ML20059C778
| ML20059C778 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/06/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2872, NUDOCS 9311020012 | |
| Download: ML20059C778 (38) | |
Text
~
~ Y ?c.Z i
$ i:Ig ;!![ i{'}
OD4 /d/.#7/93 1
(; ' '.
J. Ernest Wilkins, Jr.h [h,d. h L d Gi I
G k 12at Issued: 5/18/93
'Certifled By:
June 6, 1993 i
TABLE OF CONTENTS MINUTES OF THE 395TH ACRS MEETING March 11-12, 1993 I.
Chairman's Report................................
1 II.
Current License R";.e wal I ssues....................
1 III.
Computer Issues...................................
4 IV.
Reactor Operating Experience - Fort Calhoun Station loss-of-coolant Event of July 3-4, 1992...
6 V.
ISO Quality Standards.....................
7
'v l.
ACRS Subcommittee Activities.....
9 VII.
Future ACRS Activities.......................
11 VIII.
Upgrade of Confer ence Room................
13 IX.
Reconciliation of ACRS Comments and Recommendations.........................
13 X.
Appointment of New Members....
13 XI Miscellaneous Generic Letter on Emergency a
Response Data System Test Program.........
14 Proposed NRC Generic Lette* "Line-Item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operation..........
14 Revisions of ACRS Subcommittee Assignments.
14 XIV.
Summary / List of Follow-up Matters................
14 XV. Executive Session Reports........
15 Memorandums..............
................ 15 Supplement - Official Use Only
[ SUPPLEMENT REMOVED - FOIA EX (b) (4)]
0200ng
<b0 recrm cams
(>"'"'" "7 9311020012 930606
^
Y 0\\
V./
ii APPENDICES MINUTES OF THE 395TH ACRS MEETING MARCH 11-13, 1993 1.
Attendees II.
Future Agenda III.
Future Subcomittee Activities IV.
List of Documents Provided to the Comittee t
i
?
J 0 **I** } //$<k 3 S,,o.*
- e
.,a-m~
f g
Federr.1 Reg. ter
- 21. 58, No. 40 / Wednesday, March 3, 3 / Notices A 2279' is i
containment under certain conditions.
In an increase in risk to plant personnel path modifications.From the.
i In the event of the loss of long term and to the public (Reference 12).
environmental assessment, the staff decay heat removal capability without Therefore, this alternative is not concluded that there are no significant drywell failure, the containment practical or reasonable.
radiological or non radiologicalimpacts associated with the installation of drywell will probably fail because of Find.mg of No S.ignificant impact hardened wetwo'l vents and that such overpressmization. The drywell failure The staff reviewed the plant-specific use will not have significant adverso could have a significant effect on the ability to return the plant to a safe and features In conjunction with the effects on the quality of the human controlled condition and would result installation of hardened wetwell vent environment.
DENTS INVOLVtNG LDSS OF DECAY HEAT RchovAt.
TAKE 1.--ESTm4ATED REDUCTION OF POTENTIAL RGKS OF SEVERE Acc:
CAPABUTY (TW ACCDENT SECUENCES)
Posennel r6sk re-TW Irocpency (per dur. tun (persons-InstenatiMcost Plant nerne seector.ynar) rom per roedor-
- (tramorg year} *
' 0.75 2.3 E-05 32.7 Browris Ferry 1 2J E-05 32J
/ ( 015 2.3 E-05 32J
..wuw. 0.75.
Broers Ferry 2 _
' Broaria Ferry 3 4.5 E-05 44 4
.' --%'0.75 Brunemeck 1 45 E-05 44 4
- ,.yag.; 925 r Buureenck 2 43 E-05 45E 75 Cooper 1.4 E-05 60 2 T @140
.* W'.' t.00' O."'N'M.75 p.eeden 2 _
1.4 E-05 50 2
+*015.
Dreeden 3 43 E-45 610 Duane ArncAd 43 E-05
' 192.4 43 E-.06 45.5 9r,4MhMOAg * -
Ferrrt 2
~ - *
- Fagetit1 d.5 E-45
'392 3 4%t'*075 f
Haecri 1_ '
M 43E45
- 30.2 McM*#025 s.
Hat:h 2 -
6.3 E-06
. 281.9
',pa yrW.'C75 1.4 E-oS 36.1 {, p,%ft $.10 Hope Cseek :
43 E-05 33.9
W.r.2, '**0J5
.s-QJ5 -
Mestone 1_
i Hor *=m 1.4 E 45 15.3 y.
- r' i 1 t.50 Nine Wee Point t 1.4 E-05 55.4 3.6 E-.05 15.5 ;,. Mf*CJ5 - -
Oyseer Crosa 3.6 E-06 15.6 o pt'.v*'0J5 e PeadiDacom 2 2.3 E-45
' 31 2
% N 8025...
'f, Pescit Boeorn 3
' )-
VW 80JS -?
t Psgrtra 43 E-05 94.1, % Md.'0J5 I
1 Oued Celes 1 4.5 E-05 94.1 h
f Oued Celes 2
- ' ^ ^
- e V:J rQJS :
2J E-45
. 28 2 L
P vermore Yankee -
Mi-
-.,. w' ;'M N:
~
- Hnc enmow
,- >P~.
p.tg w
- 4 ' " g.' tr y y, s. -
,,,p.T
' tkensee Esst:ste.
-t
-ze
, ~,
ATWS." 1986 Water ReectoIr Safety Meeting, For the UA Nuclear Regulatory' ".* y -,.
h
- 1. SIX:Y 87'-297 US Nuclear Replatory
- 9. Kwam 1. N. tin =, and A. Pernon, Commission.
Referencse Gaithersburg, Maryland,Odobar 1986.
Director, Office ofNuclear He man F. Marley, Commtaton " Mark 1 Containment.
t
" Design Considerations for implementing a f*~
Performance improvement Program Plan.
,, Vent-Filldr System at the BARSEBACK' Begulation.
Commission Paper from V. Stello to NRC
. Nudear Power Plant " International Meeting IFR Doc. 93-.4870 Filed 1-2-93; By' r-mi.haars. Decstr.ber 8,1987.
o, K.. S; - p*
.}
- 2. NUREXF1150. UA NRC," Severe on the Thermal Nuclear Safety. Chicago, '
eiueen coos reews-u N
Aa:Ident RisksfAn Assessment for Five UA. August 29-September 2,1982 l '
r!
J
- 10. NUREG 1289,UA"NRCs* Regulatory / Advisory Committee on React,
- g,gj,;1 e
Nuclear Power Plants, June 1989-3 3
P
- 3. SECY-89-017,UA' NRC,TMarki,
nd Bw1Dt Analysiaf Unresoltori Safety a
- r Containment Performana improvement
- lasue A ;45.. Shutdown Decay Heat Renoval Sat uorde; Meeti Agende
%.W.d E D'
y Pmsram**Commlaston Paperfro. V. Sto!!o Requirements *,Noe=mimi'1968.'
W In accordance with the purposespfn y
to NRCr==teners.}anuarfEJ,1989..
11&rtter frosn).Dallman to O Ridgely,"A sedions 29 and 182b.cf the Atoutic.83C
- j
, w,.
4.Marnr-=ade from SJ.Culk to V.t L.
pggg BWR Mark H
- lithe %
Contalament ht%" Fallure Modes,and Energy Act (42 U.S.C.2039,428p r
i d'
y gg-Advisory Committee on Reed 0rg a
Potentialimprov=r==teinferiormanos -
$ $ ' '.1989..5.litteYfEx"nb,.MddaNt'[DICr cs,'
May 10,1989[py,@Q,W y Safeguards will hold e m '
fun 12.NUREGn2-5225. Addendum 1,"An March 11-13,1993,'in tocisp
,y. ?
't ' WGuidellaan Revision 4.NEDO-31331,Manh. VentingRisk 1 Containment 7920 Norfolk Avenue,
.3g6 Cbatrman, BWROG,"SafetyEvaluation of '
/( -
OverviewofB U*..** BWR Owners Group-Emergency Fn,c.,,h
.An Evaluation of Maryland. Notice of this ineeting3ves.bf '
1 L.1987.". September 12.1GS8. C ' ~
Potential jf e l = ent,/.
pubushed in the Federal Regist aW,
- e4M'I
~~d
- 6. Memorandum 1roal M;Cunningham to
'impms, d,'Qine]E**b989dith.,
February 24,1993.
r.
W.D. Beckner,t'Redudion in Risk from the
- Nots Au refer ='ErO redey, March 11,19't3 L.*.$ jr p.t'h. b I
.. Addition of flerdened-Vents inllWR Mark I,,yggg4 @gg,,publicMbb'sts are
$4 p
8J0 caro:45 cm.: Openftig Remarks by l
- p Reedors."Odober19/1989*e r -
for a M C66nimba'sPd!!c 2 -
ACRS Chairman (Open) -The ACRS o ;%
.7. NUREC/CR-5225,UA NP." "An Lower Csairman will make openlugtetrarks'.4w.
