension of Bylaws (HWL/JCC/RFF) 21.3-3)
Voting Procedures (HWL/RFF)
(Note:
Portions of this session will be closed as necessary to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.)
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MINUTES OF 390TH ACRS MEETING OCTOPTR 8-10, 1992 The 390th meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md.,
on October 8-10, 1992.
The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda.
The entire meeting was open to public attendance, with the exception of a portion that dealt with the selection of new Committee members and release of foreign information.
There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.
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, DC 20006.)
ATTENDEES ACRS Members:
D.
Ward (Chairman),
P.
Shewmon (Vice Chairman),
I.
- Catton, J.
- Carroll, H.
- Lewis, W.
- Lindblad, C.
Michelson, J.
E.
- Wilkins, T.
Kress, and C.
J.
Wylie. (P. Davis was in attendance as a non-voting member) 1.
Chairnan's Report (Open)
Note:
Mr.
S.
Duraiswamy was the Designated Federal official for this portion of the meeting.
Mr.
D.
Ward, ACRS Chairman, opened the meeting at 8:30 a.m.
and mentioned the following matters:
The agenda for this meeting.
e No written statements or time to make oral requests f rom members of the public.
Dr. El-Zeftawy is back from the Commission offices, e
Helen Pastis is back as the NRR liaison, e
Mr. Cogne of the GPR sent a letter to the ACRS saying they would like to sponsor a meeting in France in 1993.
A FAX was just received on an industry position on qualification of electrical equipment in license renewal indicating a bit of a difference of opinion between the staff and industry.
A 30 year service award was given to Carol Ann Rowe.
Sam Duraiswamy was given a 15 year service award.
II.
Boilina Water Reactor Stabi1it.y (Open)
Note:
Mr. Paul Boehnert was the Designated Federal Official for this portion of the meeting.
390th ACRS Meeting Minutes 2
j Introductory Comments Dr, Catton provided a report to the Committee on the status of the f
resolution effort.for the issue of BWR core power stability.
He noted that a meeting of the Joint Thermal Hydraulic Phenomena / Core-Performance Subcommittee was held on September 17, 1992 to review the actions of the BWR Owners Group, General Electric 11uclear Energy, and NRC-!JRR to close out this matter.
The resol-Ition approach is focused in two main areas: a so-called Long ' Term Solutions (LTS) program to address the control / mitigation of power oscillations assuming function of the RPS, and a program to address mitigation for the case of power oscillations accompanying an ATWS event.
Dr. Catton reminded the Committee that the latter case (ATWS with instabilities) is the only issue impacting plant risk.
Dr.
Catton recounted some of the history associated with the development of the ATWS Rule.
He noted that prior to its adoption, there were three rule versions under consideration by the Commission: a so-called Hendrie version, a utility version, and a staff version.
In the end, the strictures of the rule finally adopted by the Commission was based on a value/ impact analysis.
Of concern to Dr. Catton was that the Commission, in adopting the Rule, requested that a common-cause failure analysis be performed to determine the potential f aults of the RPS. Apparently, this work was not done; in his opinion, it should have been.
s Dr. Catton said that the Joint Subcommittee found that the staff has not yet issued an SER to close the issue of ATWS with instabilities.
The proposed resolution approach advocated by the Owners Group is to revise the EPGs to require that immediately upon confirmation of an ATWS, the operators both lower the vessel water level to the top of the fuel and immediately inject liquid boron.
Dr. Catton noted that during the September 17th Joint Subcommittee Meeting, Dr. Lipinski said that past experience with the maneuver of lowering vessel water level resulted in severe water hammer events.
Also of concern, is that the bounding analysis of the event consequences were performed with GE's TRACG code.
The uncertainties associated with these analyses are considered large.
Dr. Catton indicated that in his opinion, a rigorous. review to i
quantify the uncertainty associated with TRACG's calculations of ATWS/ instability events is needed.
Dr. Catton indicated that he is satisfied with the ef f ectiveness of the LTS program but is troubled with the poor quality of the OG approach.
For example, the OG is resisting use of plant process computers to determine the core power decay ratio on an on-line basis; another item is that the OG is not using autocorrelation techniques, which would provide a rapid detection of the onset of instabilities.
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Comments by the NRC Staff q
Mr. R. Jones (NRR) noted that the staff is reevaluating the impact of the risk from ATWS with oscillations vis-a-vis the ATWS Rule bases, in part due to receipt of a petition.
The OG has provided the staff with a PRA analysis that evaluates the impact of power 2
oscillations on the ATWS rule bases.
The staff has this analysis under review.
Jones said that a " quick-lock" at the GE analysis by NRR shows that the risk. is increased by - 10% for the case of ATWS with oscillations. In response to Dr. Catton, Mr. Jones said that he would determine if the fault / event tree analyses of the RPS, i
requested by the Commission in the SRM accompanying the ATWS Rule, was ever performed.
There was discussion of the uncertainty associated with the analytical predictions of the bounding limits for the oscillation amplitudes seen for the ATWS case.
Mr. Jones indicated agreement with Dr. Catton's belief that the code predictions contain large uncertainties in this regard.
Mr. Phillips indicated that the staff believes the overall core power response is relatively insensitive to the amplitude of the oscillations.
Dr.
Catton indicated in response that the staff needs to provide a rigorous argument to justify this
- position, given the complexities associated with the modeling of the interactive thermal hydraulic /neutronic phenomena involved.
Referring to the proposed mitigative action of lowering vessel water level for an ATWS
- event, Mr.
Phillips said NRR will investigate the issue identified by Dr. Lipinski regarding the potential for water hammer in the feedring.
Comments from the Industry A representative of General Electric Nuclear Energy, H. Pfef ferlin, made some brief comments regarding the pedigree of the GE TRACG code.
His presentation was terminated by the Committee Chairman, given both a lack of time and the fact that there would likely be another Subcommittee meeting-on this matter in the near future.
j Conclusions The Committee agreed that another subcommittee meeting should be held on this matter at such time that the staff has concluded its review of the issues pertaining to ATWS with instabilities and.has issued its SERs for both the ATWS issue and the LTS program.
In response to a request from NRR, the Committee reaffirmed its position, as stated in the Committee's June 14, 1989 letter, that the proposed LTS program represents an acceptable approach to resolution of the issue of stability assuming function of the RPS, and no further ACRS review of this matter' is necessary.
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390th ACRS Meeting Minutes 4
indicated that they will again interact with the Committee on this l
matter following completion of NRR's' actions subsequent to issuance l
of a generic letter addressing closecut of the-LTS1 program.
III. Desian Acceptance Criteria (DAC)
(Open)
Note:
Dr. El-Zeftawy was the Designated Federal Official for this portion of the meeting.
l Mr. Carroll briefed the Committee on the results of the meeting.of l
the Design Acceptance _ Criteria Subcommittee on October 7, 1992_to review the DAC process.
During that meeting the - Subcommittee discussed the staff's SECY 92-299, a
status-report on the development of DACs for the ABWR certification in the areas of instrumentation and control and of control room designs.
NRC Staff. Comments Control Room Design SECY-92-299 contains the ITAAC that GE is proposing for the ABWR control room design and the staff's Draft Final Safety Evaluation Report for human factors aspects.
The implementation of the control room design process will be the responsibility of the combined operating license (COL) applicant.
GE had submitted a neu revision of the ITAAC for the control room following the issuance of SECY-92-299.
This late information was reviewed by the staff and Committee for this meeting and appears to be acceptable to the staff at this time.
I Instrumentation and Controls (I&C)
SECY-92-299 contains the GE proposed ITAACs for the'ABWR I&C and the staff's Draft FSER.
Complete design information in the I&C area will not be submitted until af ter design certification.
GE is proposing that DAC material be included in four separate ITAACs, l
1.e.,
one system ITAAC (Multiplexing) and three generic ITAACs (Instrument Setpoint Methodology, Safety System Logic and Control, and Software Development).
General Concern Members of the Committee expressed their concern that.the Control Room Design and Instrumentation and Controls DACs are being
" overplayed" as far as representing areas of rapidly changing technology with regard to the extent that the DAC process is proposed to be used.
l Conclusions The Committee prepared a report on the matter to Chairman Selin, as noted in Section XVI.
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390th ACRS Meeting Minutes 5
IV.
Environmental Oualification of Electrical Eculpment for License Renewal (open)
' Note:
Mr.
Igne was the Designated Federal Official for 'this portion of the meeting.
1 l
Introductory Comments j
Mr.
Ward briefed the Committee on the meeting of - the ' Joint.
Subcommittees on Plant License Renewal, and Reliability and Quality that was held on September 16, 1992 to review and discuss the
_r staffs proposed Branch Technical Position (BTP)-on Environmental Qualification (EQ) of Electrical Equipment for License. Renewal (EELR).
Dr. Kress, Chairman of the Subcommittee on Reliability and Quality had no opening comments.
Mr. Lindblad noted that since the industry did not have access to the proposed BTP, it did not present a prepared response.
NRC Staff Presentations
]
Mr. Akstulewicz, NRR, in his introductory remarks provided a brief description of a series 01 paths to qualify electrical equipment, i
primarily electrical cables, for the license renewal period.
He
[
stated that he received the letter from representatives of the Nuclear Utility Group on Equipment Qualification to Mr.
D.
- Ward,
[
ACRS,
Subject:
"NRC Staff Proposed License Renewal BTP Regarding.
't Environmental Qualification of Electrical Equipment",
dated October 7, 1992, but is not prepared to discuss all of the details i
of the letter during this meeting.
