ML20236T661
| ML20236T661 | |
| Person / Time | |
|---|---|
| Issue date: | 09/12/1987 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2524, NUDOCS 8712010436 | |
| Download: ML20236T661 (60) | |
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l TABLE OF CONTENTS MINUTES OF THE 329TH ACRS MEETI SEPTEMBER 10-12, 1987
[ON N Wl l
WASHINGTON, D.C.
l Page I.
C h a i nna n ' s Re p o rt ( 0 pe n )........................................
1 II. ECCS-Revi si on of 10 CFR 50.46 (0 pen )............................
1 III. Emergency Planning (0 pen)........................................
5 IV. Auxiliary Feedwater System Reliability (0 pen)....................
6 i
1 Y.
Meeting with the Director of the Office of Nuclear Reactor i
Regulation (0 pen)................................................
8 VI. Nucl ea r Waste Di sposal (0 pen)....................................
9 VII. Pipe Wall Thinning at the Trojan Nuclear Station (0 pen)..........
14 VIII. ExecutiveSessions(0 pen / Closed).................................
16 A.
Subcommittee Reports (0 pen /Cl osed)...........................
16 1.
Advanced Reactor Designs (0 pen).........................
16 2.
New M emb e rs ( Cl o se d ).....................,..............
17 3.
Fu tu re LWR De s i g ns (0pe n)...............................
18 4.
Spent Fuel Storage (0 pen)...............................
19 5.
Regional Programs (0 pen)....................'............
20 j
6.
SouthTexasUnits1and2(0 pen)........................
20 I
7.
ReactorOperations(0 pen)...............................
21 l
l 8.
InternationalQualityAssurance(QA) Workshop (0 pen)....
22 j
l 9.
Ad Hoc Plannin Subcommittee on Advice on Nuclear WasteMattersfC1osed)..................................
23
)
l 10.
Ad Hoc Meeting with the ENEA's Technical Comittee (C1osed)................................................
24 j
l gsicsMD 0*
8712010436 871125 PDR ACRS Cortified B7 -
2524 PDR
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w
r x
a 11-i f
B.
Reports, Letters and Memoranda (0 pen)............................
-24 1.
ACRS Comments on Code Scaling, Applicability and.
Uncertainty (CSAU) Methodology for Determination of Uncertainty Associated with the Use of Realistic Evaluation Models............................................:24-2.
ACRSCommentsonDevelopmentsinEmergencyPlannincj.......... 24 j
3.
ACRS Comments Regarding Proposed International Workshop on i
Quality in Design and Construction of Nuclear Power Plants.. 24 4.
ACRS Action on the Proposed Final Rule Amendments tc 4
'10 CFR Part 72, " Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level.
Rad i oa cti ve Wa s te"..........................................
24 --
l 5
ACRS Coments on Igroved Safety for Future Light Water Reactors....................................,...............
25 C.
Other Comittee Conclusions (Okn) 1.
Steam Generator Tube Ruptures...............................
25 2.
Basdekas' Concerns..........................................
25 3.
Reorgan.ization of Nu, clear Industry Activities...............
25 4.
Imp rove d S a fe ty Featu res....................................
25 I
5.
Reactor Vendors.............................................
26 j
1 6.
Scope of PRAs for CE P1 ants.................................
26 I
7.
Post Accident Releases......................................
26 l
J 8.
Schedule of Meeting Dates for CY 1988..................,....
26*
l i
9.
Nominating Panel for ACRS Officers for CY 1988..............
26 D.
FutureActivities(Cpen).........................................
26 1.
F u tu re A ge n d a................................................ 2 6 1
2.
Future Subcommittee Activities..............................
27 i
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APPENDICES TO MINUTES OF THE 329TH'ACRS MEETING SEPTEMBER 10-12, 1987 l
WASHINGTON, D.C.
i 1
I.
List of Attendees.
II.
Schedule of Meeting Dates for CY 1988 III.
Future Agenda IV.
Future Subcommittee Activities V.
Other Documents Received I
i i
i 9
e d
_____._____m.____.._
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'k Fed:r:1 Registir / Vol. 52. No.168 / Maday. August 31,.1987 /.Nelloss' l
Fe,r further details with respect to this Friday. Septmober.12.2ss7 21mAM-J2mNoentACAS y
..a.
c.ction, see 0) the application for
- Subcomm/mee ActivitlaaIQpenT J.,
9 i
amendmeni dated March 31.1986 and dNAM A
(
(2) the Commisskn's letter to Georgia P/aning (Open)-Osca pmpmed Closed)-Haar and <liscuss inipons af m
i designated ACRS adbcommillees Te.
l Power Company dated August 25.1987 ACRS recommendadons regarding planni provisions in
.regarding safety related and rggulalogy l,..
I which are avaliable for public
'"'#8'"7nu im flitin.
mattersincluding actMties ofMRC,. a inspection at the Commission's Public vicinity o regionst uffices; and foregn regulatory.,y Docurnent Room.1717 H Street. NW"
- A#~###A##
""8'"
Policies and practices.