Q -
Overview of BWR Mark 1 Containment e c. Damnga q@@.h-e regarding condud of the meeting sad $s.m W W'.Nv.WasRn@
@.4 Dated at Rdckville, Maryla$d, this 18th day cxxnment briefly regarding atome qt cdrcent 4 E
Venting Risk Impliostions," Novemter 1968. ^
- 6. Harring, R.M.,*Coptainment Venting as interest.The Committee will discuss 4.;
4*>7
'a Mitigation Technique kr BWR Mark I Plaat 'of February l19931bc s.i "t
2-a O
- n <
, u : a. f w.. k'. ; p W.
.4 a
ds f f-w :m,:,~a.m
i
~
Federal Register / Vol. 58, No. 40 / Wednesday, March 3,1993 / Notices 12230 10.45 am-11:30 am: Appointment of determined by the Chairman, priorities for preparation of reports during New Members (Open/ Closed)--Th8 Information regartling the time to be set this session.
Cornmittee will dhcuss the qualifications of aside for this may be obtalral ~
6:45 am-20.45 am:Outrent b, cense b " PMisid t hone call to the Repemd issues (OpenHThe,Coaunittee will candidates preposed for appointment to %
I Achng AGS Encube Erector pdor to bear a briefing by and boid discussions with ccmmittee Portions of this session will be closed to the meeting. In view of the possibility representatives of the NRC staff on b status discuss information the release of which that the schedule for ACRS meetings of current license renewal issues, the establishment of a senior management review would represent a clearly unwarranted may be adjusted by the Chairman as gmup to review the harmontration of the invasion of personal princy.
nocessary to facilitate the conduct of the Maintenana and Ucense Renewal Rules.
11:30 am-12 noon: Upgmde of ACRS I1 am-fI:30 om: Computer Issues Conference Room (OpenHThe Committee meeting, persons planning to attend (OpenHThe Committee will hear a briefina will be briefed by the ACRS staff on use of should check with the Acting ACRS 2p pgmde A Conference NR staff ing ad "U "
progress toward the staff s development of Room (OpenHThe Committee will be I have determined in accordance with str.ndards and cnteria for digital briefed by the ACRS staff on the architectural subsection 10(d) Public Law 92-463 that instrumentadon and contml systems and the arrangement for the now conference room.
it is necessary to close portions of this staffs pohey on diversity.
2:30 p.m.-2:25 p.m.: Future AGS meeting noted above to discuss 12:30 cm-12:30 p.m.:Research on Activities (OpenFThe Committee will Orgamzotionalfoetors (OpenHThe discuss b report of the Ptanning and Proprietary Information applicable to the matters being considered per 5 rh=ntttee will discuss proposed AN Pmcodures Submmmittee negarding items the pmp sed for c nsideradon by the full U.S.C. 552(c)(4) and information thek release of which would represent a ~
zation f athe C Cominee.MPm:hpadon of AGS clearly unwarranted invasion of Study of Human Performance in Operating 2:35 Pm Events. Representatives of the NRC staff and BePorts (Open)-The Cocomittee will discuss personal privacy per 5 U.S.C. 552b(c)(6).'
of the industry will participate as eppmpriate.
[
s [ gitems Further information regarding toph to be discussed, whether the meetin n/blosed b 3N Pa-4 P.m.:ReconcUiadon of ACHS has been cancelled or rescheduled, ittee Cominents and Recommendauons (OpenH Chairman s ruling on requests for the er cs O will hear a briefing and hold discussions The Committee will discuss responses reSarding the reactor trip and stuck open received imm the NRC staff on opportunity to present oral statements pmesurizer safety valve event of July 3.1992.
recommendations made in ACRS rpwrts.
and the time allotted can be obtained by that omunsi at b Fort Ca:hota Nudcar 4PA-42pm: Report of the Plannin#
a prepaid telephone call to the Acting Power Plant. Representatives of the license, and Procedures Subcommittee (OpenHThe ACRS Facutive Diredon Dr. John T.
and of the NRC staff will participate, as Umrnittee will discuss the report of the Larkins (telephone 301-492-4516),
eppmpriate. -
Planning and Pmcedures Subcommittee, between 8:00 a.m. and 4:30 p.m. e.a.t.
Portions of the session will be closed as 4N Pa-6 pa:Pwpamtion of ACRS i
necessary to discuss Propriet ary Information Reports (Open)--The Committee will discuss Dated: February 25,1993.
related to this subject.
Pmposed reports regarding items considered khn C. Hope.
J 15 pm-4.45 pm: ISO Quahry during this moedag.,
s 3
,4 Standards (OpenHThe Committee will hear
[FR Doc. 93-4871 Filed 3-2-93; 8:45 aml a briefing by and hold discussions with SaturUy, Manh 13,1993 representatives of the NRC staff regarding the 8N om-12:30 pm:Prepamtion of ACRS na m ocooerse m -u ISO 9000 quahty management standard used Reports ( mn)-The Committee will disats:.
by the European mmmunity, and how it pr posed nmittee reports regarding items differs imm the quality standards being used cmsidend during this mating.
SECURITIES AND EXCHANGE - -
in tbe U.S. nuclear industry.
32N Pa-2 Pm:Miscenanwus (Open> coyyggg;oy 4.45 pa-6 p.m.: Proposed ACRS Report The Committee will discuss matters
.I.
on ComputerIssues (
nHThe Committee mnsidered but not completed at previous
[Releau No.34-31920, FDe No.SR-CBOE.
will discuss a pm ACRS report on the meetings as time and availability of 92-171 NRC staffs activities in defining appropriate inimnation pennit, Self 4egulatory Organizations; Order standards and requirements for computer, based instrumentauon and contml systems.
Procedures for the condum of and Approving and Notice _of Filing and resentatives of the NRC staff and of the partici tion in ACRS meetings were Order Granting Accelerated Approval Regustry will participete. as appropriate' in p bli b the Fhl @m to Amendment Nos.1,2,3, and 4 to i
Friday, March 12.1993 Odober 16,1992 (57 FR 47494). In Proposed Rule Changes by the a(x;ordance with these procedures, oral Chicago Board Options Exchange, f
8N om-8:45 om: ACRS Subcornmittee Activities (OpenHThe Committee will or written statements may be presented ating to Mble Exchange discuss the status of ACRS submmmittee by membuts of the public, recordings Options ("Ft.EX Options")
j assignments, including-(a) Alternate will be permitted only dudng those P ugging criteria for degraded steam open portions of the meeting when a Febru #24*1993' l
genentor tubes. (b) piping design transcdpt is being kept, and uestions
- 1. Introduction 9
impmvements for advanced plant designs,(c) may be asked only by members of the e
pmposed priority ranking of Generic Issue Committee,its consultants, and staff.
On August 31,1992, the Chicego t
1 152," Design Basis for Values that Might be Persons desiring to make oral statements Board Options Exchange, Inc. ("CDOE" Sub)ected to Significant Blowdown Imeds,"
should notify the Acting ACRS or "Eyrbnge") submitted to the and (d) the PWR version of the REI.APS/
MOD-3 code and the analytical and Executive Director, Dr. John T. Larkins.
Secudtles and Exchange Commission experimental pmgrams in support of the as far in advance as ptacticable so that
(" Commission"), pursuant to Sectie 8PP P ate arrangements can be mado 19(b) of the Securities Exchange Ad of s
d presentat oft RC ta will to allow the necessary time during the 1934 ("Act")8 and Rule 19tH participate, as appropriate.
meeting for such statements. Use of still. thereunder,8 a proposal to list and trade l
9 45 am-10.30 a.in.: Preparation of ACRS rnotion picture, and television cameras Reports (Open)- -The Comrnittee will discuss during this meeting may be limited to o s o s c 7sgbxillaszl.
proposed reports items mnsidered during sebcted portions of the meeting as ur cnt aso istmioon this macting.
/
'o,,
UNITED STATES
/
NUCLEAR REGULATORY COMMISSION n
3 I
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20685
'%......c March 3, 1993 SCHEDULE AND OUTLINE FOR DISCUSSION 395TH ACRS MEETING MARCH 11-13, 1993 Thursday. March 11. 1993. Room P-110. 7920 Norfolk Avenue. Bethesda Md.
8:45 A.M.
ODeninc Remarks by ACRS Chairman (Open) 1)
8:30 1.1)
Opening statement (PGS/SD) 1.2)
Items of Current Interest (PGS/JTL) 1.3)
Priorities for preparation of'ACRS reports (PGS/SD) 10:45 A.M.
Current License Renewal Issues (JCC/WJL/EGI) 2)
8:45 (Open)
TAB 2 -------- 2.1)
Report by.the Subcommittee Chairman regarding the status of current license renewal issues, including the establishment of a senior management review group to review the harmonization of the Maintenance and License Renewal Rules 2.2)
Briefing by and discussions with representatives of the NRC staff.
Representatives of the nuclear industry will participate, as appropriate 10:45 11:00 A.M.
BREAK 3) 11:00 11:30 A.M.
Comouter Issues (HWL/DC) (Open)
TAB 3 -------- 3.1)
Report by the Subcommittee Chairman on the need for and the progress toward the staff's development of standards and. criteria for digital instrumentation and control systems and the staff's policy on diversity 3.2)
Briefing by and discussions with representatives of the NRC staff
2 4) 11:30 12:30 P.M.