In reply to a questio.n by Mr.
Carroll, Mr. Akstulewicz stated that the CRGR has completed. its review of the proposed BTP and has endorsed its publication for public comment subject to the incorporation of the CRGR's recommendation.
t Mr.
Shemanski,
requested that the ACRS endorse the issuance of this BTP for ~ public comment.
The staff, under 10 CFR, Part 54 (License Renewal Rule),
. requires the applicant to develop a program to identify all structures, systems, and components (SSCs) which may be subject to age-related degradation unique to the license renewal period.
The
{
staff proposes a separate program to manage these components to ensure continued safe operation of the plant.
The staf f is l
proposing a BTP that applies only to the EQ of electrical equipment
[
(specifically electrical cables) during the license renewal period.
l They are concerned that the qualification standards for electrical cable insulation used in nuclear. power plants-before-1984 (representing 87 of 111 licensed plants) may not ensure adequate E
performance of cables for extended plant life.
The staff did not make it clear to the Committee why the more general treatment lof SSCs defined in 10 CFR, Part 54 is not adequate for electrical cables as well.
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Industry Presentations Mr. Walters, NUMARC, and other representatives of th,e industry have expressed objection to the staff proposal for a BTP.
They believe that while older plant electrical cables were qualified to a lesser standard than has been in use since 1984, these cables have been approved by the staff for continued use in current plants and are.
part of the current licensing bases (CLB) for each of these plants.
The industry interpretation of 10 CFR, Part 54 is that the CLB is to be preserved, with exception of the SSCs subject to age-related degradation unique to the license renewal period should' be subjected to specific management programs.
The industry representatives see no need for the proposed BTP and believe it will result in unnecessary cable replacements and add significantly to plant costs for license renewal.
The Committee did not appear.
to be convinced that the proposed BTP was necessary or appropriate.
In response to a question by Mr. Ward, neither the staff nor the.
industry presented any risk perspective on the proposed EQ for EELR.
l In response to comments from Mr. Michelson, the staff noted that chemical ef fects on the aging of the cable insulation have not been considered by them in the development of this pisposed BTP.
I Mr. Bustard, NUMARC consultant, stated that the cost of complying with the proposed BTP for electrical cables outside the containment I
would cost about 40 Million dollars.
I i
Conclusions j
c i
The Committee provided a report on this matter to the Executive Director for Operations, as noted in Section XVI.
V.
Form and Content for a Desian Certification Rule (Open)
Note:
Dr. El-Zeftawy was the Designated Federal Official for this portion of the meeting.
i Mr.
- Wylie, Chairman of the Improved Light Water Reactor Subcommittee, noted that the Subcommittee met on September 23, i
1992.
The staff is proposing the use of the form and content for j
a design certification rule in accordance with 10 CFR Part 52, Sub-part B.
The proposed rule defines the following:
Scope of standard design certification.
e Content of a certified standard design.
What is approved by the certification.
Duration of the certification.
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Change process.
e Record keeping requirements Staff Presentations The staff envisions a concise and short rule that would be an Appendix to 10 CFR Part 52 that would reference a separate set of volumes, called the design control document (DCD).
The DCD will include an extraction of everything in the application that is required for certification, except proprietary information.
It will control the design after certification with copies in the central NRC files and the Public Document Room.
The DCD will be i
the basis for the design certification.
The staff's evaluation of that basis will be provided in the staff's final safety evaluation report (FSER).
Both will be challengeable during the rulemaking.
The theory behind design certification through rulemaking is that the rulemaking process provides the chance to raise issues.
If an issue is not raised during the rulemaking, then it cannot be raised following the rulemaking, except with a certain heightened standard for raising the issue.
It was not clear whether the requirements call for only one ACRS report to be provided af ter the FSER is written and before the DCD is issued, or will require a second report after the DCD is written. A clarification was requested.
D. Crutchfield, supported by an OGC representative, agreed to provide this guidance.
Conclusions The Committee provided a report on this matter to Chairman Selin, as noted in Section XVI.
VI.
Reconciliation of ACRS Comments and Recommendations (Open)
Note:
Mr.
S.
Duraiswamy was the Designated Federal Official for this portion of the meeting.
The Executive Director for Operations' (EDO's) responses to previous ACRS reports were discussed as follows:
EDO letter, dated September 3,
1992, responding to the ACRS report dated August 12, 1992, concerning ITAAC for GE ABWR.
)
Based on additional discussions during the meeting with Mr.
- Russell, the Committee found the EDO's response to the Committee's comment about ensuring "that components and
. systems in the plant can be expected to have reliabilities which are consistent with those assumed in the PRA" to be acceptable.
However, with regard to the Committee's interest in reviewing the so-called generic ITAAC, the Planning and
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. 390th ACRS Meeting Minutes 8
Procedures Subcommittee will recommend which ACRS subcommittee should handle this assignment.
A recommendation of the subcommittee to handle this matter will be made to' the Committee during the November 1992 ACRS meeting, e
EDO letter, dated October 5,
1992, responding to the ACRS report dated August 14, 1992, concerning GSI 106, Piping and Use of Highly Combustible Gases.
The.EDO letter was responsive to the Committee's comments.
The ACRS staff was asked to follow-up on the status of the staff's review of the INEL Report that was written as part of this effort e
EDO letter, dated October 1,
1992, responding to the ACRS report dated August 27, 1992, concerning fatigue evaluation procedures.
The EDO did acknowledge the Committee's comments.
EDO letter, dated September 28, 1992, responding to the ACRS report dated August 11, 1992, concerning NRC requirements that are marginal to safety.
The EDO letter was responsive to the Committee's comments, EDO letter, dated September 23, 1992, responding to the ACRS e
report dated August 18, 1992, concerning severe accidents.
The Committee found the response weak.
Dr.
Catton will prepare a draf t letter for ACRS consideration at the November 1992 ACRS meeting, EDO letter, dated September 18, 1992, responding to the ACRS e
report dated August 14, 1992, concerning GSI 151, ATWS pump trip.
The EDO letter was responsive to the Committee's comments.
e EDO letter, dated October 8,
1992, responding to the. ACRS report dated September 17, 1992, concerning the BWR and Fermi-2 plant power uprates.
The EDO letter was responsive to the Committee's. comments.
EDO letter, dated June 12, 1992, responding to the ACRS report o
dated May 13, 1992, concerning Evolutionary and Passive LWRs, the staff's requirements on the design and use of the Post Accident Sampling System (PASS), the Committee found the EDO I
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390th ACRS Meeting Minates 9
letter was responsive to the Committee's comments.
This was a carryover item from the September ACRS meeting.
VII. Maintenance of Nuclear Power Plants (Open)
Note:
Mr. Alderman was the Designated Federal Official for this portion of the meeting.
Introductory Comments
?
Mr. Carroll, Chairman of the Maintenance Practices and Procedures Subcommittee, noted that the Subcommittee met on October 6,
- 1992, and was told that the staff and NUMARC were in agreement on a regulatory guide that-endorses the program being proposed by NUMARC.
He noted that the Committee was being asked to comment on whether the staf f's proposed regulatory guide was ready for public comment.
NUMARC Presentation Mr.
W. Hall, NUMARC, discussed their activities with regard to the implementation guidance for the maintenance rule. He presented a.
brief background of their activities and their approach.to implementi-the rule.
He said that they had broken the rule into four areas as follows-Determine the SSCs that were in the scope of the rule.
o Evaluate all the SSCs within the scope and determir.e which paragraphs cf the rule would be applicable.
Perform a performance assessment of the activities of the systems.
Determine the impact of taking a system out of service for maintenance and monitoring activities, with regard to the overall safety of the plant.
I Mr. Hall discussed the verification and validation (V&V) program.
He said that nine plants were used in this study, i.e.,
three Westinghouse plants, two Combustion plants, two Babcock and Wilcox plants, and two General Electric plants.
The first effort, under the V&V program, was to have the participants identify all the j
structures, systems, and components that they find at their plants to be within the scope of the rule.
The lists were compared for similarities and differences, with an effort is being ' made to-derive a common list.
A major effort is to identify the risk significant criteria for the selection of risk significant SSCs at the plants.
Mr.
Hall discussed some of the lessons learned from the V&V program. The first was to exclude SSCs used in emergency operating procedures from the scope of the rule.
Another. was that organizations within each utility found that the different
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390th ACR_S Meeting Minutes 10 organizations had different lists of systems and described systems dif ferently depending upon their~ use of that particular system.
It was. discovered that ' nomenclature differences exist, such that structure and system nomenclature that is used to' define same or similar plant functions within and among the-NSSS types' is considerably different.
One of the issues, establishing goals and monitoring at the component level, was not a practical thing for a utility, by virtue of the number of components that could be involved in a particular structure or system. Appropriate use of PRA results was one of the lessons learned.
The concern is that use of " generic performance results" or "best performance ever i
achieved" as a basis could potentially result in a-lot of unnecessary costs to a utility.
All the participants agreed that industry wide performance shouldn't be used as a basis for establishing a goal at a particular utility.
Mr. Hall discussed the major project milestones.
Implementation of the rule will go into effect in July 1996.
NRC Staff Presentation Mr. Rothberg, Office of Research, stressed that their activities concentrated on monitoring the effectiveness of maintenance, rather than specifying anything about maintenance activities.
He'said that the NRC intends to issue the regulatory guidance by June 30, 1993 and should endorse the industry guidance without exceptions.
If-there are any exceptions, there may be a delay in issuance of the regulatory guidance.