.. a: ~.
Washington DC, and at the Appli A#ocahon o/AmmafoNW Portions elthis seaska willbdoma AdVIC' *" NUC/"f #8888 ACfl"i l'8 County Public 1.lbrary 301 City Ha as necessary to discussinformailon.. t nfte$athe lorinte Provided in confidence by a foreign. '
I Drive. Baxley, Georgia 31513. A copy of 1 a ocation of.
c$ ear Tvke'te$nic 1 ad p
I the M.,2 W Ra N M nd~.
e sed to e Regulatory Canmission. Washington'n
- regulati n fn leerweste.
ACRSReports to the NRC(Openf DC 20555. Attention: Director' Divislo Clesed)-Discuss proposed reports to This session will be closed 6 discuss cf Resetor Projects 1/11.
the NRC regarding items considered the internal personnelrules and dudag this meedng D:ted at Betheode. Maryisad. this 25th day practices of NRC and to discuss Pordons of this weida may be cleend cf Augv111967 information the release of which would as required to discuss information 1
For the Nuclear Regulatory Commission.
represent a clearly unwarran(ed
- Dart f Hood, invasion of personalprivacy.
provided in confidence by a foreign A cting DimctorPmject Dimctomte 11,31, 112A.M.-12MNoon:Futm ACRS I
source.
g g g y,.,ga p g ;yj,a,nanaoa, Division o/ReactorProjects.1//1.
Activities (Open)-Discuss anticipated (Open).4emplete discussion of liens (FR Doc. 8M9s50 Filen-28 87: 8:45 am)
ACRS subcommittee actidties and items considered during this meeting..
proposed for consideration by the full
. Procedures for the conduct of and Committee.
participation la ACRS meetings avere am PR-22 PM:Ssorage ofSpear publishedin the Feders! Register os Advisory Committee on Reactor NuclearPower Plant Puel(Open) -
October 30.1936 (51 FR 87341).3n -
1 Safeguarda; Meeting Agenda Consider proposed changes to la CFR scoordance with these procedures. oral i
Part 72.1.icensms Requirements for the or written statements may be presented I
in accordance with the purposes of Storage of Spent Fuelin anIndependent by mernbere of the public. recordings esctions 29 and 182b. of the /.lomic S ent Fuel Storage Installation (ISFSI)
P Energy Act (42 U.S.C. 2039,2232b), the to define regulatory requirements for a willbe permitted only during those portions of the meeting when a Advisory Committee on Reactor monitored retrievable storage facility transcript is beit:g kept and guestions -
Safeguards willhold a meeting on (MRS) for spent nuclear power plant may be.esked only by members of the fu~ l.
September 10-12.1987, in Room 1046.
e Cominittee, its consultants, and Staff.
1717 H Street. NW., Washington, DC.
MPM4 WPM: Tro/anNuclear Penons desiring tomake oral Notice of this meeting was published in~ ' PowerPlant (Open}.-8riefing regardin8 statenents should notify the ACRS the Federal Register on August 17.1987.
excessive pipe thinningin the main Executive Director as far in advance as
'Ibursday. September 20.1987 h.
5
.M. Se/ sin /c 3
a m
ca m e allow the BMA.M.-a:45 AM:ReportofACRS Qualification of Equipment (Open}--
necessary time during the meeting for Chairman (Open}-The ACRS Chairman Briefing regarding results of seismic such statements. Use of still, motion will report briefly regarding items of walk-through of the Zion Nuclear picture and television cameres during current interest to the Committee.
Station.
this meeting may be limited to selected 8:45 AM-10:45 AM: Emergency Core 4:45 PM-6MPM:JalptovedSafety portions of the meeting as determined CooRing (Open}-Review aspects of the PeaturesforPuture Light Water by the Chairman. information regarding j
proposed revision of to CFR 50.46 Reactore (Open/ Closed)-Discuss the time to be set aside for this purpose 1
regarding use of"best estimate"models proposed ACRS comments regarding the may be obtained by a prepaid telephone in the evaluation of ECCS performance.
cost effectiveness. feasibility, and call to the ACRS Executive Director.
f12 A.M.-12WNoon: Meeting with benefit of safety-related systems and RJ. Fraley, prior to the meeting. la view Director, NRR (Open)-Discurs items of features n ted in its report of January of the possibility that the schedule for 15.1987.
. ACRS meetings may be adjusted by the mutual interest regarding NRR activities.
JmPM42PM: Management end Portions of this session may be closed Chainnan as necessary to facilitate the 4
DisposalofNuclear Waste (Open}--
as squhed to discuss information conduct of the muting, persons i
Discuss proposed research sctivities provided in confidence by a foreign planning to attend should eeck orith the,
reisted to the management and disposal ACRS Executive Directorif such source.
cf high and low-let al radioactive waste. Saturday. Septmober 32.1987 rwchedehngwedd rudtin major g,,,,,,,g,,,,,
3:15 P.ivf.-5:15 P.M.: Auxiliory M:30AM-11MAM: Preparation o I have dstermined in a ccordance 3Ath '
PsedwaterSystem(Open)4onsider ACRS Reports do ths NRC(Open/.. f subseodon 30(d). Pub. L 88463 abat it is -
espects of nuclear power plant auxiliary. Closed)-Discuss proposed reports to' necessaryto close portions of this fesdweter system design and operation the NRCsegarding tiems conaldered meeting as noted above tu discuss lhzt impact on system reliability.
durbs this meeting '. '
information the rolesee of which would 5:15 PR-4:30PM: ACRS Reports to.