Ergoosed ACRS Reoorts (Jcc/HA) (Open) 4.1)
Discuss the scope and content of proposed ACRS reports on the NRC sponsored research on organizational factors, and on the NRC staff's Study of Human Performance in Operating Events 12:30 1:30 P.M.
LUNCH 5) 1:30 3:00 P.M.
Reactor Ooeratina Eroerience (JCC/DC)
(Open/ Closed)
TAB 5 ------- 5.1)
Report by the Subcommittee Chairman regarding the reactor trip and stuck-open pressurizer safety valve event of July 3, 1992, that occurred at the Fort Calhoun Nuclear Power Plant 5.2)
Briefing by and discussions with representatives of the NRC staff.
Representatives of the licensee will participate, as appropriate (Note:
Portions of this session will be closed as necessary to discuss Proprietary Information related to this subject) 3:00 3:15 P.M.
BREAK 6) 3:15 4:45 P.M.
ISO ouality Standards (TSK/MDH) (Open) 6.1)
Report by the cognizant ACRS TAB 6 --------
Member regarding the ISO 9000 quality management standard used by the European community, and how it differs from the quality standards being used in the U.S. nuclear industry 6.2)
Briefing by and discussions with an ACRS consultant.
Representatives of the NRC staff will participate, as appropriate 7) 4:45 6:00 P.M.
ProDosed ACRS Reoort on ComDuter Issues (HWL/DC) (Open) 7.1)
Discuss the scope and content of the proposed ACRS report on the NRC staff's activities in defining i
appropriate standards and requirements for computer-based instrumentation and control systems j
l 3
Fridav, March 12, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md.
9:45 A.M.
ACRS Subcommittee Activities (Open) 8)
8:30 8.1)
Report of the Materials and Metallurgy Subcommittee on (a) alternate plugging criteria for degraded steam generator tubes and (b) piping design improvements for advanced plant designs (PGS/EGI) 8.2)
Report of the Mechanical components Subcommittee Chairman on the NRC staff's proposed priority ranking of Generic Issue 152, " Design Basis for Valves that Might be Subjected to Significant Blowdown Loads" (CM/EGI) 8.3)
Report of the Thermal Hydraulic Phenomena Subcommittee on the RELAP5/ MOD-3 code and the analytical and experimental programs in support of the AP600 design certification (IC/PAB) 10:30 A.M.
Precaration of ACRS Reoorts (Open) 9)
9:45 Discuss proposed ACRS reporto regarding items considered during this meeting and previous meetings, including:
9.1) License Renewal Issues (JCC/WJL/EGI)
(tentative) 9.2) NRC sponsored research on organi-zational factors (JCC/HA) 9.3) NRC staff's Study of Human Performance in Operating Events (JCC/HA) 9.4) Computer issues (HWL/DC) 9.5) GE ABWR review schedule (CM/EGI) 10:30 10:45 BREAK
- 10) 10:45 11:15 A.M.
Euturg ACRS Activities (PGS/RPS) (Open) 10.1)
Discuss recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the Committee
- 11) 11:15 12:15 P.M.
Uourade of ACRS Conference Room (Open) 11.1)
Briefing by the ACRS staff on use of advanced audio-visual technology (JCC/MES/HSS)
i 4
11.2)
Briefing by the ACRS staff on the architectural arrangement for the new conference room (JCC/MLM)
-l 12:15 1:15 P.M.
LUNCH
]
2:15 P.M.
Precaration of ACRS Recorts (Open) l 12) 1:15 12.1 Discuss the scope and content of proposed ACRS reports on matters.
considered during this meeting 2:45 P.M.
Reconciliation of ACRS Comments and' 13) 2:15 Recommendations (PGS, et al./SD) (Open) 13.1)
Discuss replies from the NRC Executive Director for Operations regarding proposed reconciliation of ACRS comments and recommendations 2:45 3:00 P.M.
BREAK 4:00 P.M.
Anoointment of New Members (PGS/JTL) 14) 3:00 (Open/ Closed) 14.1)
Discuss qualifications of candidates proposed-for appointment to the Committee (Note:
Portions of this session will be closed, as appropriate, to discuss information the release of which would represent a clearly. unwarranted invasion of personal privacy.)
15) 4:00 4:30 P.M.
ACRS Subcommittee Activities (PGS/JTL)
(Open) 15.1)
Report of the Planning and Procedures Subcommittee 16) 4:30 6:00 P.M.
Precaration of ACRS Renorts (Open) 16.1)
Discuss the scope and content of proposed ACRS reports on matters considered during this meeting Saturday, March 13, 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, M51.4.
17) 8:30 11:00 A.M.
Precaration of ACRS Recorts (Open) 17.1)
Discuss the scope and content of proposed ACRS reports on matters considered during this meeting and previous meetings
6s h.
2 e
i4Ed
.+--#--*-
3 a
J e8*AL-8 d4 4
ham-+F-
+
5 1:00 P.M.
Miscellaneous (Open) 18) 12:30 18.1)
Complete discussion.of matters considered during this meeting'and matters considered but not completed.
at previous meetings as time and.
availability of information permit.
'l 1
9 h
e
)
. i
6 l
CHECKLIST FOR AGENDAS 1.
are times correct (am's and pm's) 2.
Closed and opens shown on each one 3.
check dates (Thursdays and Fridays) 4.
Check breaks:
Thursday:
LUNCHES:
THURSDAY FRIDAY 6.
Engrs. same as for letters and OK k
e
i Certified By:
5 J. Ernest Wilkins, Jr.
b MINUTES OF 395TH ACRS MEETING MARCH 11-12, 1993 The 395th meeting of the Advisory Comittee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md., on March 11-12, 1993.
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 Comittee members and other matters of a personal nature. 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: P. Shewmon (Chairman), J. E. Wilkins, (Vice Chairman), J. Carroll (Member at Large), I. Catton, P. Davis, H. 1.ewis, W. Lindblad, C. Michelson, T.
Kress, R. Seale, and C. J. Wylie.
I.
Chairman's Report (0 pen)
Note: Mr. Duraiswamy was the Designated Federal Official for this portion of the meeting.
Dr. Shewmon, ACRS Chairman, opened the meeting at 8:30 a.m. and mentioned the following matters:
agenda for this meeting presentation to Dr. Seale discussed priority of the reports the Comittee would work on this month I
II.
Current License Renewal Issues (0 pen)
Note: Mr. E. G. Igne was the Designated Federal Official for this portion of the meeting.
Mr.
- Carroll, Chairman of the Plant License Renewal Subcommittee, introduced this matter by asking the staff to address the results of the their senior management review on the harmonization of the maintenance and j
license renewal rules and its recommendations on how the license renewal rule is envisioned to be implemented.
Following the previous Comittee meeting with the Comissioners in December 1992, an SRM was issued requesting that the Comittee comment on the staff's efforts to harmonize the maintenance and license renewal rules.
2 Staff Presentations License Renewal - Staff Conclusions Mr. Travers, NRR, presented the status of the staff's efforts to examine a number of key license renewal issues focused on implementing the license renewal rule the Comission promulgated in January 1992.
He mentioned that the outcome of the staff's senior management review and the staff's proposal for implementing 10 CFR Part 54, " Requirements for Renewal of-Operating Licenses for Nuclear Power Plants," are delineated in SECY 04, dated March 1,1993. The staff plans to discuss this SECY at a public meeting on March 12, 1993 and meet with the Commission to discuss this matter on March 15, 1993.
In a reply to a question from Mr. Davis concerning current expectation for an application for license renewal, Mr. Travers stated that one of the B&W plants, as a result of the B&W Owners Group License Renewal efforts, is planning to submit an application in 1997.
Mr. Travers discussed the conclusions of the senior management review as follows:
The license renewal rule as promulgated needs no change.
The form of the renewal license (New License vs. Amendment) does not affect the scope of the technical issues reviewed or the safety evaluations required.
The Current Licensing Basis (CLB) is carried forward into the renewal period and NRC's regulatory processes will provide assurance that the CLB will be maintained through the renewal period.
For older plants, fatigue and EQ issues will be addressed as a current generic issue, not as part of the license renewal review.
For newer plants, fatigue and EQ issues will have to be addressed as part of the license renewal review.
In reply to a question by Mr. Carroll on the status of the current branch technical positions on fatigue and EQ, Mr. Russell, NRR, stated that the staff has concluded that the issues related to fatigue and EQ should be addressed for all facilities, not just those that propose to review their licenses. Action plans will be developed and subject to regulatory /back-I fit analysis in order to determine if today's operating plants relating to fatigue and EQ should be back-fitted.
Further, Mr. Russell stated that the staff is looking at safety margins for piping and other mechanical.
components and will make judgements as to whether modifications are needed on current staff positions.
Mr. Russell stated that new generic requirements will be promulgated using the action plan process and that new generic requirement issues will be presented to the ACRS for coment.
3 In reply to a question by Dr. Wilkins, Mr. Russell stated the 00R guidelines applied to plants that received their operating licenses before May 23, 1980.
NUREG-0588 guidelines were applied to those plants receiving their licenses after May 23, 1980.