The staff's view of the major elements of the industry guidance is that the licensees identify the SSCs within the scope of the. rule.
The program must demonstrate that SSCs are maintained so that they will perform their intended function.
In response to a request by Mr. Carroll, Mr. Rothberg described options A(1) and A(2) of the maintenance rule. He said that A(1) refers to setting goals and monitoring essentially in a manner to provide reasonable assurance that SSCs are capable of fulfilling their intended functions.
He noted that A(2) of the rule says that you need not perform monitoring and goal setting if you have a program that demonstrates that the performance of structures, systems, and components, is being effectively controlled through preventive maintenance.
The industry approach is to use exirting maintenance programs and include most of the SSCs under A(2).
Certain SSCs will have goal setting and will be monitored.
Mr.Rothberg said that A(3) of the rule requires that periodic assessments be made of maintenance
- efforts, to ensure that maintenance is effective.
The staff intends to amend 10 CFR 50.65 to change the assessment period to every refueling outage.
l
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r 390th.ACRS Meeting Minutes 11 Mr. Davis expressed his concern about excessive ~ testing ~during shutdown and the subsequent increase in risk.
Mr. Rothberg.said i
that this is a problem and the current plan is to use PRA methods to resolve it.
In response to a question from Mr. Carroll concerning who does the i
periodic assessment, Mr. Rothberg said that they envisioned that several engineers would gather the data throughout the appraisal period.
The periodic appraisal would involve several layers-of management.
The implementation guidance for the maintenance rule is intended to complement the provisions of other regulations without providing i
redundant or conflicting guidance.. Mr. Carroll suggested that' guidance should be provided to utilities that would allow the utilities to prepare for license renewal during the time they are setting up for the maintenance rule.
Conclusions The Committee provided a report on this matter to the Executive Director for Operations, as noted in Section XVI.
.i VIII.
Renewal of Nuclear Power Plant Operator Licensos arid Recualification (Open)
Note:
Mr. Alderman was the Designated Federal Official for this portion of the meeting.
ID.troductioD Mr. Carroll, Chairman of the Human Factors Subcommittee, discussed the proposed amendments to 10 CFR 55 on renewal of nuclear power plant operator licenses and requalification.
He noted that the amendments would revise the current requalification regulations for licensed operators by eliminating the requirement that they pass a requalification examination administered by the NRC at some point during the six year term of their license.
The staff would rely on l
the written examinations and annual operating test that licensees are giving to their operators.
URC Staff Presentations on the Rule Chance Mr. Bruce Boger, NRR, Mr. Paul Lohaus, RES, and Mr. Robert Gallo, NRR, presented the staff's position and experience supporting the proposed change.
They noted that essentially, the rule change would delete the requirement for the NRC to examine each operator for license renewal, would add a requirement for a utility to submit annual operating tests and biennial written examinations to the NRC, and expand the scope of the rule to include facility licensees.
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390th ACRS Meeting Minutes 12 Dr. Lewis asked why the tests were given on this_ frequency.
This implies that operational expertise decays.on the scale of a-year, though it's practiced every day, while book learning only decays on j
the scale.of two years, though such is not used every day.
The.
~
Federal Aviation Administration (FAA) only' requires airline pilots to pass one written examination for. life.
Mr. Gallo responded that'2 years represents _a regulatory limit.
Many plants test more often than that.
Mr. Boger indicated that the reason for these frequencies goes back to the initial rule l
passed in 1986.
Mr. Lohaus said that the, rule change will still mean that the spirit of the existing rule will be met.
Mr. Gallo described a new inspection program beginning this winter.
Oneite NRC activities will emphasize review of simulator testing.
A majority of the failures are found in this activity.
Also crew evaluations, discussed below under the pilot program, are done with simulators.
Offsite NRC activities will emphasize review of the licensee's written examinations.
4 Dr.
Shewmon inquired about the staff's consideration of INPO programs.
Mr. Gallo responded that INPO programs of accreditation take into account all asptcts of operator testing, whereas the NRC l
program will focus on training.
Mr. Carroll felt that INPO does a rigorous job, having withdrawn accreditation for 2 utilities.
The Committee to Review of Generic Requirements (CRGR) has recommended that the staff conduct examinations at each facility, every fourth year for weaker programs and every sixth year for-stronger ones.
Mr. Carroll asked Mr. Gallo when was the last time he personally gave an exam.
Mr. Gallo replied that he had gotten out to observe several tests.
Several years ago, the staff was criticized for inconsistency among regional offices on this matter of qualifying operators.
The staff has improved its efforts through such means as conference calls and meetings between headquarters and regional staffs.
Mr. Gallo pointed out that with the rule change, NRC would retain options for dealing with weak programs, for example, by requiring additional testing or conducting a "for cause" inspection.
In* summary, Mr.
Gallo noted that the NRC would gain several advantages with the rule change:
conservation of resources, ability to gauge the big picture, and becoming more proactive than reactive.
NRC Staff Presentation on the Pilot Reaualification Program The pilot program now in place involves evaluating whole crews of i
operators with plant simulator machines; to date all crews that
-m 390th ACRS Meeting Minutes 13
-have been evaluated have passed.
The program also has identified.
weaknesses of ' individual operators, which the affected facility
)
licensees have corrected.
This pilot program'has been used at.the Surry and Hatch facilities.
Mr. Carroll pointed out that nuclear industry operators.have been rigorously qualified, yet suf fer about a 10 percent. failure rate on -
requalification. FAA experience shows a much smaller failure rate.
Mr.'Gallo observed that the nuclear industry failure rate _for 1992 is down to 5 percent.
Mr. Boger did not know the failure rate for airline pilots, but noted that they can be trained and tested -
simultaneously whereas nuclear industry operators don't have'the opportunity of being trained and tested simultaneously.
Mr. Gallo noted that the individual nuclear power plant operator i
failure rate is about 5 percent, down from the 10-11 percent prior to this year.
Conclusions The Committee provided a report on this matter to the Executive Director for Operations, as noted in Section XVI.
7 IX.
Use of PRA in the Reculatory Process (Open)
Note:
Mr. Houston was the Designated Federal Official for this portion of the meeting.
Dr.
- Lewis, Chairman of the Probabilistic Risk Assessment Subcommittee, introduced this topic noting that the Committee had written a report in July 1991 that highlighted the problems.with regard to the use of PRA within the NRC staff.
Pf.A Workina Group Status Report Mr. M. Cunningham (RES), Chairman of the PRA Working Group, briefed the Committee on the status of the various PRA tasks.
These tasks are as follows:
Task 1
- Identify how the Staff is using PRA Task 2
- Identify limitations that exist in present staff uses of PRA Task 3
- For each category of PRA-use, define appropriate PRA methods and scope Task 4
- Identify skills and techniques needed to overcome identified limitations Task 5
- Develop a Final Report i
Mr. Cunningham, presented the results of surveys for Tasks 1 and 2.
l He cited numerous areas where PRAs were being applied in ' the regulatory activities.
He indicated that the majority of PRA applications are Level 1 PRAs with the end product expressed as j
9
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9 390th ACRS Meeting Minutes 14 core damage' frequency (CDF) or charges'in CDF.
He noted_that the-staff lacked. experience and familiarity with PRA techniques and i
there was even less experience and training in the field of
+
statistics'and decision making.
In regard to Task 3,
he discussed the development of general.
I guidance for PRA use and guidance on key-technical issues and methods by a selected group of experts.
He indicated that.a draft
-i guidance report would be ready by the end of 1992.
l In closing, he discussed the role and schedule for (1)_the External Peer Review Group and (2) the ACRS.
Three topics were mentioned-for meetings with the Committee: (1) PRA Guidance for the staff, (2) examples of Risk Evaluation and (3) strengths and weaknesses of reliability calculations.
He indicated that a final report to resolve PRA issues was tentatively scheduled for April 1993.
NRR Applications of PRA-Mr. W. Pussell, Associate Director of NRR, discussed three areas of.
i PRA applications as follows:
(1)
Living PRAs for future plants, (2)
Reliability Assurance Program for the design and operational phases for future plants, and (3)
Applications in monitoring the maintenance rule.
He indicated that a regulatory guide to define the scope and content of PRA submittals is being developed by the RES staff.
The PRA studies will be applied to resolve the severe accident issues i
for each future plant design.
In regard to the maintenance rule, he indicated that PRA would be used to: (1) balance unavailability due to preventive maintenance (PM) against reliability gained from performing PM, and (2) assess total out of service time for key
- systems, structures and l
components against overall plant safety.
Conclusions This was a briefing for information only.
No ACRS action was taken at this time.
Topics were identified for possible future meetings as appropriate.
X.
Environmental Oualification of Safety-Grade Dicital Computer Protection and Control Systems (Open)
Note:
Mr. Duraiswamy was the Designated Federal Official for this portion of the meeting.
l
390th ACRS Meeting Minutes 15 Introductory Comments Dr.
H.
Lewis, Chairman of the Computers in Nuclear Power Plant i
operations Subcommittee, introduced the topic, noting that the Subcommittee has been interested in issues involving the application of software-driven digital systems in nuclear plant instrumentation and control (I&C) systems.
In particular, members of the Subcommittee had questions about the research programs.
NRC Staff Presentation Mr. Scott Newberry, Chief of the Instrumentation and Control System Branch, discussed the research program being conducted by the'NRC in response to the needs of NRR, the end user.
A major-objective of the program is to develop additional standards and guides for environmental qualification of software-driven digital equipment, and their technical bases, where the need is determined to exist.