Portions of this sesslan may be anossd espresent a. clearly umearranted NRC(Open)-Discussproposed ACRS as required to discuss information invasion of[norsonal privacy (5 U.S.C.
reports to the NRC regardirng eatters providtd in confidence by & Tcrelga 32b(c)(S)1. nformation relate d to the noted above, source.
internalpersonnel rules and precuces of
(
4
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32858 Fed:ril Regist r / Vol. 52s No.168 / Monday, August 31, 1987 / Notic:s.
thi agency (5 U.S.C. 552b(c)(2)), and *
- September 15,1987'at 9:00 a.m :
- 3. Comments slkould be specific and '
information provided in confidence by a Towne Plaza Motor Inn, Veranda Room.
concise. Alternative language should be.
f: reign source (5 U.S.C. 552b(c)(4)).
N.nh Street and E. Yakima Avenue; submitted if a change is being proposed..
Further information regarding topics Yakima, Washinf,toru
- 4. All wmments should be typed,if in be discussed, whether the meeting
- September 21,1987 at 10:00 a.m.,
possible, and double spaced, it would h:s been cancelled or rescheduled, the Northwest Power Planning Council,1301 also be helpful!f a separate page were Chairman's ruling on requests for the Lockey Street, First floor Helena, prepared for comments on each cpputunity to present oral statements Montana; and proposed amendmer,t or tejection..
and the time allotted can be obtained by
- September 25,1987 at 9:00 a.m.,
Provide ten copies of all comrnents,if a prepaid telephone call to the ACRS Northwest Power Planning Council.
Possible.
Executive Director, Mr. Raymond F.
Central Office,850 SW. Broadway, Suite Fon runTHan mFonesAft0N CONTACT:
Fraley (telephone 202/634-3265),
1100, Portland, Oregon.
Dulcy Mahar, director ci public between 8:15 A.M. and 5:00 P.M.
information and involvement,859 SW.
Instmetions for Oral Comment at a6ay, Sdem NMand, Oregon Datt AuguAt 26.1987.
HearinE' 97205 (toll free 1-800-222,3355 in Idaho, M eC. Hope..
- 1. Requests for time slots must be '
Montana and Washington: toll-free 1-Addsory Committee Management Officer.
made at least five days prior to the 800-452-2324 in Oregon: or 503-222-(FR Doc. 87-19948 Filed 6-26-87; 8 43 ara) hearings. Contact Ruth Curtis.
5161).
information coordinator, at the Council's ' suPPt.EMENTARY issF0nl4ATION: On central office,850 SW, Broadway, Suite November 15,1982, as required by the 1100, Portland, Oregon 97205 or (503)
Pacific Northwest Electric Power PACIFIC NORTHWEST ELECTRIC 222-5161 (toll free 1-800-222-3355 in Planning and Conservation Act, Pub. L POWER AND CONSERVATION Idaho, Montana and Washington or 1-96-501. 94 Stat. 2897,16 U.S.C. 839 et Pt.ANNING COUNCIL 80N52-2324 in Oregon).
. seg. (the Act), the Council adopted a 2.Those who do not sign up for time Columbia River Basin Fish and Wildlife Columbia River Basin Fish and Wl'dlife si to will be permitted to testify as time Prograrr The Act allows the Council to Program; Proposed Amendments permits.
amend its program from time to time.
Regarding Umatitle Fish Hatchery; Hearings and Public Comment Perled
- 3. Hearings should be used to in 1984, the Council called on summarize written comments
- Bonneville to fund the development of a AntNcy: Pacific Northwest Electric Commenta should not be read.
hatchery at Umatilla, Oregon to Power and Conservation Planning Comments should be limited to the draft produce 200.000 summer steelhead Council.
amendment document.
(40.000 pounds). At its October 1980 l
Actioet Notice of proposed
- 4. If possible, ten copies of hearing meeting the Council approved siting, cmendments, hearing and opportunity testimony should be submitted to the feasibility and preliminary design of the to ::omment.
Council recorder at the hearings. This hatchery, and directed that the design person will be sitting at a table near the should allow for future expanded sunsetAny:On Novembr 15,1982, the Council members. (See instructions for capacity up to 160.000 pounds.The Pacific Northwest Electric Power and written comment.)