Mr. Travers stated that the review philosophy is to consider broad ranges of plant structures, systems and components, which will be a mechanisms for dealing with the great majority of issues without requiring extensive analysis.
These mechanisms are in place today.
Mr. Travers noted that PRAs can be used for safety insights but not for directly reducing the scope of license renewal reviews.
However, PRA results can be used in effective maintenance programs and will thereby indirectly support dispositioning of license renewal issues.
In reply to a question by Mr. Davis, Mr. Travers stated that PRA insights can be used to increase the scope of review in connection with aging identification and management. Further, severe accidents and severe accident management are not to be revisited during license renewal reviews.
In reply to a question by Mr. Carroll on the makeup of the Senior Management Review Team, Mr. Travers, a member of the team, mentioned J.
- Sniezik, W.
- Russell, J.
- Partlow, F. Miraglia, and F.
Gillespie, are members.
In addition, other people, including A. Thadani, J. Richardson, etc., at times were in attendance.
Inteorated Plant Assessment (IPA)
Mr. Russell, NRR, discussed the IPA Program as it relates to the activities conducted under the maintenance and license renewal rules. All plant egyipment within the scope of the license renewal rule will be considered.
The scope will then be reduced based on the definition of SSCs important to license renewal, i.e.,
the standard safety-related equipment definition plus the nonsafety equipment whose failure could impact the ability of safety systems to perform their function, plus the regulations in 10 CFR 50.48 for EQ of equipment, pressurized thermal shock, ATWS and station blackout. From the plant technical specifications other items that are risk-significant are included for renewal consideration.
This scope of review should reduce plant equipment for renewal consideration by about 30 percent.
Mr. Russell felt that functional review may eliminate about another 5 percent of all equipment.
Uniqueness review determines if age-related degradation is unique to the renewal period as defined in 54.21(a)(3). He stated that not much equipment falls in this category.
If degradation is found to be unique to the renewal period, 54.21(a)(5) defines an effective maintenance program review.
Mr. Russell stated that the staff is proposing to determine the performance or condition of the component instead of evaluating the individual degradation mechanism for each component.
This will be evaluated by reviewing the completeness of the surveillance testing or the in-service inspection as found in the maintenance program, which will be fully implemented in current plants
l 4
when the first license renewal application is received in 1997.
Mr.
Russell stated that the staff estimates that about 60 percent of all plant equipment does have an effective maintenance program and that 5 percent of all plant equipment will need further maintenance program documentation that the staff will need to review and evaluate.
With respect to the operational phase reliability program, Mr. Carroll stated that this matter would probably be dealt with by the resolution of the maintenance rule.
In a reply to a question by Dr. Wilkins, Mr.
Russell stated that the regulatory guide for the maintenance rule which endorsed the NUMARC guidelines has been put for public comment and being evaluated by the staff. He mentioned that the NUMARC guidelines have been changed as a result of verification and validation program. These changes
~
have been reviewed by the staff and indicated that the changes are substantial enough to require another public notice and comment period.
Mr. Carroll noted that NUKARC was in attendance but not preoared for comments or presentation.
Conclusions This was an information briefing only.
The Committee did not comment on this matter as a result of this briefing. Mr. Carroll suggested that the Committee not respond to the Commission's December 24, 1992 SRM until after the Conmittee hears from industry (NUMARC) and until after the staff presents SECY-93-049 to the Commission.
III. Comouter issues (0 pen)
Note: Mr. D. Coe was the Designated Federal Official for this portion of the meeting.
Dr. H. Lewis, Chairman of the Computers in Nuclear Power Plant Operations Subcommittee, introduced this topic to the Committee by noting that there are two separate levels of discussion that must be undertaken. One is at the level of detail associated with conversions from analog to digital instrumentation and control (!&C) systems in existing plants.
The other is a higher level at which the criteria is established for decision-making at the first level.
He emphasized the need to keep the two discussions separate.
NRC Staff Presentation, Mr. William T.
Russell, Associate Director, inspection and Technical Assessment, Office of NRR Mr. Russell stated his agreement that there were both policy and technical issues that need to be discussed and that he was prepared to talk about both.
Mr. Russell made the following points:
Digital I&C can provide enhanced capabilities and improved safety.
m 4
5 The technology is changing rapidly ad staff recruiting is ongoing to bring special expertise in digital system applications to the NRC, even in the face of impending budget cuts.
Logical deficiencies embedded in software create a systemic failure mode to which probability of failure cannot be assigned.
The staff's approach to this has been to require diversity within the design of the control and protection system. Based on earlier ACRS coments, the staff will consider diversity achieved by a second dedicated simple digital
- system, and also under certain circumstances give credit to non-safety systems and/or mr.nual operator actions. The adequacy of such systems will be evaluated on a case-by-case basis.
Based on discussions with other regulatory authorities, the staff has identified the importance of writing specifications on hardware / software performance that are precise and unambiguous.
The question of analog to digital retrofits is being worked via staff dialogue with EPRI and NUMARC working groups.
Mr. Carroll asked why the staff does not intend to include severe accidents ir its review of I&C system mitigation capability. Mr. Russell responded im.t most of severe accident mitigation involves mancel (not automatic) actions, and will be treated under the staff position to require manual system level actuation.
Mr. Michelson questioned where and when the staff would review digital system failures due to pipe breaks or fires. Mr. Russell stated that pipe breaks were included in the staff's review, but that failure due to fire is being addressed under the physical separation requirements of the fire protection plan.
Mr. Michelson asked if the staff was considering the potential for multiple unwanted actions as a possible failure mode of digital I&C systems.
Mr. Chiramal, NRR, responded that a Failure Modes and Effects Analysis had been performed on the ABWR.
Mr. Russell added that the concern over possible control and safety system interaction was dealt with via the classical reliance on the protection system to initiate protective action if a control system malfunction threatened reactor safety.
Mr. Russell noted that digital I&C issues would be discussed as a portion of the May 3-4, 1993 Regulatory Information Conference and at a Research Workshop on digital and software issues planned for September 1993.
Conclusions The Comittee did issue a report to Chairman Selin on computers in nuclear power plants, as noted in Section XIII of these minutes, l
6 IV.
Reactor Ooeratino Exoerience - Fort Calhoun Station loss-of-Coolant Event of July 3-4. 1992 (0 pen)
Note: Mr. D. Coe was the Designated Federal Official for this portion of the meeting.
Mr. J. Carroll, Chairman of the Plant Operations Subcommittee, introduced this topic to the Committee by noting that this event had a number of similarities to the Three Mile Island 2 accident, most notably a temporarily stuck open safety valve.
He emphasized the Committee's interest in the operator response and emergency procedure effectiveness.
NRC Staff Presentation, Mr. Al Chaffee, Chief of the Events Assessment Branch in NRR Mr. Chaffee opened the presentation by introducing Mr. Phil Harrell, Chief of the Technical Support Staff in Region IV, who was the Augmented Inspection Team (AIT) leader for this event.
i Mr. Harrell described the sequence of events starting with an electrical problem on the power supply that caused the main turbine control valve to suddenly go shut.
This caused a reactor trip on high reactor coolant system (RCS) pressure, and the opening of both PORVs, which subsequently shut as designed, and one reactor vessel code safety valve.
The code safety valve lifted prematurely at 2430 psia (setpoint is 2500 psia plus or minus one percent) and reseated at 1745 psia (below the intended reseat pressure of 1950 psia).
As pressure began recovering, the code safety malfunctioned again, this time lifting at 1925 psia, causing a drop in RCS pressure that automatically actuated safety injection at 1600 psia.
Safety injection accompanied by the continuing discharge through the code safety caused pressurtzer level to increase to 100 percent at about 10 minutes into the event. Shortly afterward the RCS became solid (no steam bubble in the pressurizer).
Mr. Harrell described the difficulty the operators experienced in evaluating their instrument readings for subcooling margin during this event, due to the design feature of the subcooling margin instrument display that placed a question mark next to the reading when one input went off-scale.
He noted that operators ultimately resorted to manual calculations of subcooling margin using core exit thermocouples and wide range RCS pressure readings. He stated that the operators stopped two of the three running high pressure safety injection pumps (HPSI) in accordance with emergency operating procederes, leaving one HPSI and three charging pumps running.
Mr. Harrell described the subsequent cooldown during which operators controlled RCS pressure by throttling HPSI flow, due to the RCS water-solid condition. At one point, operators slightly overthrottled HPSI flow and the reactor vessel level indicating (RVLI) system ir.dicated the creation of a void in the upper vessel head.
Operators immediately increased HPSI flow and the indication returned to normal.
i
f, 7
Hr. Harrell briefly discussed the code safety valve malfunction as a result of valve " chattering" causing the setpoint adjustment bolt to reposition.
Finally, he described the licensee's corrective action to torque the locknut on the adjusting bolt to 400 ft-lbs and to place a locking device on the nut.
Mr. Carroll asked if operators had been given simulator practice on cooldowns with a LOCA condition.
Mr. Guliani, Fort Calhoun Station, replied that they had been given this type of training.
Mr. Lindblad asked if the simulator response had been checked against this actual event.
Mr. Guilani replied that it had, and had given good fidelity in simulating actual plant thermal hydraulic response.