Currently NRR is conducting meetings with Research (RES) to better define NRR's user needs.
The RES program was noted to go well beyond just electromagnetic interference / radio frequency interference (EMI/RFI), which was the focus of much of.the earlier l
discussion during the subcommittee's June 1992 meeting with RES.
Mr.
Newberry stated that there were about ten environmental
~;
stressors of concern, some of which would require more research than others.
For example, although much is known about the reliability of digital systems at high temperatures, not'much is known about the probabilities of the different failure modes when failure due to high temperature begins to occur.
Another stressor.
that needs further research is smoke.
Dr. Catton emphasized that current research in this area is beginning to show the effect of-smoke as being a highly significant environmental stressor, and that this should be factored into the NRC's research program.
Mr.
Vagins stated that smoke would be looked-at as part of the RES program.
Mr. Michelson questioned the manner in which the results of the RES program would be used.
Mr.
Newberry stated that although regulatory guides were a requested product of the RES program, the information and results being generated prior to that product would be a valuable benefit to the staff's ongoing reviews (e.g.
the advanced designs).
Mr. Michelson questioned the ease of changing l
the staff's review guidelines as the RES program results change over time.
Mr.
Newberry stat d that ' the guidelines would be
]
incorporated into tier two of the Part 52 certification process and i
that there were vehicles for making changes to that level.
J Dr. Leviis asked if the list of stressors had been prioritized.
Mr.
j Vagins st ated that they were not currently prioritized but that it was a goed comment and should be done.
He stated that they would do so.
390th ACRS Meeting Minutes 16 Mr. Vagins stated that the EMI/RFI program to date has involved literature survey and evaluation and is about 90 percent complete.
He also stated that the research funding for all areas other than EMI/RFI has been doubled, beg 2nning in 1993.
Mr. Michelson asked if the multiple system response program (MSRP)
(Unresolved Safety Issue A-17 resolution) was related to these EQ issues.
Mr.
Newberry stated that the MSRP was in progress, although he did not have an exact status.
Dr. Lewis asked if NRC had access to military research programs in areas related to current NRC sponsored research.
Mr. Vagins stated that NRC has had no direct access to military research.
Mr.
Michelson suggested trying to go through the Department of Energy or National Institute of Science and Technology (NIST) to gain access to Department of Defense research.
Conclusions The Committee determined that a
briefing on the status of Unresolved Safety Issue A-17 and the Multiple System Response Program and its findings with regard to this matter should be scheduled for a future full Committee meeting session.
XI.
Inspections, Tests, Analyses, and Acceptance Criteria _(ITAAC) for GE ABWR Desion (Open)
Due to lack of new information, discussion of this matter was postponed to a later meeting.
The preparation of a report on this matter will be considered further at the November 1992 meeting.
XII.
Yankee Rowe Nuclear Power Plant (Open)
Note:
Mr. Houston was the Designated Nederal Official for this portion of the meeting.
Introductory Comments Dr. Shewmon, Chairman of the Materials and Metallurgy Subcommittee, introduced the topic noting that embrittlement questions about the Yankee Rowe pressure vessel caught the NRC staff and the utility unprepared.
The staff and utility representatives briefing was to tell the Committee of the lessons learned from this activity.
URC Staff Presentation Mr.
P.
Milano,NRR Project Manager, discussed the chronology of events that ultimately led to the shutdown and proposed decommissioning of Yankee Rowe.
The basic problems at Yankee Rowe were discussed and mainly focused on (1) lack of surveillance test specimens of appropriate materials, (2) unknown composition of weld
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)
material, and (3) absence of inservice inspection in key areas.
Based on assumptions made or conditions imposed in these areas of l
uncertainty, the licensee calculated that the lower limit for low l
Charpy upper-shelf energy could not be met.
From the activities at Yankee Rowe, the~ staff has focused on the i
following task action plans:
Revisions to rules and. guidance on pressurized thermal shock o
(PTS) analysis, Rule and regulatory guide on annealing, e
Standard review plans, e
Interactions with government and industry, i
Review of the overall management process, e
During the discussion of the guidance given or proposed for Regulatory Guide 1.154, Dr. Lewis questioned the position taken by the staff that RG 1.154 gave the "only" acceptable position.
It was emphasized that RGs were not regulations and should.only be taken as one acceptable approach.
In response to questions concerning the lead time needed. for requests to perform vessel annealing, the staff indicated that such' requests should be submitted at least 5 years before expected annealing.
Presentation by Representatives of Yankee Atomic Enero C yniam (YAEC) l Mr. J.
Hazeltine, YAEC, discussed the licensee's assessment of tne process and expressed hope that similar situatf.ons involving difficult technical assessment could be avoided in the future.
He indicated that an opportunity was lost in this case to demonstrate that the NRC, the licensee and the scientific community could move toward a consensus on a real, critical and complex problem in a professional, technical way.
He discussed areas of frustration, e.g.,
no one senior NRC staffer in charge, little technical integration, and wasted resources.
He also discussed some of the conservatism that was forced onto the licensee via RG 1.154 (e.g.,
all flaws are concentrated in the surface).
He indicated that NRC should conduct an analysis of the affect of the many conservatism and develop a realistic best i
estimate approach.
i Mr. Hazeltine recommended that an international group of scientists and engineers be convened to establish an international consensus
'l
k o
-i 390th ACRS Meeting Minutes 18
.i and technical basis for the fundamental issues associated with the Yankee Rowe vessel matter.
In response to the licensee, Mr.
S. Varga, NRR, said that the NRC staff was sensitive to the YAEC frustrations but, he felt staff management oversight and the review process were appropriately
~
performed.
In fact, Dr. Murley, NRR, recently presented awards to many of the staff for their outstanding effort in regard to Yankee
-l Rowe.
Conelt ions 7
This was a briefing for information only.
No ACRS actions was taken at this time.
XIII.
Miscellaneous (Open/ Closed)
Note:
Mr. Fraley was the Designated Federal Official for this portion of the meeting.
Candidates for the NRC " Thermal Hydraulic" review aroup (Closed) l The Committee discussed a request from Mr. Eric Beckjord that the Committee recommend a nominee for membership on the thermal i
hydraulic review group to be established.
The Committee recommended several candidates for consideration in a memorandum to James Taylor, as noted in Section XVI.
Availability and Adeauacy of Desian Bases Information (Open)
The Committee directed Mr. Fraley to send a Memorandum to Thomas Murley, as noted in Section XVI.
Visit to Eastern European Nuclear Power Plants by the ACRS Chairman (Closed)
This portion of the meeting is reported in a special closed meeting supplement, which is attached.
XIV. ACRS Subcommittee Activities (Open/ Closed) l Note:
Mr. Fraley was the Designated Federal Official for this portion of the meeting.
F Report of ACRS Plannina and Procedures Subcommittee Meetino on October 7.
1992 (Open)
The minutes of the October 7,
1992
. Planning and Procedures Subcommittee meeting were discussed.
There was general agreement with the minutes of that meeting with the following comments:
O.
1 390th ACRS Meeting Minutes 19 Appointment of ACRS Members (Closed)
This portion of the meeting is reported.in.a special closed meeting supplement, which is attached.
Election of ACRS Officer (Closed)
The Committee selected Dr.
Wilkins to serve as the new
" Member-at-Large" for the Committee for the remainder of the 1992 calendar year.
Editina ACRS Reports (Open)
The Committee agreed with the Subcommittee's recommendation to use standardized NRC format / style as modified per ACRS practice.
Mr. Fraley was asked to write an office procedure regarding editing to ensure that the editing changes do not change the Committee's intended meaning at the time the Committee approved the report.
The ACRS office should send the cognizant Subcommittee Chairman and the ACRS Chairman copies of both the Committee passed final version and the version sent to the Commission of each report, i
" Stock" Ownership by ACRS Members (Open) l The Committee agreed that a letter should be sent to the OGC requesting that members be subject to agency prohibitions regarding stock ownership in companies on the forbidden list unless a specific exemption is granted by the Commission.
However, it was agreed to request an allowance that members be allowed a tax deferral if they should have to sell stocks to become a member.
Mr. Fraley should check with the OGC to determine if this allowance already exists before making such a request.
ACRS Meetina Calendar for 1992 (Open)
The Committee agreed to the following schedule for holding ACRS meetings for calendar year 1993:
393rd Meeting - January 7-9, 1993 394th Meeting - February 11-13, 1993 395th Meeting - March 11-13, 1993 396th Meeting - April 15-17, 1993 1
397th Meeting - May 13-15, 1993 398th Meeting - June 10-12, 1993 399th Meeting - July 8-10, 1993 400th Meeting - August 5-7, 1993 l
401st Meeting - September 9-11, 1993 402nd Meeting - October 7-9, 1993 403rd Meeting - November 4-6, 1993 404th Meeting - December 9-11, 1993
)
j l
390th ACRS Meeting Minutes 20 4
Report on the International Meetino on Computers Held on September 22, 1992 Due to the shortage of time at this meeting, this report has been rescheduled for the November 1992 ACRS meeting.
XV.
Preparation of other ACRS Reports and Memoranda (Open)
Note:
Mr. Fraley was the Designated Federal Official for this-portion of the meeting.
In addition to those matters discussed with representatives of the staff and industry during this meeting, the members-discussed and completed the following memorandum:
Draft Generic Letter on the Availability and Adecuacy of Desian Bases Information The Committee directed Raymond F. Fraley to send a memorandum to the Director of the Office of Nuclear Reactor Regulation, as noted in Section XVI.