Council noted that an amendment would Conservation Planning Council (the 5.Those persons officially be needed prior to expanded Council) adopted a Cclumbia River representing an organization will have construction. At its February 1987 Basin Fish and Wildlife Program (fish 15 minutes to summadre their written meeting. the Council approved such an end wildlife program).The fish and testimony. (Organizations may have amendment. and called for development wildlife program has been amended on only one officialrepresentative.) All
. of a facility master plan.
several occasions since then. The
.other individuals will be limited to five A hatche master plan is beIng Councilis proposing again to amend the minutes.These time limits will be prepared, w ch willdescribe the fish and wildlife program, to allow observed strictly in order to allow production profile, smolt release sites, tisting of oxygen supplementation at the parties to testify.
etc., and explain how the hatchery
~
Umatilla hatchery.The proposed 6.The Council may ask c,uestions for operations will respond to the program cmendraent of the fish and wildlife clarification. If so, this will be over and goal of doubling salmon and steelhead program is being relea sed for public '
above the time limits imposed above.
run sizes. and other Council policies (see review and comment and pubhc
- 7. A written record of each hearing Program Section 204).The Council hearings will be held.This notice i
describes the proposed amendments;
. will be made. Appearance at more than expects the master plan to be submitted one hearing is unnecessary. Scheduling in October 1987, with Council action in provides information on how to obtain preference will be given to individuals December 1987, and construction cte it eIt and { eatings.ups which have not testified at beginning in mid 1988, ocument. an the During the early phases of master plan outlines the process for submitting he pm nt t came op r written comments and participating in Instructions for Written Comment the hearings.-
3, Comments should be limited to the place to test a new method of fish EATLI AND ADOps9ase.'Ihe,publlC,
proposed amendment and must be.
production using supplement &I oxygen.
comment period negarding the proposed received in the Council's central office, in the existing hatchery design, half of
.anendments closes at 5 p.m., September 850 SW. Broadway, Suite 1100, Portland. the ponds would use a standard double-30,1347. Public hearings on the proposed Oregon 97205 by 5 p.m. on September 30/ ' pass water system,in which a given amendnaras will be held.
1907. Comments received after that time volume of water is used twice. Oxygen
- September 10,1987 at 1:30 p.m., City. will not be considered..
supplementation involves re aerating Council Chambers, tl.e Electric Building.
- 2. Written comments should be oxy' gen-depleted water so that a given 140 S. Capital, Idaho Falls, Idaho:
. marked "Umatilla Hatebery Comments." volume of water can be used three w
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION o
{
.,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
g WASHINGTON, D. C. 20665 Revised: September 4, 1987 I
1 SCHEDULE'AND OUTLINE FOR DISCUSSION I
329TH ACRS MEETING SEPTEMBER.10-12, 1987 I
WASHINGTON, D.C.
)
.i
'l Thursday, September 10,1987, Room 1046,1717 H Street,'M.W., Washington, D.C.
I 1) 8:30 - 8:45 A.M.
Chairman's Report (0 pen) 1.1) Openingrenarks(WK) l 1.2)
Items of current interest (WK/RFF) l 1.2-1) Proposed meeting dates for 1988-1.2-2) ACRS subcommittee meeting of the 1
Whole-ACRS Future Activities 2) 8:45 - 10:45 A.M.
ECCS - 10 CFR 50.46 Revision (0 pen) 2.1) Subcommittee report regarding proposed uncertainty methodology in use of best-estimateevaluationmodels(DAW /PAB) 2.2) Meeting with NRC Staff representatives
.)
10:45 - 11:00 A.M.
BREAK 3) 11:00 - 12:45 P.M.
Emergency Planning (0 pen)'
l 3.1) Discuss proposed ACRS recommendations l
regarding emergency planning in the' vicinityofnuclearfacilities(DWM/EGI) 12:45 - 1:45 P.M.
LUNCH I
4) 1:45 - 3:45 P.M.
Auxiliary Feedwater System Reliability (0 pen) l 4.1) Report of ACR5 subcommittee regarding
.j l
proposed resolution of GI 93, Steam
-l Binding of Auxiliary Feedwater Pumps and G1 124 Auxiliary Feedwater System i
Reliability (DAW /PAB) 4.2) Meeting with NRC Staff representatives l
3:45 - 4:00 P.M.
BREAK 5) 4:00 - 4:15 P.M.
AdvancedReactors(0 pen) 3"T" Report of subcommittee meeting on' August
]
25-26, 1987 regardingLMRs(DAW /MME) i 1
se
f l
~
329th ACRS Meeting Agenda
-2<
4 6) 4:15 - 5:15 P.M.
Meetinp with Director, Office of Nuc. lear Reactor Regulation (0 pen) 6.1) Briefing and discussion regarding items i
of mutual interest about NRR activities j
7) 5:15 - 5:45 P.M.
Nuclear Waste / Allocation of Resources j
(Closed) 7.1) Discuss allocation of NRC resources to
. provide technical advice to NRC regarding j
regulationofnuclearradwaste(DWM/5JSP)
(Note: This session will'be closed as necess-ary to discuss the internal personnel rules and I
practices of the NRC and information the j
release of which would represent a cicarl unwarrantedinvasionofpersonalpriv'acy.)"