Mr. Carroll asked for the staff's views on whether the information it disseminated to the industry on this event should have been more detailed.
Mr. Chaffee said they were reviewing this matter.
He felt the Augmented Inspection Team (AIT) looked at all aspects of the event and arrived at a valid conclusion that the operators performed correctly.
Mr.
J.
Rosenthal, AE00, added that his impression of this event was that it represented one of the few opportunities for the NRC to evaluate human and hardware interaction during a "TMI-like" event. He stated that this event demonstrated the successful implementation of pos>TMI requirements such as RVLI systems, emergency operating procedures, operator training, and control room instrumentation.
Mr. Davis questioned the operators intent to limit RCS pressure to reduce break flow as being counterproductive to maintaining subcooled margin.
Mr. Guliani replied that operators are trained to maintain a minimum of 20 degrees F subcooling, but that given flexibility above this margin, they would also realize that keeping pressure low would minimize loss of coolant through the break.
Conclusions The was a briefing for information. No specific action was taken at this meeting as a result of this briefing.
V.
ISO Ouality Standards (0 pen)
Note: Mr. D. Houston was the Designated Federal Official for this portion of the meeting.
Introduction Dr. T. Kress introduced the speaker Mr. Rob Cerzosimo who is affiliated with KEMA and is an ACRS consultant.
Dr. Kress indicated that the European nuclear industry has adopted ISO 9000 Standards as contrasted to the ANSI /ASME NQA-1 Standards in the United States. He questioned whether there were any safety implications associated with the adoption of the ISO standards for USA plants or for obtaining parts from European suppliers.
8 Discussion Mr. Cerzosimo discussed the ISO 9000 Standards for quality management and quality assurance that were issued in 1987.
These standards were developed by the International Standards Organization (IS0) to promote harmonization of standards within and outside the European comrranity.
In his presentation, he discussed the following topics:
Historical Background of ISO 9000 - Evolution from military, NASA, FAA, automotive and industrial standards from 1959 to 1987. Listing of ISO 9000 Series Standards.
A Summary Comparison of ISO 9001, 1987 and ANSI /ASME NQA-1, 1989 Standards - A summary and comparison of each requirement and concluding remarks about their differences, if any.
An Overview of the American National Accreditation Program for Registrars of Quality Systems - A listing of U.S. registrars (10) and accreditation (5). Also, an indication of increased registrar activity in the U.S. during 1992 from 68 registrations in March to 116 in July.
A Document Listing of the Current Status of ISO 9000 and 10000 Series Standards - This listing showed existing standards, new standards and work in progress.
Background Information on the European Council Directives and the C5 Mark - The Conformit6 Europ4enne (CE) Mark will indicate that the product complies with the set requirements for safety, health, environment and consumer protection.
In closing, he provided the following conclusion:
1)
The certification of a company's quality system (by an accredited certifying body or " Registrar") cannot, by i tsel f, provide the necessary confidence that a specific item, product or service will, in fact, exhibit the degree of quality required for the specific safety-related application.
In part, this is due to the fact that the evolving mutual recognition schemes have not fully demonstrated the degree of consistency necessary for such safety-related applications.
2)
A company that has established measures for quality and documented adequate and suitable provision, as required by an ISO 9001 and/or 9002 standard (as applicable), for achieving and improving quality may have a quality system that satisfies the intent of the current nuclear regulatory requirements.
3)
Some companies, that will have achieved Certification of their ISO 9000 quality system, will expect to provide items and rervices to the nuclear industry.
9 Conclusions This was a briefing only.
No Ccmittee action was taken at this meeting as a result of this briefing.
VI.
ACRS Subcommittee Activities (0 pen)
Note:
Dr. John Larkins was the Designated Federal Official for this portion of the meeting.
Report of the Materials and Metalluray Subcomittee Meetina Held on March
- 10. 1993 Dr. Shewmon briefed the Comittee on the outcome of the Joint ACRS Subcomittees on Materials and Metallurgy / Structural Engineering meeting of March 10, 1993.
Steam Generator Interim Criteria Dr. Shewmon stated that the staff and industry presented the status of the interim steam generator tube plugging criteria applicable to outside diameter steam generator tube degradation of short and deep cracks at the tube support plant.
For steam generator tube degradation at locations other than the tube support plate the current tube plugging criteria, i.e., plug or sleeve with degradation greater than 40% through wall, still applies.
The interim plugging criteria (good for 1 fuel cycle only) is based on voltage readings during eddy current inspections of steam generator tubes.
The industry has correlated the strength of defective tubes versus 1
voltage. The staff has accepted 1 volt for the interim criteria for some current plants.
The industry stated that the 1 volt limit is too conservative and stated that 3-5 volts would still be justified based on tests and analysis.
It was mentioned that the European's acceptance criteria is significantly higher (by an order of magnitude). The staff is concerned that tight and long axial cracks are difficult to discern using the voltage criteria.
This briefing was for information only. The subcomittee will meet again when the staff final plugging criteria is documented.
ALWR Pinino Desian Criteria Dr. Shewmon noted that at the meeting, the industry presented a briefing on first-of-a-kind engineering on piping design criteria for advanced LWRs. The industry stated that based on recent tests and analyses, it was found that current piping systems are rigid and very robust. In addition, tests indicate that the current ASME Code failure criteria are incorrect and should be corrected. Based on the industry proposed piping criteria, redesigned piping systems should be more flexible and have less supoorts, restraints and snubbers. These improvements should reduce piping loads; be easier to inspect and fabricate; and reduce overall cost. The industry
10 stated that they are working with the ASME Code Committees (in which the staff is represented) to modify existing codes to reflect current knowledge.
This briefing was for information only.
Report of Thermal Hydraulic (T/H) Phenomena Subcommit. tee Meetino. March 4-
- 5. 1993 - Idaho Falls. Idaho Dr. Catton, T/H Phenomena Subcommittee Chairman, reported on the subject meeting. The meeting was held to discuss the status of the PWR version of the RELAP5/M003 (R/5) code, sponsored by the Office of Research.
The emphasis of the discussions was on the use of R/5 to support RES's confirmatory research programs associated with NRR's certification review for the Westinghouse AP600 passive plant design.
Key points noted by Dr. Catton in his report to the Committee included the following:
The meeting was productive. RES and the Contractor (INEL) provided good support.
Dr. Catton attributed this to the presence of Dr.
Sheron.
R/5 is now the NRC's code of choice for use in supporting NRR's
=
review of both the Westinghouse AP600 and the General Electric SBWR passive plant designs.
The decision to use R/5 for these tasks is believed to have been made by NRR.
As R/5 is a one-dimensional code, there will be difficulties encountered in modeling the important multi-dimensional phenomena seen in both passive designs.
RES is using the code scaling, applicability, and uncertainty (CSAU) methodology as a guide to making the necessary modifications to R/5 in order to support the AP600 modeling effort.
Mode',ing transients in the passive plants will strongly challenge
=
the code, as these events must be tracked for as long as 2-3 days, and the T/H interactions between the RCS and containment are strongly coupled.
To this end, RES plans to marry the R/5 and CONTAIN codes.
The Subcommittee will need to investigate the coupling of these codes.
The modeling capability of R/5 is weak regarding the T/H phenomena associated with small break LOCA events. This is due to the failure of RES during the 1970s to support strong development of the correlations associated with two-fluid modeling capability.
Mr. Davis said he was surprised to discover that the so-called
" passive" plant designs, e.g., AP600, required more complex modeling i
than that of the current reactor designs. He felt that this was a dichotomy, given that the passive designs are supposed to be " safer" than current plant designs.
Dr. Catton observed that one needs to incorporate quasi-steady state modelling capability into R/5 in
-1 11 order to properly simulate the 'T/H phenomena seen.in the passive plant designs.
During Committee discussion, Dr. Shewmon asked if Westinghouse's codes are in any better shape than is R/5.
Dr. Catton indicated that one of the objectives of the Idaho Falls meeting was to identify topics / issues'for discussion with Westinghouse on the status of their analytical program for discussion at a future Subcommittee meeting.
In conclusion, Dr. Catton said that each of the Subcommittee consultants is to prepare a report that identifies specific problems / concerns with i
R/5, both as identified during the subject meeting and as a result of a review of the Code's "Models and Correlations" document.
Following compilation of the issues provided by the consultants and their transmittal to RES, another meeting of the T/H Phenomena Subcommittee will then be held to discuss the disposition of these items.
)
Reoort of ACRS Plannino and Procedures Subcommittee Meetino on March 10.
1911 The draft minutes of the March 10, 1993 Planning and Procedures Subcommittee meeting were discussed. There was general agreement with the t
minutes of that meeting.
Specific Comments regarding new members are discussed in a special " Internal Use Only Supplement."
VII.
Future ACRS Activities (0 pen)
Note:
Dr. Richard Savio was the Designated Federal Official for this portion of the meeting.
s The following activities were scheduled for the 396th ACRS Meeting, April 15-17, 1993, Bethesda, MD:
Proposed NRC Staff Plan for Comparina Safety Goals with Reculations (Tentative) - The Comittee will review and comment on the NRC staff plan for using the Safety Goal Policy to judge the effectiveness of the NRC regulations. Representatives of the NRC staff and industry will participate.