XVI.
Executive Session (Open)
Note:
Mr. Fraley was the Designated Federal Official for this portion of the meeting.
During its 390th
- meeting, October 8-10,
- 1992, the Advisory Committee on Reactor Safeguards discussed several matters and completed the Reports and Memoranda as noted.
REPORTS Proposed Guidance for Implementation of the Maintenance Rule, e
10 CFR 50.65 (Report to Mr. James M.
- Taylor, Executive Director for Operations, dated October 15, 1992)
ACRS Recommendations Concernino NRC Thermal Hydraulic Review e
Group (Report to Mr. James M. Taylor, Executive Director for Operations, dated October 14, 1992) with limited distribution, e
Second Interim Report on the Use of the Desian Acceptance Criteria Process in the Certification of the General Electric Nuclear Enerav Advanced Boilina Water Reactor Desian (Report to Chairman Selin, dated October 16, 1992) e SECY-92-287,
" Form and Content for a Desian Certification Rule" (Report to Chairman Selin, dated October 16, 1992) t
1 4
i
'l 390th ACRS Meeting Minutes 21 Proposed Amendments to 10 CFR Part 55 on Renewal of Nuclear Power Plant Operator Licenses and Recualification (Report to i
Mr. James M. Taylor, Executive Director for Operations, dated October 19, 1992) e Proposed Branch Technical Position on Environmental Oualification of Electrical Eauipment for License Renewal (Report to Mr.
James M.
- Taylor, Executive Director for Operations, dated October 22, 1992)
MEMORANDA t
e Draft Generic Letter on the Availability and Adecuacy of Desian Bases Information (Memorandum for Thomas E.
- Murley, Director of Of fice of Nuclear Reactor Regulation, from Raymond F.
Fraley, Executive Director of the ACRS, dated October 14, 1992)
Memorandum to Mr. Trip B. Rothschild, Deputy Assistant General e
Counsel / Legislative Counsel of the Office of the General Counsel, from David A. Ward, ACRS Chairman, dated October 16, 1992, concerning a proposal on whether the Committee should be subject to the Commission's stock ownership restrictions.
XVII.
Future ACRS Activities (Open)
A.
Future Aaenda The Committee agreed to a tentative schedule for the 391st, November 5-7, t992 ACRS meeting as contained in Appendix II.
B.
Future Subcommittee Activities A list of future ACRS Subcommittee meetings was distributed to the Committee members (Appendix III).
C.
Second Ouadricartite Meetina of Advisory Committees Dr. Wilkins noted that the Committee received a letter from Mr. Francis Cogne, President of the French Groupe Permanent Reacteur, dated September 22, 1992.
Mr.
j Cogne's letter responded to the June 29, 1992 Committee letter that suggested another multilateral meeting of advisory bodies be held with the same nations participating as did at the October 19-23, 1986 Wingspread meeting.
Mr. Cogne said the RSK and GPR would
{
organize such a meeting in Europe, probably' France, i
during the spring to fall period in 1993, and that j
further information concerning this meeting would be sent to the ACRS during the next couple of months.
I 390th ACRS. Meeting Minutes 22-Dr. Catton suggested that the meeting be held at the time
'j immediately following the Structural Mechanics in Reactor.-
Technology (Smirt) conference and its. post. seminar:
meeting.
They are scheduled for August 16-20_-and 23-24, 1993, respectively, in Stuttgart, Germany.
XVIII.
Summary / List of Follow-up Matters I
e It was noted that Dr. Shewmon will complete Mr. Wards term as Chairman when he leaves the Committee on November 4, 1992, and Mr. Carroll will assume the duties of the Vice-Chairman.
J.
E. Wilkins was elected to the position of Member-at Large for the Planning and Procedures Subcommittee for the remainder of the year.
With regard to qualification of electrical equipment for i
license renewal, Mr. Michelson would like to know if-the fire retardant coating on electrical cables is looked at to ensure that chemical reaction of the coating would not cause degradation.
(Mr. Igne has the follow-up on this matter.)
e An ACRS office procedure should be prepared for editing of ACRS reports.
The guide should ensure that a copy of the final marked draft of the ACRS report, as it was approved by the Committee, is sent to the cognizant Subcommittee chairman and to the ACRS Chairman following editing.
(Mr. Fraley has the follow-up on this matter.)
Mr.
Crutchfield,
- NRR, agreed to provide an official determination as to whether the Rules and Statutes will require one or two ACRS reports for the ABWR.
The staff is presently asking for one ACRS report after the FSER is written, but before design certification and the final design
- approval, i.e.,
before hearings and final Rule.
(Dr. El-Zeftawy has the follow-up on this matter.)
NUMARC will provide information to Dr. Kress on the selection e
of criteria for determination of risk significant systems, structures and components (SSCs) as required by the Maintenance Rule (Mr. Alderman has the followup on this matter)
The Planning and Procedures Subcommittee, at its November 1992 e
meeting, should prepare a recommendation to the Committee suggesting which subcommittee will handle the ITAACs for the generic subjects.
(Mr.
Fraley has the follow-up on this matter.)
The ACRS staff should determine the status of the staff's-review of the INEL Report that was written as part of the GI-106 effort on hydrogen combustion and detonation.
This
390th ACRS Meeting Minutes 23 information should be provided to Mr.
Carroll before the i
December 1992 ACRS meeting.
(Mr. Houston has the follow-up on this matter.)
Dr. Catton noted that the EDO's response to the Committee's comments on severe accidents is weak in areas related to hydrogen generation / control and steam explosions.
He will prepare a response for Committee consideration at the November ACRS meeting on the matters of igniters acting as detonators and on steam explosions.
(Mr. Houston has.the follow-up on this matter.)
i e
Dr. Catton wishes to receive a copy of a German Report on a steam explosion test at a KfK facility when outside water was
~,
dumped on molten material, that surprisingly destroyed the test facility.
Dr. Ullrich Muller (Phone 07247823450), KfK, has indicated that a copy of this report will be sent to the ACRS when available.
(Mr. Quittschreiber has the follow-up on this matter.)
Note:
Dr.
H.
Alsmeyer, KfK, reported on this matter at the October 1992 WRSR Research meeting.
Dr. Muller said they would send the ACRS a copy of a report on this matter at a letter date.
o Dr. Catton wishes to receive a copy of a German report that discusses the phenomena associated with the hydrogen explosion tests that were shown on the video that was provided to the Committee from the RSK.
(Mr. Quittschreiber has the follow-up on this matter.)
Note:
Dr. Ullrich Muller, KfK, will provide the ACRS a copy a report on this matter if and when one becomes available, Dr. Kress wishes to know what the staff is planning to do with e
regard to assessing models (hopefully not every model) of the severe accident codes.
The EDO letter to the ACRS dated i
September 23, 1992 states "The NRC has put a contract in place l
to provide an independent assessment and evaluation of models that are proposed for implementation in severe accident codes."
(Mr. Houston has the follow-up on this matter )
e A progress report on the Multiple Systems Response Program (MSRP) should be scheduled for a future ACRS meeting. (Dr.
Savio has the follow-up on this matter.)
The Committee agreed that the ACRS office management should e
evaluate the options available for ACRS video-conferencing capability at the new White Flint office building.
(Mr.
Fraley has the follow-up on this matter.)
Members of the Committee had neither comment nor plans to take e
i further action regarding the September 22, 1992 letter to John Hoyle, Office of the Secretary, from Herbert Bardach.
The
t 390th ACRS Meeting Minutes-24 letter provided comments from Mr. Bardach that certain widely used computer codes used in designing radiation shielding were.
disposed to yield serious errors of underestimation'of-dose rates.
Dr. Wilkins will look at this matter further as an item of personal ~ interest.
(Mr. Igne.has the follow-up on.
l this matter.)
i The meeting was adjourned at 2:30 p.m., Saturday, October 10, 1992.
4 2
a 4
I a
i a
f I
1
APPENDICES MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10 1.
Attendees II.
Future Agenda III.
Future Subcommittee Activities IV.
List of Documents Provided to the Committee
.l
[
APPENDIX I MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10 l
Thursday October 8. 1992 Public Attendees NRC Attendees P. W. Marriott, GE Nuclear Energy Sam Lee, NRR Y. S. Kim, Halliburton NUS Jerry Edson, NRR J. K. Garrett, GE Nuclear Energy Jit Vora, RES T. J. Rausch, BWRUF/ Commonwealth Edison Raj Anand, NRR M. A. Ross, GE-P. T. Kuo, NRR V. San Angelo, SERCH Licensing /Bechtel Power G. Hubbard, NRR F. P. Amend, MKW Power Systems Ann Dummer, NRR A. P. Heymer, NUMARC David Tang, NRR C. K. Lewe, Halliburton NUS Jim O'Brien, NRR L. J. Toth, Gasser Assoc.
Debbie Jackson, NRR Karen Unnerstall, Newman & Holtzinger Frank Akstulewicz, NRR Thomas Penland, Winston & Strawn Jocelyn Mitchell, ED0 Brian Steinman, Energy Operations, Inc.