8) 5:45 - 6:30 P.M.
Preparation of ACRS Reports on:-(0 pen) l 8.1)
ECC5 - Propcsed revision of 10 CFR Part50.46(DAW /PAB) 8.2) Auxiliary Feedwater System Reliability l
(DAW /PAB) 8.3) EmergencyPlanning(DWM/EGI) i Friday, September 11, 1987, Room 1046, 1717 H Street, N.W.1 Washington, D.C.
9) 8:30 - 11:00 A.M.
Nuclear Waste Management and Disposa'l (0 pen)
WTeport of subcommittee treeting on August 17-19.1987(DWM/OSM) 9.2) Meeting with NRC representatives regard-ing:
9.2-1) Borehole and shaft closure 9.2-2) Solidification of decontamination resins 9.3) Preparation of ACRS report to NRC 11:00 - 11:15 A.M.
BREAK
- 10) 11:15 - 12:00 Noon AspointmentofACRSMembers(Closed)
~
M.1) Subcommittee report regarding new members i
(HWL/NSL)
I (Note: This session will be closed to discuss information the release of which would consti-tute a clearly unwarranted invasion.of personal privacy.)
12:00 - 1:00 P.M.
LUNCH 11) 1:00 - 1:45 P.M, Future ACRS Activities _ (0 pen) 11.1) Discuss anticipated ACRS Subcommittee activities (DWM/RFF)
E__________
g; t,
329th ACRS Meeting Agenda. -
l
' I l
. 11.2). Discuss items' proposed for consideration by the full Committee (WK/RFF)1 11.3) Report of subcommittee chairman regard-ing proposed staff resolution of ACRS recommendations in its report of June i
10,>1986 regarding proposed operation I
of the South Texas nuclear plant.
(JCM/MME) 12) 1:45 - 2:15 P.M.
Storage-of'SpentFuel.(0 pen) 12.1) Subcommittee chairman's report regarding
)
. proposed revisien of 10 CFR Part 72 to define requirements for a monitored
.retrievablestorage(MRS) facility (CPS /OSM)
- 13) 2:15 - 3:15 P.M.
Trojan Nuclear Station (0 pen)~
13.1) Pipethinningclncident(JCE/HA)
'3:15 - 3:30 P.M.
BREAK
- 14) 3:30 - 4:30 P M.
Imoroved Safety Features in Future I.WRs M n/ closed) l 14.1). Discuss proposed response to inquiry
' {
, regarding cost, effectiveness, etc. of l
safety systems noted in ACRS report of January 15,.1987(CJW/RKM)
(Note:
Portions of this session will be closed as necessary to discuss information provided in confidence by a foreign source.)
I
- 15) 4:30 - 6:00 P.M.
Subcommittee' Activities: (0 pen / Closed) 15.1) 4:30-5:00:. Reactor Operations (0 pen)
- Discuss ACR$ procedures for-i reporting / evaluating o and incidents (JCE/HA)perating events' 15.2) Reports on:
1
~
15.2-1) 5:00-5:30: Regional'Activi-ties - Subete. meetin 1725/87 at Region V.(g onFJR/PAB)
(0 pen) i 15.2-2) 5:30-6:00:
Foreign Requla--
tory Policies and Prac",1ces -
(Closed) - Meeting with tMEA Technicel' Advisory Committee i
(WK/etal./RFF)
(Note:.This session will be closed to discuss information provided in con -
fidence by a foreign source.)
)
I I-
]
v.
329th ACRS Meeting Agenda
- ~
q l
j Saturday. September 12, 1987. Room'1046, 1717 H Street. N.W.
1(ashington, D.C.
- 16) 8:30 - 12:00 Noon PreparationofACRSReportson::(0 pen / Closed)-
H (11:00-11:15-BREAK) 16.1) B:30-9:00:
5torate of Spent Fuel -
10 CFF, 72 Revision (Open).
(tentative)(CPS /0SM)-
- j 16.2) 9
- 00-11:00: Improved Safety Features for Future LWRS-(Open/01osed) -
Response regarding effectiveness, cost, etc., of systems in ACRS.
report of January 15. 1987-i
.(CJW/RKM)
(Note:
Portions of.this session will
-)
be closed as required to discuss in--
~l femation provided in confidence by a -
.foreignsource.)
11:00-11:15: BREAK b
1 16.3) 11:15-11:45: Emeroency Planning
-l (MJ5/EGI) 0 16.4) 11:45-12:00:. International QA Workshop
-(FJR/EGI)
~
12:00 - 1:00 P.M.
LUNCH
- 17) 1:00 - 3:00 P.M.-
Complete ACRS reports and discussion regarding items considered during this meeting 1
(0 pen / Closed) 17.1) Items, as appropriate'
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.a MINUTES OF THE 329TH ACRS MEETING SEPTEMBER 10-12, 1987 WASHINGTON, D.C.
l The 329th meeting of the Advisory Committee on Reactor Safeguards, held at 1717 H Street, N.W., Washington, D.C., was convened by Acting Chair-man F. Remick at 8:30 a.m., Thursday, September 10, 1987.