The SALP Procram - The Committee will review and comment on the overall SALP process and the changes made or proposed since the Regulatory Impact Survey that was conducted in 1989.
Representatives of the industry and NRC staff will participate.
Commission Paner on Safety Goals /Laroe Release - The Committee will review and comment on a revised Commission paper on the definition of a large release within the context of the implementation of the Safety Goal Policy.
Representatives of the NRC staff will participate.
Maintenance Guidance Documents - The Committee will review and
=
comment on the guidance documents for Implementation of the Maintenance Rule.
Representatives of the NRC staff and industry will participate.
12 Current license Renewal Issues - The Comittee will discuss and coment on how the Maintenance Rule might be used as a means to address the activities regired of licensees by the License Renewal Rule.
Representatives of the industry and NRC staff will partici-pate.
Procosed Final Comission Paper on Resolved SECY-90-016 Follow-on Issues - The Comittee will review and coment on the status of the NRC staff's work on resolution of SECY-90-016 follow-on issues.
Representatives of the NRC staff will participate.
Reculatory Guide for Imolementation of Revised 10 CFR Part 20 - The Comittee will discuss and comment on the proposed final regulatory guide, DG-8006, " Control of Access to High and Very High Radiation Areas in Nuclear Power Plants." Representatives of the NRC staff will participate, as appropriate.
Prioritization of Generic Issue 152. "Desion Basis for Valves that Micht be Sub.iected to Sionificant Blowdown loads" - The Comittee will discuss proposed ACRS report on the proposed priority ranking of this generic issue.
Representatives of the NRC staff will participate, as appropriate.
Oroanizational Factors Research - The Comittee will discuss proposed ACRS report on the Organizational Factors Research Program.
Representatives of the NRC staff and industry will participate, as appropriate.
Effects of Hurricane Andrew on the Turkey Point Plant - The NRC staff will brief the Committee on the effects of Hurricane Andrew on the Turkey Point Nuclear Plant.
Representatives of the industry will participate, as appropriate.
Meetino with the Director of th_g Office of Policy Plannino (Tenta-tive) - Meet with the Director of the Office of Policy Planning to discuss matters of mutual interest.
Future ACRS Activities - The Comittee will discuss topics proposed for consideration by the full Comittee.
Resolution of ACRS Recomendations - The Comittee will discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS coments and recomendations.
ACRS Subcommittee Activities - The Comittee will hear reports on and hold discussions of the status of ACRS subcomittee assignments, including activities of the NRC Region II Office, Severe Accident issues for the GE ABWR, ABB-CE System 80+ control room mockup, and procedures for the conduct of ACRS business. Representatives of the NRC staff will participate, as appropriate.
Aooointment of ACRS Members - The Comittee will discuss qual-ifications of candidates proposed for appointment as ACRS members.
Portions of this session will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.
Hiscellaneous - The Comittee will discuss miscellaneous matters l
related to the conduct of Comittee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.
i
i 13 VIII. Uoarade of Conference Room (0 pen)
Note:
Dr. John Larkins was the Designated Federal Official for this portion of the meeting.
A representative of the NRC's Office of Consolidation made a presentation covering the design concept, furniture and furnishings for the ACRS meeting room and subcommittee rooms.
Mr. Schofer demonstrated the use of the XY Index, that is available for use at this time on the Network.
The Index has all of the ACRS letters that have been issued since 1985. He demonstrated the word / phrase search capability of the presently available XY Index program.
IX.
Reconciliation of ACRS Comments and Recommendations (0 pen)
Note:
Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.
The Executive Director for Operations' (ED0's) responses to previous ACRS reports were discussed as follows:
ED0 letter, dated February 24, 1993, responding to the ACRS report dated December 17, 1992, "NRC Response to the Petition Submitted by Richard Grill for Rulemaking on Electrical transients, PRM-50-56."
The EDO letter did address the Committee's comments.
ED0 letter, dated February 19, 1993, responding to the ACRS report dated November 12,1992, " Revised Regulatory Analysis Guid:'ir.sr."
The EDO letter did address the Committee's comments.
ED0 letter, dated February 11, 1993, responding to the ACRS report dated January 13, 1993, concerning Proposed Resolution of Generic Safety Issue 120, "On-Line Testability of Protection Systems."
The EDO letter did address the Committee's comments.
X.
Accointment of New Members (Closed)
Note:
Dr. John Larkins was the Designated Federal Official for this portion of the meeting.
The Committee intends to send a slate of nominees to the Commission to fill the vacancy that will be created when Dr. Shewmon retires.
This slate is expected to be sent following the April or the May 1993 meeting.
This portion of the meeting is reported in a special closed meeting supplement, which is attached.
- Q 1
14 XI.
Miscellaneous (0 pen)
)
Note:
Dr. John Larkins was the Designated Federal Official for this portion of the meeting.
Generic letter on Emeroency Response Data System Test Proaram The Committee directed Dr. Larkins to ~ send a memorandum to James M.
Taylor, Executive Director for Operations, as noted in Section XIII of these minutes, indicating that the Committee decided not to review the propa cd generic letter.
Prooosed NRC Generic letter "Line-Item Technical Soecification Imorovements to Reduce Surveillance Reauirements for Testino Durina Power Ooeration" The Committee directed Dr. Larkins to send a memorandum to Gail H. Marcus, Chief of the Generic Communications Branch, as noted in Section XIII of these minutes, indicating that the Committee decided not'to review the
~
proposed generic letter.
S Revision of ACRS Subcommittee Assianments The members were given a revised list of proposed subcommittee assignments.
The members will provide their comments on the proposed assignments to Mr. Duraiswamy before the April 1993 ACRS meeting.
Lack of individual members comments will suggest the members agreement with their assignments.
XII.
Summary / List of Follow-uo Matters Bill Russell offered to provide the Committee a list of plants with regard to the applicability of the staff's D0R Guidelines for license renewal. (Mr. Igne has the followup on this matter)
Dr. Lewis asked that the ACRS staff find the possible implications on the ACRS of the court order that certain sections of the Federal Advisory Committee Act (FACA) to certain meetings of the President's -
Task Force on National Health Care Reform is unconstitutional. (Dr.
Larkins has the followup on this matter)
The Committee agreed that October 11-15, 1993 would be an acceptable date for the Multilateral Meeting of Advisory Committees in France.
The ACRS staff should notify the GRS/RSK of the acceptability of this date so that planning for the meeting can continue.
(Mr.
Quittschreiber has the follow-up on this matter.)
The ACRS Vice Chairman and the ACRS staff should set up a training j
program for Russian specialists attending a one day session at the ACRS office on June 3,1993 on the functions of the ACRS.
(Mr.
Quittschreiber has the followup on this matter.)
4 15 Dr. Seale asked the representatives of the Department of Energy to provide a copy of the comparison between the advanced reactor policy statements in SECY-88-203, dated July 15, 1988 and the draft policy statements, dated December 16, 1992.
Note:
Mr. C. L. Reid, DOE, provided a copy of this comparison on February 18, 1993.
XIII. Executive Session (0 pen)
Note: Dr. Larkins was the Designated Federal Official for this portion of the meeting.
During its 395th meeting, March 11-13, 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memorandums as noted.
Rgoorts Comouters in Nuclear Power Plant Ooerations (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 18, 1993)
Advanced Boilina Water Reactor (ABWR) Review Schedule (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 18,1993)
Human Performance in Ooeratina Events (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated March 19, 1993)
Memorandums Generic letter on Emeroency Response Data System Test Proaram (Memorandum to James M. Taylor, Executive Director for Operations, from John T. Larkins, Executive Director of the ACRS, dated March 17,1993.)
Proposed NRC Generic letter "Line-Item Technical Soecification Imorovements to Reduce Surveillance Reauirements for Testina Durina Power Ooeration" (Memorandum to Gail.H.
Marcus, Chief of the Generic Communications Branch in the Division of Operating Reactor Support Office, from John T. Larkins, Executive Director of the ACRS, dated March 17,1993.)
Meeting was adjourned at 6:00 pm on March 12, 1993
o,.
i 4
APPENDICES MINUTES OF THE 395TH ACRS MEETIEG MARCH _11-13, 1993 I.
Attendees II.
Future Agenda III.
Future Subcomittee Activities IV.
List of Documents Provided to the Comittee
H o
APPENDIX I MINUTES.0F THE 395TH ACRS MEETING MARCH 11-13 March 11. 1993 I
Public Attendees NRC Attendees' 1
J. H. Taylor, B&W Nuclear Technologies Mark Lesser, EDO l
C. K. Lewe,'NUS Jef Vora, RES John Osborne, Baltimore Gas & Electric Co.
George.Sege, RES l
John Rycyna, Baltimore Gas & Electric Co.
John Cuceig, RES Mark Beaumont, Westinghouse William Travers, NRR.