D. Crutchfield, NRR Ellen Ginsberg, NUMARC Ron Parkhill, NRR Bill Horin, Winston & Strawn Tony DiPalo, RES Larry D. Bustard, Sandia National Labs George Sege, RES Phil Holzman, Strategic Tech. & Resources Richard P. Correia, NRR-Tricia Heroux, EPRI W. Beckner, NRR Donna Harrison, DOE - NE - 42 W. T. Russell, NRR Kay Ng, NUMARC A. Thadani, NRR Sal Carfagno, Consultant C. Rossi, NRR G. Zech, NRR R. Zimmerman, NRR
- 0. Rothberg, RES Tony Ulses, NRR Jerry Wilson, NRR R. Jones, NRR L. Phillips, NRR H. Richings, NRR H. Pastis, NRR Jim Stewart, NRR Mike Waterman, NRR M. Chiramal, NRR C. Goodman, NRR R. Eckenrode, NRR J. Wermiel, NRR G. Galletti, NRR Scott Newberry, NRR Cecil Thomas, NRR Geary S. Mizuno. NRC J. J. Burns, NRC Joe Joyce, NRR M. Taylor, OED0 M. Mayfield, OEDO P. Shemanski, NRR
. Minutes of 390th ACRS Meeting, Appendix 1 Attendtes.
Friday October 9. 1992 Public Attendees NRC Attendees M. G. Phillips, Newman & Holtzinger Frank Cherny, RES Warren Hall, NRMARC Pat O'Reilly, AE0D a
Y. S. Kim, Halliburton NUS Dave Trimble, OCM Doug Walters, NUMARC Charles Rossi, NRR Dan Rains, NUMARC John Burns, NRC Patrick Harris, SERCH Licensing /Bechtel Nancy Salgado, NRC
-Gilbert Zylan, Science & Engineering Assoc., Inc.
Cheryl Beardslee, NRC tricia Heroux, EPQI Richard Correia, NRC L. J. Toth, Gasser Assoc.
Franklin Coffman, NRC Beu A. Franklin, Mc Cerere. Hill Charles Petrone, NRR R. N. Whitesel, NUMARC Tom Foley, NRR R. C. Evans, NUMARC Gary Zech, NRR Roger Huston, TVA F. Akstulewicz, NRR Elizabeth Len, Winston & Straun E. Doolittle, OCM Tony Pietrangelo, NUMARC H. Pastis, NRR R. L. Seale, WBAZ G. Mizuno, 0GC John Hashire, Yankee Atomic Darrel Nash, OPP James P. Riocio, Public Citizen Mat Taylor, OEDO Ron Gumble, Sartrex Robert Gallo, NRR Kurt Cezcuz, NUMARC David J. Lange, NRR L. Zerk, STS John Munro, NRR Richard D. Gondello, Baltimore Gas & Electric Brad Hardin, RES Doug Walters, NUMARC Dan Dorman, NRR l
Robert J. Smith, Duke Power Co.
Chris Orsini, NRR Peter M. Yandow, Carolina Power & Light W. R. Butler, NRR David D. Reiff, Keuric Co, Inc., S.S., MD C. Z. Serpan, RES Diane Tamai, Baltimore Gas & Electric Luz R. Naval, NRC Russ Bell, NUMARC K. L. Evans, GSA
+ - - -.
a APPENDIX II MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10, 1992 FUTURE AGENDA The Committee agreed to ' discus's the 'following during its' 391st meeting, November 5-7, 1992:
A.
Insichts from Common Mode Failure Events - Briefing by and discussion with representatives of the NRC staff regarding an analysis of selected common mode failure' events.
B.
Analysis of the Human Factors Aspects of Operatina Events -
Briefing by and discussion with representatives of the NRC staff regarding on-site evaluation team work related to analyzing human factors aspects of selected operating events.
Representatives of the nuclear industry will participate, as appropriate.
C.
Requlatory' Analysis Guidelines - Review and report on proposed Revision 2 to NUREG/BR-0058, Regulatory Analysis Guidelines for U.S.
NRC.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
D.
Meetina with the Director, NRC Office of Nuclear Material Safety and 'Safecuards (NMSS) - Meeting with Director, NMSS, to discuss items of mutual interest, including matters such as the status of NRC and industry proposals for revised security requirements for nuclear power plants, status of the.high-3evel waste storage and disposal programs, and regulatory changes as a result of the incident which occurred at'the GE Wilmington Facility.
E.
Risk-Based Reaulation/Fitzpatrick Nuclear Plant IPE - Briefing by and discussion with representatives of the New York Power Authority (NYPA) regarding NYPA's views on risk-based regulation and the results of the Fitzpatrick Individual Plant Examination (IPE) and its relationship to the NRC Diagnostic Evaluation Team review of this plant.
Representatives of the NRC staff will participate, as appropriate.
F.
Reactor Operating Experience - Briefing by and discussion with representatives of the NRC staff regarding events at operating nuclear power ' plants, including. loss of' high-head safety injection pumps at the Shearon Harris nuclear plant, and an Augmented Inspection Team (AIT) evaluation of an incident at the LaSalle nuclear station.
Report by the cognizant Subcommittee Chairman regarding a recent incident at the Fukushima nuclear plant in Japan during which reactor condensate and feedwater pumps were inadvertently turned off.
Representatives of the nuclear industry (licensees) will participate, as appropriate.
G.
Risk-Based Reaulation - Review and report on the NRC staff's proposal on risk-based regulation. Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
26 II.
Prioritization of Generic Safety Issues - Review and comment on guidelines proposed by the -NRC staf f for prioritization of generic safety issues.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
1.
Environmental Oualification of. Safety-Grade Digital Computer
~
Protection and Control Systems - Discuss proposed ACRS report on the nature of the NRC research program to qualify safety-grade digital computer protection and control systems proposed-for use in nuclear power plants.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
J.
Reconciliation of ACRS Comments and Recommendations - Discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to ACRS comments and recommendations.
Appendix II i
't
'f P
.. -. - +, -,. - - - - -,
,.--,,,..---c-.-.-..
,.-,,n..
,c,
~
i I
APPENDIX 11I 1
MINUTES Or THE 390TH ACRS MEETING _
OCTOBER 8-10, 1992 1
FUTURE SUBCOMMITTEE ACTIVITIES l
Safety Philosophy, Technoloav and Criteria, October 28, 1992, 7920 Norfolk Avenue, Bethesda, MD (Houston), 8:30 a.m.,
P-110.
The Subcommittee will review Revision 2 to NUREG/BR-0058, Regulatory Analysis Guidelines, and guidelines for prioritization of Generic Safety Issues.
Attendance by the following is anticipated, and reservations h' ave been made at the hotels as indicated for the night of October 27:
Kress HYATT Michelson HYATT Ward NONE Wylie HYATT
. Lewis HYATT Kerr NONE Plant Operations, November 4,
1992, Bethesda, MD - Postponed to December 9, 1992.
Plannina and Procedures, November 4,
1992, 7920' Norfolk Avenue, Bethesda, MD (Fraley), 9:00 a.m.
12 Noon, Room P-422.
The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed.
Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of November 3:
Shewmon NONE Carroll HOLIDAY INN Wilkins HOLIDAY INN 391st ACRS Meetin_g, November 5-7,
- 1992, 7920 Norfolk Avenue, Bethesda, MD, Room P-110.
Items are tentatively scheduled.
A.
Insichts from Common Mode Failure Events - Briefing by and discussion with representatives of the NRC staff regarding an analysis of selected common mode failure events.
B.
Analysis of the Human Factors Aspects of Operatina Events -
Briefing by and discussion with representatives of the NRC staff regarding-onsite evaluation team work related to
{
analyzing human factors aspects of selected operating events.
Representatives of the nuclear industry will participate, as j
appropriate.
i
i i
]
2 C.
Regulatory Analysis Guidelines - Review and report on' proposed Revision 2 to NUREG/BR-0058, Regulatory Analysis Guidelines for U.S.
NRC.
Representatives of the NRC staff and the nuclear industry will participate, as appropria,te.
- D.
Meetina with the Director, NRC Office of Nuclear Material Safety and Safeauards (NMSS) - Meeting with Director, NMSS, _ to discuss items of mutual interest, including matters such as the status of NRC and industry proposals for revised security requirements for nuclear power plants, status of the high level waste storage and disposal programs, and regulatory changes as a result of the incident which occurred at the GE Wilmington Facility.
E.
Risk-Based Reculation/Fitzpatrick Nuclear Plant IPE - Briefing by and discussion with representatives of the New York Power Authority (NYPA) regarding NYPA's views'on risk-based regulation, and the results of the Fitzpatrick Individual Plant Examination (IPE) and its relationship to the NRC Diagnostic Evaluation Team review of a this plant.
Representatives of the NRC staff will participate, as appropriate.
- F.
Reactor Operatina Experience - Briefing by and discussion with representatives of the NRC staff regarding events at operating nuclear power plants, including loss of high-head safety injection pumps at the Shearon Harris nuclear plant, and en Augmented Inspection Team (AIT) evaluation of an incident at the LaSalle nuclear station.
Report by the cognizant Subcommittee Chairman regarding a recent incident at the Fukushima nuclear plant in
.7apan during which reactor condensate and feedwater pumps were inadvertently turned off.
Representatives of the nuclear industry (licensees) will participate, as appropriate.
G.
Risk-Based Reaulation Review and report on NRC staff's proposal on risk-based regulation. Representatives of the NRC staff the nuclear industry will participate, as appropriate.
H.
Prioritization of Generic Safety Tssues - Review and comment on guidelines proposed by the NRC staff for prioritization of generic safety issues.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
I.
Environmental Oualification of Safetv-Grade Dicital Computer Protection and Control Systems - Discuss proposed ACRS report on the nature of the NRC research program to qualify safety-grade digital computer protection and control systems proposed for use in nuclear power plants.