[ Note:
For a list of attendees, see Appendix 1.
Dr. Shewmon did not i
attend this meeting.
Drs. Lewis, Moeller, Okrent, and Steindler were i
not present on Saturday. Mr. Ward was not present on Friday and Satur-day.]
The Chairman said that the agenda for the meeting had been published.
He identified the items to be discussed on Thursday. He stated that the meeting was being held in conformance with the Federal Advisory Commit-tee Act and the Government in the Sunshine Act, Public Laws92-463 and 94-409, respectively.
He also noted that a transcript of some of the public portions of the meeting was being taken, and would be available in the NRC Public Document Room at 1717 H Street, N.W., Washington, D.C.
[ Note:
Copies of the transcript taken at this meeting are also avail-able for purchase from the Heritage Reporting Corporation, 1220 L Street, N.W., Washington, D.C. 20005.]
I.
Chairman'sReport(0 pen)
[ Note:
R.
F.
Fraley was the Designated Federal Official for this portionofthemeeting.]
Dr. Remick announced that the proposed schedule for ACRS meetings for calendar year 1988 was in the Meeting Notebooks under Tab 1.2-1.
Members wer,e asked to review the proposed schedule and to inform Mr.
Fraley of known problems before the discussion during the Future Agenda discussion.
Dr. Remick also noted that propcsed meeting dates for October (1988) were 6-8; for November,10-12; and for December, 8-10.
(These had been inadvertently omitted in the printing.)
Dr. Remick said that the meeting of the Planning Subcommittee on October-22-23 and and for one-half day on October 24 was to be held at the Sheraton International Conference Center in Reston, Va.
Members were asked to inform Mr. Lockard if they are to attend.
Dr. Remick presented a certificate to Mr. Libarkin marking his 30 years of Federal Service.
I II. ECCS - Revision of 10 CFR 50.46 (0 pen)
[ Note:
Mr. P. Boehnert was the Designated Federal Official for this l
portionofthemeeting.]'
j Mr. Ward, Chainnan of the Thennal Hydraulic (T/H) Phenomena Subcommit-I tee, reported that, about three to four years ago, NRC was urged to make
f 1
329TH ACRS MEETING MINUTES 2
constructive use of the large body of ECCS/LOCA research.
Out of this effort, the revised ECCS Rule was proposed. The new rule allows use of 1
realistic [best estimate (BE)] evauation models for LOCA calculations Versus the present overly conservative ems.
The ACRS has endorsed the
]
use of the BE approach.
The Congress has urged that ECCS research be put to good use because of the potential economic advantage gained by Licensees (e.g., increased power production).
The Comittee has urged use of BE models in order to enhance safety analyses, particularly for transient analyses; another factor is that physical parameters of ECCS j
systems have been tuned to conservative EM analyses sometimes to the detriment of safety.
?
Mr. Ward also noted that use of BE models requires taking account of the i
necessary accompanying uncertainty analyses.
He said that use of BE models doesn't invent new uncertainties, and use of engineering judgment is still required, just as it has been with the current ems, especially during their early use.
At ACRS' behest, the T/H Phenomena Subcommittee has reviewed the NRC Office of Research (RES) Staff's effort to develop a comprehensive uncertainty methodology. Mr. Ward said he has asked Dr. Catton, who has been observing.the RES effort on behalf of the ACRS, to give the Commit-tee his perspective on this work.
{
In response to Mr. Reed, Mr. Ward noted that the uncertainty methodology utilizes a combination of analyses and evaluation of test data where relevant data is available.
Mr. Reed cautioned that the economic incentive here is strong, thus the ACRS review must be particularly diligent.
Dr. Lewis noted that one should be talking in terms of " realistic" not "best estimate" for this topic, as "best estimate" has a definite I
statistical connotation.
I Dr. Shotkin, NRC/RES, provided overview remarks.
He noted that the Commission required RES to seek ACRS review of its uncertainty eval-uation methodology known as the Code Scaling, Applicability, and Uncer-tainty (CSAU) development effort.
Peer review of the CSAU methodology is scheduled to begin in November 1987.
RES said that the ECCS Rule package consists of (1) the revised Rule, (2) a Regulatory Guide, and (3) a Compendium of ECCS Research supporting the new Rule.
One of the objectives of the Compendium Report is to justify why it is acceptable tp use realistic evaluation models for LOCA calculations in the regulatory process.
RES's schedule for issuance of the Final ECCS Rule calls for ACRS review of the Final Rule version in December 1987.
RES sees the following ultimate uses of their uncertainty methodology:
o q
329TH ACRS MiUING MINUTES 3-1 H
1.
Proof.of principle 2.
. Independent audit to check industry submittals 3.
Guidance for industry.
Dr. Shotkin noted that W:and CE have (or will) submit their uncertainty methodology for NRC revlew. ~ There.will be no requirement for industry to follow CSAU directly, but they, must be aware of the' basics of the CSAU method.