Lynn Connor, STS Steven A. Reynolds, NRR a
L. E. Steele, Consultant W. T. Russell,~NRR Roger Huston, TVA D. Nash, OPP L. J. Toth, Gasser Associates R. Nease, NRR Deborah Staudinger,' B&W Owner's Group T. Hiltz, NRR Kevin Graney, SERCH Licensing - Bechtel F. Akstulewicz, NRR J. Alan Beard, GE S. Hoffman, NRR R. Clark Evans, NUMARC Scott Newberry, NRR:
H. M. Fontecilla, VA Power Sun Ninh, NRR T. L. Patterson, OPPD Helen Pastis, NRR G. E. Guiliani, OPPD William Huffman, AE0D M. T. Frans, OPPD
~ Dave Trimble, OCM Chuck Nitrone, NRR Ron Parkhill, NRR J. Scarborough, GCM i
J. Moulton,.PDLR R. Anand, PDLR J. Sharkey, NRR l
T. Foley, NRR B. Boger, NRR J. Wermiel, NRR C. Antonesa, NRC J. Kramer, RES M. Fleishman, OCM R. Gallo, DRCH Jim Stewart, DRCH Bill Besch, RIV Ed Goodwin, NRR i
Frank Cherny, RES Craig Hrabal, RES John Kauffman, AEOD t
Mary S. Wagner, AEOD-A. T. Howell, R IV Chris Skinner, R IV 1
F. J. Zarzuela, NRR P. Harrell, R IV B. Grimes, DORS George Hubbard, PD-IV-1 Steven Bloom, PD-IV-1 Chu-Yu Liang, DSSA
a 4
Minutes of 395th ACRS Meeting, Appendix I I-2 Attendees March 11. 1993 NRC Attendees C.
G. Hammer, DE J.
E. Rosenthal, AEOD G.
Lanik, AEOD J.
Gutter, AEOD John MacKinnon, AEOD Owen Gormley, RES Robert Gramm, NRR Jack Heltemes, RES Gary Zech, NRR P
t
4 r
APPENDIX I MINUTES OF THE 395TH ACRS MEETING MARCH 11-13 l
March 12. 1993 Public Attendees NRC Attendees Vin San Angelo, Bechtel Norm Lauben, RES Chery Lewe, NUS Arthur Busiik, RES Mark Beaumont, Westinghouse Joel Kramer, RES H. Pastis, NRR M. Taylor, OEDO 3
l APPENDIX II MINUTES OF THE 395TH ACRS MEETING MARCH 11-12, 1993 FUTURE AGENDA 396th ACRS Meetina, April 15-17, 1993, 7920 Norfolk Avenue, Bethesda.- MD, Room P-110.
During this meeting, the Committee plans to consider the following:
A.
Proposed NRC Staff Plan for Comparina Safety Goals with Reaulations -
Review and comment on the NRC staff plan for using the Safety Goal Policy to judge the effectiveness of the NRC regulations. Representatives of the NRC staff and industry will participate.
[ Note:
This item has been deferred to the May 1993 ACRS meeting.]
B.
SALP Proaram - Review and comment on the overall SALP process and the changes made or proposed since the Regulatory Impact Survey that was conducted in 1989.
Representatives of the industry and NRC staff will participate.
C.
Commission Paper on Safety Goals /Larae Release - Review and comment on a revised Commission paper on the definition of a large release within the context of the implementation of the Safety Goal Policy. Representatives of the NRC staff will participate.
D.
Maintenance Guidance Documents Review and comment on the guidance documents for Implementation of the Maintenance Rule. Representatives of the NRC staff and industry will participate.
E.
Current License Renewal Issues - Discuss and comment on how the Mainte-nance Rule might be used as a means to address the activities required of licensees by the License Renewal Rule.
Representatives of the industry and NRC staff will participate.
F.
Proposed Final Commission Pacer on Resolved SECY-90-016 Follow-on Issues -
Review and comment on the status of the NRC staff's work on resolution of SECY-90-016 follow-on issues.
Representatives of the NRC staff will participate.
G.
Reaulatory Guide for Implementation of Revised 10 CFR Part 20 - Discuss and comment on the proposed final regulatory guide, DG-8006, " Control of Access to High and Very High Radiation Areas in Nuclear Power Plants."
Representatives of the NRC staff will participate.
11.
Prioritization of Generic Issue 152. "Desian Basis for Valves that Miaht be Subiected to Sianificant Blowdown loads" - Discuss proposed ACRS report on the proposed priority ranking of this generic issue.
Representatives of the NRC staff will participate, as appropriate.
I.
Oraanizational Factors Research - Discuss proposed ACRS report on the Organizational Factors Research Program. Representatives of the NRC staff and industry will participate, as appropriate.
J.
Effects of Hurricane Andrew on the Turkey Point Plant - Hear a briefing by and hold discussions with representatives of the NRC staff regarding the effects of Hurricane Andrew on the Turkey Point Nuclear Plant. Represen-tatives of the industry will participate.
K.
Meetina with the NRC Commissioners (Tentative)
Meet with the NRC Commissioners to discuss items of mutual interest.
[ Note: This item has been deferred to the May 1993 ACRS meeting.]
L.
Meetina with the Director of the Office of Policy Plannina - Meet with the Director of the Office of Policy Planning to discuss matters of mutual 1
interest.
1 1
- ,. a 1
/
2 Appendix II H.
Future ACRS Activities - Discuss topics proposed for consideration by the full Committee.
N.
Resolution of ACRS Recommendations - Discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS comments and recommendations.
O.
ACRS Subcommittee Activities - Hear reports on and hold discussions of the status of ACRS subcommittee assignments, including activities of the NRC Region 11 Office, Severe Accident issues for the GE ABWR, ABB-CE System 80+ control room mock-up, multi-dimensional plant configuration management system, and procedures for the conduct of ACRS business. Representatives of the NRC staff will participate, as appropriate.
- P.
Apoointment of ACRS Members - Discuss qualifications of candidates proposed for appointment as ACRS members.
Portions of this session will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.
Q.
Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.
- Closed
.a l
l APPENDIX III MINUTES OF THE 395TH ACRS MEETING MARCH 11-12, 1993 FUTURE SUBCOMMITTEE ACTIVITIES Advanced Pressurized Water Reactors, April 13, 1993, Windsor. Connecticut (Igne).
The Subcommittee members will visit the ABB-CE facility at Windsor, Connecticut.
to observe the System 80+ control room mock-up. Attendance by the following is anticipated, and reservations have been made at the COMFORT INN-AIRPORT (203/627-6585),260 Main Street, East Windsor, CT for the nights of April 12 and 13:
Catton (tent)
Shewmon Davis Wylie Seale Plannina and Procedures, April 14, 1993, 7920 Norfolk Avenue, Bethesda. MD (Larkins), 3:00 p.m. - 5:30 p.m.,
Room P-422.
The Subcommittee will discuss
, proposed ACRS activities and related matters.
Qualifications of candidates t 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 r
the following is anticipated, and reservations have been made at the hotels as l
inditated for the night of April 13:
Shewmon NONE Carroll H0LIDAY INN Wilkins HOLIDAY INN Probabilistic Risk Assessment, May 11, 1993, 7920 Norfolk Avenue, Bethesda MD (Houston), 8:30 a.m.,
Room P-110.
The Subcommittee will discuss the report of the PRA Working Group that summarizes activities of this Group and provides guidance for the staff regarding the application of PRA.
Lodging will be an-nounced later.
Attendance by the following is anticipated:
Lewis Wilkins Kress Kerr Michelson Okrent Seale Ward Joint Thermal Hydraulic Phenomena / Core Performance, May 12, 1993, 7920 Norfolk Avenue, Bethesda, MD (Boehnert), 8:30 a.m., Room P-110. The Subcommittees will continue their review of the issues pertaining to BWR core power stability.
Lodging will be announced later. Attendance by the following is anticipated:
Catton Dhir Wilkins Kerr Davis Lee iKress Lipinski
'Seale Zuber Shewmon u
2 i
Plannina and Procedures, May 12, 1993, 7920 Norfolk Avenue, Bethesda. MD (Larkins), 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.
Attendatice by the following is anticipated:
Shewmon Carroll Wilkins 397th ACRS Meetina, May 13-15, 1993, 7920 Norfolk Avenue, Bethesda. MD, Room P-110. Agenda to be announced.
Plannina and Procedures, June 9,
1993, 7920 Norfolk Avenue, Bethesda. MD (Larkins), 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:
Wilkins Carroll Member-at-large 398th ACRS Meetina, June 10-12, 1993, 7920 Norfolk Avenue, Bethesda MD, Room P-110. Agenda to be announced.
Probabilistic Risk Assessment (tentative) Date to be determined (April /May),
Bethesda. MD (Houston).
The Subcommittee will discuss a proposed regulatory guide on the use of PRA in design certification and other applications of PRA in j the regulatory process.
Attendance by the following is anticipated:
Lewis Seale Davi; Wilkins Kress Consultants - TBD Mic$elson
'e ',
3 Safety Philosophy. Technoloov and Criteria (tentative), Date to be. determined (April /May), Bethesda. MD (Houston).
plan for comparing safety goals with regulations.The Subcommittee will discuss a prop Attendance by the following is anticipated:
Kress wylje Davis Kerr Lewis Ward Michelson Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (April /May),Bethesda,MD(Houston). The Subcommittees will begin their review of the staff's proposed technical positions on severe accident issues for future plant designs.
The topics of fuel-coolant interactions and hydrogen will also be discussed.