Representatives of the NRC staff and the nuclear industry will participate,as appropriate.
J.
Activities of ACRS Subcommittees and Members - Reports and discussion regarding assigned Subcommittee activities, including a report of the ACRS Planning and Procedures Subcommittee regarding conduct of Committee activities.
- Open/ Closed 1
L
i 3
- K.
Appointment of New Members Discuss qualifications for nominees for vacancies during 1993 and qualifications of candidates nominated for appointment to the ACRS.
L.
Reconciliation of ACRS Comments and Recommendations - Discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to ACRS comments and recommendations.
M.
Future ACRS Activities - Discuss topics proposed by the ACRS Planning and Procedures Subcommittee for consideration by the full Committee.
N.
Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed at previous. sessions as time and availability of information permit.
Advanced Boilinct Water Reactors, November 18-19, 199'2, 7920 Norfolk Avenue, Bethesda, MD (El-Zeftawy), 8:30 a.m.,
Room P-4 22.
The' Subcommittee will continue its review of the Final Safety Evalua-tien Report (FSER) for the ABWR design and any' residual issues.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the nights of November 17 and 18:
t Michelson HYATT Shewmon NONE-Carroll HOLIDAY INN Wylie HYATT Catton HYATT Costner NONE Davis NONE Kress HYATT Advanced Pressurized Water Reactors, December 8,1992, Bethesda, MD i
- Postponed to February 10, 1993.
Joint Control and Electrical Power Jvstems/Probabilistic Risk Assessment, December 8, 1992, 7920 Norfolk Avenue, Bethesda, MD (Coe), 8:30 a.m.,
Room P-110.
The Subcommittees will review the proposed final amendment to the Station Blackout Rule (10 CFR 50.63) and the associated Regulatory Guide 1.9, Revision 3,
regarding the reliability of diesel generators.
Lodging will be announced later.
Attendance by the following is anticipated:
Wylie Lindblad Lewis Michelson Carroll Wilkins Davis Singpurwalla Kress
- Open/ Closed
e 4
4 Plant Operations, December 9, 1992, 7920 Norfolk Avenue, Bethesda, lid (Coe), 8:30 a.m.,
Room P-110.
The Subcommittee will discuss proposed changes to the Systematic Assessment of Licensee I
Performance (SALP) program included in SECY-92-290 as well as issues and concerns associated with the overall SALP process.
Attendance by the following in anticipated, and reservations have been made at the hotels as irJi ated for the night of December 8:
Carroll HOLIDAY INN Kress HYATT l
Catton HYATT Michelson HYATT Davis NONE Shewmon NONE
[
Lewis HYATT Wilkins HOLIDAY INN l
Lindblad RESIDENCE INN Wylie
, HYATT l
Plannina and Procedures, December 9,
1992, 7920 Norfolk Avenue, j
Bethesda, MD (Fraley), 3:00 p.m.
- 5:30 p.m.,
Rodm ' P-4 22.
The Subcommittee will discuss proposed ACRS activities and - related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed.
Portions of this meeting will be closed to discuss information the release of which would represent
~
a clearly unwarranted invasion of personal privacy.
Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of December 8:
\\
Shewmon NONE Carroll HOLIDAY INN I
Wilkins HYATT l
392nd ACRS Meetina, December 10-12, 1992, 7920 Norfolk Avenue, Bethesda, MD, Room P-110 - Agenda to be announced.
Control and Electrical Power Systems, January 6, 1993, 7920 Norfolk I
- Avenue, Bethesda, MD (Coe),
8:30 a.m.,
Room P-110.
The Subcommittee will review the NRC staff's proposed resolution of Generic Issue 120, "Online testability of Protection Systems."
i Lodging will be announced later.
Attendance by the following is anticipated:
i Wylie Lewis
{
Carroll Lindblad l
Davis Michelson
?
I t
s
~
~
J 5
Plannina and Procedures, January 6,
1993, 7920 Norfolk Avenue, Bethesda, MD (Fraley), 3:00 p.m.
- 5:30 p.m.,
Room P-422.
The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed.
Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.
Lodging will be announced later.
Attendance by the following is anticipated:
i Shewmon Carroll Wilkins t
393rd ACRS Meetina, January 7-9,
- 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110 - Agenda to be announced.
Advanced Pressurized Water Reactors, February 10,
- 1993, 7920 Norfolk Avenue, Bethesda. MD (Igne), 8:30 a.m.,
Room P-110.
The Subcommittee will review the NRC staff's Draft" Safety Evaluation Report (DSER) for certification of the ABB CE Systems 80+ Design.
l Lodging will be announced later.
Attendance by the following is anticipated:
Carroll Michelson Catton Shewinon Davis Wylie Kress 394th ACRS Meetina, February 11-13, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110 - Agenda to be announced.
l Thermal Hydraulic Phenomena, Date to be determined (November),
Bethesda, MD (Boehnert). The Subcommittee will continue its review of the NRC staff program to address the issue of interfacing systems LOCAs.
Attendance by the following is anticipated:
J Catton Dhir Davis Schrock Kress Zuber Ward Wilkins i
l l
6 Severe Accidents, Date to be determined (November / December),
Bethesda. MD (Houston). The Subcommittee will review the technical position on steam explosions.-
Attendance by the following is anticipated:-
Kress Shewmon Catton Ward
-Davis Kerr Lindblad Lee Michelson Decay Heat Removal Systems, Date to be determined (November /
December), Bethesda, MD (Boehnert).
The Subcommittee will review the proposed final resolution of Generic Safety Issue 23, " Reactor Coolant Pump Seal Failures."
Attendance by the following is anticipated:
b Catton Michelson Davis Wylie Lindblad Thermal Hydraulic Phenomena, Date to be determined (January, _1993),
Idaho Falls, ID (Boehnert).
The Subcommittee will review: -(1) the
+
code scaling, applicability, and uncertainty (CSAU) evaluation methodology as applied to the RELAPS/ MOD 3 code for use in modeling advanced LWRs, and (2) the status of the effort to apply the CSAU methodology to a small-break LOCA calculation using the RELAP5/ MOD 3 code.
Attendance by the following is anticipated:
Catton Dhir Davis Schrock Kress Ward Wilkins Zuber Thermal Hydraulic Phenomena, Date to be determined (January,1993),
San Jose, CA (Boehnert).
The Subcommittee will review the GE code qualification report that supports use of the TRACG code for the Simplified BWR design certification effort.
Catton Dhir Davis Schrock Kress Zuber Wilkins l
1
t APPENDIX IV MINUTES OF THE 390TH ACRS MEETING OCTOBER 8-10, 1992 LIST OF DOCUMENTS RECEIVED BY THE COMMITTEE INote:
Some of the materials listed may have been provided for ACRS Internal Committee Use Oniv or may contain Proprietary Informationi ACRS MEETING NOTEBOOK Boilina Water Reactor Stability Project Status Report e
Letter for Paul Boehnert from William Kerr, dated September 18, 1992, re, Commente on September 17, T/H Subcommittee and the Core Performance Subcommittee Letter for Paul Boehnert from John Lee, dated September 28,
- 1992, re, T/H Phenomena Subcommittee Meeting on September 17, 1992 [ Prepared for Internal Committee Use]
Letter for Ivan Catton from Walter Lipinski, dated September 22,
- 1992, re, BWR Core Power Stability
[ Prepared for Internal Committee Use]
Excerpt pages from Argonne National Laboratory, re, Design of the Argonne Low Power Reactor dated, May 1961 Memorandum for I.
- Catton, J.
Wilkins from P.
- Boehnert, dated October 1, 1992, re, ACRS Meeting Summary / Minutes of the Joint T/H Phenomena / Core Performance Subcommittee on September 17, 1992
[with attached Working Copy Minutes, Prepared for Internal Committee Use)
Letter for Lando Zech from F.
Remick, dated June 14, 1989, re, BWR Core Power Stability Desian Acceptance Criteria e
Tentative Schedule Attachments to Project Status Report e
Policy Issue SECY-92-299 August 27, 1992 Letter for James Taylor from David Ward, dated August 12, 1992, re, ACRS Plan for Reviewing the Application for Certification of the GE ABWR Design Letter for Chairman Selin from David Ward, dated June 16, 1992, re, Interim Report on the Use of Design Acceptance Criteria in the Certification of the GE Nuclear Energy ABWR Design Environmental Oualification of Electric Ecuipment for License Renewal e
Tentative Schedule Attachments to Project Status Report e
Memorandum for Raymond Fraley from John Craig, dated July 10, 1992, re, Request for Review of Branch Technical Position on Environmental Qualification of Electric Equipment for License Renewal [with enclosures) l Low-Voltage, In-Containment, Environmentally-Qualified Cable License Renewal Industry Report, NUMARC Report 90-08, dated July 1990
~
2 Form and Content for a Design Certification Ruls Tentative Agenda Project Status Report e
10 CFR Part 52 Policy Issue SECY-92-287 August 18, 1992 Letter for Chairman Kerr from Carlyle Michelson, dated August 14, 1990, re, Level of Detail Required for Design Certification Under Part 52 Staff's Presentation on Form and Content Design Certification Rule by J.
Wilson, NRR, M. Malsch, OGC Maintenance of Nuclear Power Plants Proposed Agenda e
Status Report e
Memorandum for Raymond Fraley from C.