I Dr. ~ Zuber. detailed. the - CSAU methodology developed 'by NRC/RES.. Mr.
Michelson asked how inewly. discovered phenomena are accounted. for in
.CSAU. Dr.;Zuber said he would address this point'1ater in his.presenta -
tion.
In response to Mr. -- Ebersole, Dr. Zuber said' the CSAU method willi be-applied to various accident scenarios other than LB LOCA (SB LOCA, transients,etc.).
~
Dr. Zuber noted that CSAU addresses-three key issues for use of realis-tic'models:-
j 1.
Code. capability to scale-up phenomena observed in small scale test facilities to a fu11' scale NPP-2.
Code capability to address a particular scenario or-set 'of scenar-ios for a given plant design 3.
Code uncertainty to calculate important parameters (say peak cladding temperatures, PCT), in a full scale NPP.
j R
These three issues must be addressed in order to properly use realistic' (BE) codes.
Dr. Zuber discussed the role of scaling in plant safety analyses.
Referring to a flow chart (Figure 1), he detailed the parameters-of -
concern for use of scaled experiments and how they are addressed.
Referring to the power-to-volume scaling approach, Dr. Zuber noted that 4
the inevitable distortions of this (or any other) scaling approach must i
be (and are) addressed in the CSAU method.
In response to Mr. Ebersole, Dr. Zuber said the overall code uncertainty value r.alculated by CSAU is both plant-and. scenario-specific.
The ca> abilities and characteristics of the modern thermal hydraulic codes (TRAC RELAP-5, etc.), and their attendant problems, were noted.
Dr. Zuber indicated that in order to assure the ~ integrity. of these codes the adequacy of the closure equations must be ' determined,'the effect of-
" tuning" must be evaluated, and whether or not the code has compensating errors must be decided.
Dr. Zuber indicated.that use of ' engineerit.g judgment is necessary during this entire endeavor.
-9 1
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329TH ACRS MEETING MINUTES 4
The specifics of the CSAU methodology were discussed.
The basic re-quirement for use of CSAU is complete documentation of the code in question. This includes a code manual, a quality assurance document on the models and considerations in the code, a user guide, and an assess-ment report.
Dr. Lewis raised a concern with the lack of a clear definition of what is meant by " uncertainty" in the CSAU method.
In response to Mr. Michelson, Dr. Shotkin noted that the " unknowns" (vis-a-vis LOCA phenomena) will still remain with this new method, t
The details of the CSAU method were discussed.
A flow chart detailing the elements of the CSAU method is shown. in Figure 2.
In response to Mr. Michelson, Dr. Zuber said that if a user runs a calculation with nodalization that is different from that used by the code developer, the user must evaluate the specific impact of the nodalization change.
Describing the application of CSAU to a LB LOCA, Dr. Zuber noted. that preliminary results obtained by use of CSAU to date have shown that the LB LOCA PCT blowdown peak is independent of scale for the test facil-ities evaluated.
Dr. Lewis questioned the validity of the statistical approach used by NRC/RES in the CSAU method.
Dr. Zuber noted that a pure s.tatistical approach is not (and realistically cannot be) used here.
l
~
Currently RES is applying CSAU to a TRAC-PFI/ MOD 1 LB LOCA calculation.
The results of the exercise should be available by the end of 1987.
A Technical Program Group (TPG) is overseeing this effort as well as the continuing CSAU development effort.
Dr. Okrent noted that LB LOCA is consi.dered a low probability' event. He wondered if time has overtaken this effort and questioned the need for such a complex exercise.
Dr. Zuber indicated that CSAU can be applied to a simple problem like LB LOCA, but it is also comprehensive in that it can be applied to more complex problems such as SB LOCA and tran-sients.
Dr. Catton provided comments from his prospective as a TPG member.
Points noted include:
Appendix K should be abolished; it is too prescriptive. We need to move toward use of realistic BE analyses combined with an uncer-tainty evaluation.
The central question is how to (correctly) quantify tne uncertain $y.
W, CE, and EXXON have either proposed or ' submitted their own version of BE LOCA codes for NRC review.
.=
4a FLOW OIAERAM FOR CODE SCALING, APPLICA81LITY AND UNCERTAINTY (CSAU) EVALUATION METHODOLOGY Scenario Specification 1
Select NPP and frozen code i
Provide complete code documentation
)
i Reviewcodecomparigenstolimiteddata sets (Separatg ggTest) and a I
Develop phenomena identification and
-ranking tables (PIRT).-
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a 1
329TH ACRS MEETING MINUTES 5-
'I i
The various uncertainties' involve in PCT' prediction must be com--
bined in an acceptable way.
Use of engineering-judgment is neces-sary to decide how this'should be done.
The key step for the use of the CSAU method is to perfonn a reason-ableness test of the code (s) in question by comparison of. the critical models with appropriate separate effects ~ tests. This step-will also require judicious engineering judgment.
The problem of compensating errors'must be addressed in the use of the codes.