Attendance by the following is anticipated:
Kress Shewmon Catton Dhir Davis Kerr Lindblad Lee Nichelson Ward Seale Individual Plant Examinations (tentative), Date to be determined (May/ June),
Bethesda MD (Houston).
The Subcommittee will discuss the status and insights gained in regard to the Individual Plant Examination Program. Attendance by the following is anticipated:
Davis Michelson Catton Seale Kress Kerr Lindblad Ward Decay Heat Removal. Systems, Date to be determined, Bethesda, MD (Boehnert). The Subcommittee will continue its review of the NRC staff's proposed final resolution of Generic Safety Issue 23, " Reactor Coolant Pump Seal Failures."
Attendance by the following is anticipated:
Catton Michelson Davis Wylie Lindblad Ward l
I
vi Q
4 Thermal Hydraulic Phenomena, Date to be determined, Bethesda, MD (Boehnert). The Subcpmmittee will begin its review of the Westinghouse analytical program used in shpport of the AP600 design certification test program.
Attendance by the folfowing is anticipated:
Catton Dhir Davis Schrock Kress Ward Seale Wul ff Wilkins Zuber Thermal Hydraulic Phenomena, Date to be determined, Oreaon State University (OSU). Corvallis OR (Boehnert).
The Subcommittee will continue its review of the Westinghouse and NRC integral systems and separate effec
- test programs supporting the AP600 design certification effort.
The meeting ulscussion will focus on the OSU integral systems test facility. Attendance by the following is anticipated:
Catton Dhir Davis Kerr Kress Schrock Lindblad Ward Seale Wulff Wilkins Zuber Thermal Hydraulic Phenomena, Date to be determined (2-day meeting), San Jose, CA (Boehnert). The Subcommittee will continue its review of both the GE analytical program (TRACG code) and the experimental program supporting the certification effort for the Simplified Boiling Water Reactor design.
Attendance by the following is anticipated:
Catton Dhir Davis Kerr Kress Ward Seale Wul ff Wilkins Zuber Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (Fall),
Bethesda. MD (Houston).
The Subcommittees will continue their review of the staff's proposed technical positions on severe accident issues for future plant designs. The topics of basemat penetration and direct containment heating will also be discussed. Attendance by the following is anticipated:
Kress Shewmon rCatton Dhir Davis Kerr Lindblad Lee Michelson Ward Sealk
v e
s q
,e APPENDIX IV MINUTES OF'THE 395TH ACRS MEETING i
MARCH 11-13, 1993 LIST OF DOCUMENTS RECEIVED BY THE' COMMITTEE INote:
Some of the materials listed may have been crovided for ACRS Internal l
Committee Use Oniv or maY contain Proprietary Information1 MEETING NOTEBOOK TAB NO.
2 Current License Renewal Issues 1.
Tentative Schedule 2.
Status Report 3.
Letter for James Taylor from David Ward, dated August 17,.1992, re:
Proposed Regulatory Guide and Interim. Standard Review Plan for License Renewal and a Related Branch Technical Position on Fatigue Evaluation Procedures 4.
Letter for James Taylor from David Ward, dated October 15, 1992, re:
Proposed Guidance for Implementation of the Maintenance Rule,10 CFR 50.65 5.
SECY-93-049, " Implementation of 10 CFR Part 54, Requirements for Renewal of Operating Licenses of 10 CFR Part 54," dated MarchL 1, i
1993 6.
Integrated Plant Assessment 4
Proposed ACRS Reports 7.
Tentative Schedule Status Report 8.
Letter for Kenneth Carr from Carlyle Michelson, dated August 16, 1990, re: NRC Research on Organizational Factors 9.
Excerpt-from Paul Boehnert Project Status Report on Topics for the 394th ACRS Meeting 10.
SECY-92-020, Review of Organizational Factors Research, February 1, 1993
+
11.
Memorandum for Franklin Coffman from Gary Zech, dated September 18, 1992, re: Input on Commission SRM on Research in Organizational and Management Area
- 12., slides for most recent SALP Ratings 13.
SECY-92-407, The Independent Role of the Office for Analysis and Evaluation of Operational Data in the Assessment of Operational Experience and the Investigation of Operational Events 14.
Letter for Paul Shewmon from Kenneth Rogers, dated February 17, 1993, re: ACRS's Views on Organizational Factors Research 15.
Note to Jay Carroll from Dave Ward, dated February 12, 1993, re:
Comments on Draft Letter 5
Reactor Operatino Experience 16.
Agenda 17.
Project Status Report 18.
NRC Information Notice 93-02, re: Malfunction of a Pressurizer Code Safety Valve, dated January 4, 1993 19.
Letter for W. G. Gates from James Milhoan, dated August 6,1992, re:
NRC Inspection Report 50-285/92-18 20.
Memorandum for Phillip Harrell fram James Milhoan, dated July 4, 1992, re: Augmented Inspection Team at Fort Calhoun Station
, e 4
21.
Attachment B, Disposition of the Internal Parts of Pressurizer Code Safety Valve RC-142, [with attachments]
22.
Letter for W. G. Gates, OPPD, from James Milhoan, dated July 4, 1992, re: Confirmatory Action Letter 23.
Letter for W. G. Gates from James Milhoan, dated July 8,1992, re:
Revision to July 4,
- 1992, Confirmatory Action Letter, with attachments E, F, and G 6
ISO Guality Standards 24.
Tentative Schedule 25.
Status Report 26.
Attachments:
An Article " Vision 2000, a Strategy for International Standards Implementation in the Quality Arena during the 1990s," by the Task Force that prepared the ISO 9000 Series Documents 27.
Memorandum for G. C. Millman, et al., from 0. P. Gormley, dated March 1, 1993, re: ASQC Conference / ISO 9000 Training.
MEETING HAND 0UTS AGENDA ITEMS 3
Computer Issues 28.
Letter for Drs. Lewis, Kress, and Wilkins from Chairman Selin, dated February 23, 1993, re: Response to December 11, 1992, letter commented on the staff's regulatory program plan for digital instrumentation and control systems in nuclear plants
[with enclosure]
29.
Letter for Paul Shewmon from James Taylor, dated December 10, 1992, re:
Response
to Environmental Qualification for Digital Instrumentation and Control Systems [with enclosure]
30.
Letter for David Ward from James Taylor, dated October 23, 1992, re:
Defense against Common Mode Failures in Digital Instrumentation and Control Systems [with enclosure]
31.
Letter for David Ward from James Taylor, dated October 22, 1992, re:
Response to September 16, 1992, draft Comission paper " Design Certification and Licensing Policy Issues pertaining to Passive and Evolutionary Advanced Light Water Reactor Designs" [with enclosures]
32.
Memorandum for William T. Russell and Clemens J. Heltemes from Dennis Crutchfield, dated February 18, 1993, re: Final Concurrence Review of the Comission Paper " Policy Technical and Licensing Issues Pertaining to Evolutionary and Advanced ight Water Reactor Designs" (with enclosures]
4.0 33.
Letter for Herman Alderman from Tom Leamon, dated March 5,1993, re:
Comments by ACRS Consultants on Organizational Factors Letter 34.
Memorandum for Jay Carroll from Dave Ward, dated March 10, 1993, re:
Coments on March 2,1993 draft of 0FR letter 5
35.
INP0 SER 18-92, Fort Calhoun Stuck Open Safety Valve Event 7
36.
Memorandum for ACRS Members from Stewart Long, dated March 11, 1993, re: Some Comments on Achieving and Certifying Software Safety for Nuclear Power Plants 37.
Letter for Terry Dailey from Patrick R.H. Place, dated February 18, 1993, re: Report on February 9th meeting of the ACRS Computer Subcommittee 8
38.
Memorandum for Carlyle Michelson from Elpidio Igne, dated March 11, 1993, re: Background Information for Review Schedule for the ABWR
[with attachments]
+\\ o 1
8.3 39.
Memorandum for ACRS Members from P. Boehnert, dated March II,1993, re: Thermal Hydraulic Phenomena Subconnittee Meeting, March 4-5, 1993, Idaho Falls, Idaho - Subcommittee Chairman's Report 8.3 40.
Letter for Ivan Catton from Pete Davis, dated March 9,1993, re:
Comments from Thermal Hydraulic Subcommittee Meeting in Idaho Falls, March 4-5, 1993 10 41.
Memorandum for John Larkins from Warren Minners, dated March 11, 1993, re: ACRS Review of Draft Commission Paper on large Release Determination [with enclosures draft copy attached for Internal use only]
10.1 42.
Memorandum for ACRS Members from R. P. Savio, dated March 12, 1993, re: Future ACRS Activities - 396th Meeting April 14-17, 1993, with' attachment Future Agenda Items 43.
Letter for James Taylor from David Ward, dated May 14, 1992, re:
Advance Notice of Proposed Rulemaking on Severe Accident Plant Performance Criteria for Future LWRs [with enclosure]
HANDOUTS OTHER THAN ACRS 44.
Presentation for ACRS Digital Instrumentation and Control Systems, March 11, 1993, by William T. Russell, NRR 45.
License Renewal, by W. Russell, W. Travers March 11, 1993 I
1