Heltemes, dated September 9, 1992, re, Proposed Public Comment Package re, Implementation Guidance for the Maintenance Rule, 10 CFR 50.65 [with enclosures Appendix A & F1 Implementacion of NRC Maintenance Rule, Excerpt from 385th Meeting Minutes, May 6-9, 1992 Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Draf t) NUMARC 93-01, Revision 2A, July 9, 1992 Memorandum for J. Sniezek, W. Russell, et al.,
from Jack Roe, dated May 5, 1992, re, A Comparison of Maintenance and License Renewal Rules Letter for Chairman Carr from David Ward, dated May 20,
- 1991, re, Staff Evaluation and Recommendations on Maintenance Rulemaking Letter for Chairman Carr from Forrest Remick, dated October 12, 1989, re, Proposed Revised Policy Statement on the Maintenance of Nuclear Power Plants Letter for Chairman Zech from Forrest Remick, dated April 11,
- 1989, re, Proposed Final Rulemaking Related to Maintenance of Nuclear Power Plaats Letter for Chairman Zech from William Kerr, dated September 13, 1988, re, Proposed Rulemaking Related to
)
Maintenance of Nuclear Power Plants Letter for Chairman Zech from William Ecrr, dated February 16,
- 1988, re, ACRS Comments on SECY-87-314, Interim Policy Statement on Maintenance of Nuclear Power Plants, dated December 30, 1987 Letter for William Dircks from David Ward, dated August 13, 1985, re, ACRS Comments on the NRC Maintenance and-Surveillance Program Plan SECY-85-129 Dated April 12, 1985 Training _and Oualification of Nuclear Power Plant Operations Proposed Agenda e
Status Report e
Memorandum for Raymond Fraley from C. J. Heltemes, dated j
September 11, 1992, re, Request for Review of Proposed Rule Change to 10 CFR Part 55 and Associated Regulatory Analysis [with enclosures)
r 1
./
USE OF PRA IN THE REGULATORY PROCESS Tentative Agenda e
Project Status Report e
Letter for Chairman Selin from David Ward, dated July 19,
- 1991, re, The Consistent Use of Probabilistic Risk Assessment Letter for Chairman Selin from David Ward, dated December 14, 1991, re, The Consistent Use of Probabilistic Risk Assessment Memorandum for James Taylor from Samuel Chilk, dated January 24, 1992, re, Staff Requirements - Briefing on' Regulatory Application of PRA Policy Issue SECY 92-273 dated August 6, 1992, re, Staff Use of PRA [with enclosures]
ENVIRONMENTAL OUALIFICATION OF-SAFETY-GRADE DIGITAL COMPUTER PROTECTIN AND CONTROL SYSTEMS Project Status Report e
Policy Issue SECY-91-273 dated August 27,
- 1991, re, Review of Vendor's Test Programs to Support the Design Certification of Passive Light Water Reactors NRC Research presentation exerpts from June 16, 1992 Joint Subcommittee Meeting of Computers in NPP Operations, and Reliability and Quality YANKEE ROWE NUCLEAR POWER PLANT e
Tentative Schedule Project Status Report e
Policy Issue SECY-92-203 dated August 14, 1992, re Action Plans to Implement the Lessons Learned from the Yankee Rowe Reactors Vessel Embrittlement Issue
[with enclosures]
Letter for Joe Colvin from James Taylor, dated July 9, 1992, re, Schedule two meetings to discuss important issues re, Coordination of Generic Reactor Pressure Vessel Integrity and the Possible Use of the Yankee Rowe, and Studies of Generic Plant Components Systems and Structures Aging Evaluation and Management i
l
. ~ - -
. e e 4_.
ACRS MEETING HANDOUTS AGENDA DOCUMENTS l
ITEM NO.
3.0 Desian Acceptance Criteria 1.
Cross Reference of Generic ITAAC to System ITAAC 2.
Instrumentation and Controls DAC Material 3.
Chapter 7 " Instrumentation and Control 4.
Control Room Design DAC Material 5.1 Form and Content for a Desian Certification Rule 5.
Letter for Dennis Crutchfield from Raymond Ng, dated October 5, 1992, re, SECY-92-287 Form and Content for a Design Certification Rule 6.1 Future ACRS Activities 6.
Memorandum for James Carroll and C.
Wylie from Steve l
Mays, dated July 7,
1992, re, River Bend Reliability Program
[ prepared for internal Committee use, with enclosures]
r 7.
Memorandum for ACRS Members from Richard Savio, dated
[
October 8, 1992, re, Future ACRS Activities - 391st ACRS Meeting November 5-7, 1992 7.1 Reconciliation of ACRS Comments and Recommendations I
8.
Note from Dave Ward to Members, dated October 7,
9.
Letter for David Ward from James Taylor, dated September 3,
1992, re, Response to Chariman's Lett,r dated August i
12, 1992 re, ITAAC for GE ABWR j
10.
Letter for Chairtaan Selin from David Ward, dated August 12,
- 1992, re, Inspections,
- Tests, Analyses,.
and l
Acceptance Criteria Program for the GE ABWR Design l
11.
Letter for David Ward from James Taylor, dated October 5, 1992, re, Proposed Resolution of Generic Safety Issue 106, " Piping and the Use of Highly Combustible Gases in Vital-Areas" 12.
Letter for James Taylor from David Ward, dated August 14, 1992, re, Proposed Resolution of Generic Safety Issue-106, " Piping and Use of Highly Combustible Gases in Vital Areas" 13.
Letter for David Ward from James Taylor, dated October 1,-
1992, re, Proposed Regulatory Guide and Interim Standard Review Plan for License Renewal and a Branch Technical Position on Fatigue Evaluation Procedures
.i 14.
Letter for James Taylor from David Ward, dated August 17, 1992, re, Proposed Regulatory Guide and Interim Standard l
Review Plan for License Renewal and a Related Branch Technical Position on Fatigue Evaluation Procedures 15.
Letter for David Ward from James Taylor, dated September 28, 1992, re, Elimination of Requirements Marginal to Safety
5
\\
16.
Letter for Chairman Selin from David Ward, dated August 11, 1992, re, Elimination of Requirements Marginal to Safety 17.
Letter for David Ward from James Taylor, dated September 23, 1992, re, Staff Response to ACRS Letter on the Severe i
Accident Research Program Plan [with attachments]
18.
Letter for Chairman Selia from David Ward, dated August 18, 1992, re, Severe Accident Research Program Plan 19.
Letter for David Ward from James Taylor, dated September 18, 1992, re, Proposed Resolution of Generic Issue 151,
" Reliability of ATWS Recirculation Pump Trips in Boiling Water Reactors" 20.
. Letter for James Taylor from David Ward, dated August 14,
- 1992, re, Proposed Resolution of Generic Issue 151,
" Reliability of ATWS Recirculation Pump Trip in Boiling Water Reactors" 7.2 21.
Comments on the Staff Response to the ACRS Report on the Severe Accident Research Plan 21.2 Recommendations Regarding Candidates for NRC Thermal-Hydraulic Review Group 22.
Memorandum for ACRS Members from P.
- Boehnert, dated October 7,
- 1992, re, Constitution of NRC Task Force Pursuant to Commission Direction for NRC-Sponsored i
Confirmatory Testing in Support of AP600 Design certification [with enclosures, prepared for internal Committee use]
LIST OF HANDOUTS OTHER THAN ACRS 23.
Staff Presentation on Form and Content Design Certification Rule, by Jerry Wilson - NRR 24.
Presentation to ACRS BTP on Environmental Qualification i
of Electrical Equipment, Doug Walters - NUMARC 25.
NRR Staff Presentation to the ACRS,
Subject:
BTP on Environmental Qualification of Electric Equipment Important to License Renewal, by P.
Shemanski - NRR 26.
Item 3, SECY-92-299, Development of DAC for the GE ABWR in the Areas of I&C and Control Room Design, by T. Boyce
- NRR 27.
Living PRA/ Reliability Assurance Program, by W. Russell 28.
Faxed copy from Winston & Strawn to David Ward, dated October 7, 1992 [ Official Use Only]
29.
Item 2, GE Handout ATWS Consequences 30.
Item 9, NUMARC Presentation to ACRS on Maintenance Rule Implementation 31.
Item 9, Monitoring the Effectiveness of Maintenance at NPP 32.
Item 11, ACRS Briefing on Licensed Operator Requalification, dated October 9, 1992, by Paul Lohaus, Robert Gallo 33.
Item 12, Status Report on the PRA Working Group, by Mark Cunningham, NRR 34.
Item 13, Qualification of Safety Grade Digital Computer
A 6 P
s Protection and Control System, by Scott Fewberry 35.
Memorandum for Raymond Fraley from Eugene Imbro, dated October 7,
- 1992, re, Draft Generic Letter on the Availability and Adequacy of Design Bases Information 36.
Item 15, NRR Staff Presentation to the ACRS, Task Action Plans to Implement Lessons Learned from the Yankee Rowe Reactor Vessel Embrittlement Issue, by Patrick Milano 37.
Item 15, Yankee Atomic Electric Company, Lessons Learned from Reactor Vessel Effort 38.
Advance Draft Copy, to R.
Savio, dated October 9,
- _1992, re, Risk-Based Regulation 39.
Memorandum for see attached list from Eric Beckjord, dated September 4,
1992, re, Twentieth Water Reactor Safety Information Meeting 40.
The Oregonian News Article, dated October 2,
- 1992,
Subject:
A Slip of the Tongue Triggers False Fears of Disaster at Hanford 41.
Letter for John C.
Hoyle from Herbert Bardach, dated September 22,
- 1992, re, Computer Codes Used in the Nuclear Industry I
w
,-