As a result of the CSAU development effort, NRC will require the code developers. to provide ' complete documentation (QA document,.
assessment report, etc.) before the code is released for use.
In conclusion, Dr. Catton noted that the CSAU method is simple and straightforward to apply.
The need for. use of engineering judgment is justified because the method is scrutable.
ACRS _ should encourage the CSAU effort but reserve judgment until 'the method has been exercised, i
Mr. Ward asked if CSAU will-falicapart if used on SB LOCA and tran-sients.
Dr. Catton said that he didn't 'think'so. but.SB LOCAs will be much more difficult to evaluate for overall code' uncertainty. Addition-al experiments may be necessary to assure the proper data is available for use of CSAU here.
~
i III.fEmergencyPlanning(0 pen)
[ Note:.Mr. E. I of the meeting.]gne was the Designated Federal Official for this portion i
Dr. F. Rowsome, bak Ridge Associated Universities (formerly of NRC), Mr.
H. Specter, New York Power Authority, and Dr. L. Ritchie, Sandia Nation-al Laboratories, discussed preliminary analyses of the benefits of various measures taken as.a means of protecting the population in case I
of a major accident at a nuclear power plant.
Studies reported by these groups indicate that sheltering, followed by monitoring of radiation exposure rates, and relocation within four to eight hours after an accident of populations found to be in affected high-radiation areas, yields predictions for: the number of prompt i
fatalities lower than those estimated to be provided by large-scale evacuation as expected under current decision-making practices.
This was the statistical result for a wide range. of accident scenarios.
Further, the number of people, the distance they would need to te moved, and the disruptive-impact of sheltering-relocation - approach would l
normally be less' than those for the insnediate evacuation approach.
4
____-.____m.________
329TH ACRS MEETING MINUTES 6
The 'Comittee prepared a letter to Chairman Zech on this matter.-
IV. Auxiliary Feedwater Systems Reliability (0 pen)
[ Note:
P. Boehnert was the Designated Federal Official for this portion ofthemeeting.]
Mr. Ward, as Chairman of the Decay Heat Removal -Systems '(DHRS) Subcom-mittee, noted that the ACRS had conmented in a pejorative sense, on the-resolution approach for GI 124:. " Auxiliary Feedwater System (AFWS)
Reliability."
At the ACRS September 1986 meeting. the NRC Staff asked-the Comittee to defer judgment on their resolution. approach until further work had been done. NRR has reviewed two additional' plant sites and the DHRS Subcommittee reviewed their efforts to date at a meeting on August 5, 1987.-
S. Diab, NRC/NRR, reviewed the status of GI-124.
He noted that this issue first arose after the TMI-2 accident, and that subsequently a reliability study of all PWR AFWSs was e NRR also incorporated a numerical reliability criterion of 10 qpducted.5 unavailability / demand to 10~
into the Standard Plan Review. All PWR AFWSs'were subsequently reviewed per NUREG-0737 requirements and, as a result, the.AFWSs at seven plants were found wanting.
The issue of the reliability.of the AFWSs of these seven plants (ANO-1 and
-2, Crystal River-3, Ft. Calhoun, Prairie Island-1 and -2, and Rancho Seco) fonned the bases for the' GI-124 effort.
Mr. Ward noted that there are some PWRs with two-trainIAFWSs that have demonstrated an acceptable reliability.
NRR confirmed ' this statement.
Mr. Reed cited the additional concern with B&W' plant. AFWSs via the potential problems associated with secondary side level control.
He also raised the concern of having four steam generators versus two steam generators on some PWR designs and how this impacts on the reliability of DHR. Mr. Ward noted that some plants can ramp down MFW flow to very low levels which may aid DHR reliability.
The NRR resolution approach for GI-124 involves a plant-specific review by a multidisciplinary NRR AFWS Review Team.
The Team's review sco covered t.11 aspects (design, maintenance, training, operation, etc.') pe of the plants' AFWS.
Any recommendations 'for backfits are being handled via the 10 CFR 50.109 requirements.
To date, Staff reviews for Prairie Island and ANO-2 are complete.
The Crystal River Unit 3 Report should be issued later this month.
The remaining three plant reviews are scheduled to be completed by January 1988.
The review status for each of the seven plants was noted.
Dr. Okrent said that a Sandia report on prevention and - mitigation of severe.
I l
1
'l 329TH ACRS MEETING MINUTES 7.
1 j
accidents noted concerns associated'with blowdown of-the RPS.
He asked if ~ NRR had considered the negative aspects -associated. with feed-and.-
bleed (F&B). Mr. Ward noted that this item has indeed caused F&B to be q
controversial.
NRR noted that timelyT initiation of F&B is : crucial to' 4
success and. there are many technical constraints on its. use.
]
n indicated that their evaluation of how much credit to assign to use of
]
F&B vis-a-vis resolution of GI-124 was tempered by the above concerns.
It was noted that ANO-1.and Rancho Seco may not be visited by the AFWS:
Review Team because of other NRC programs addressing concerns with these' Units.
1 Details of the results of the Prairie Island AFWS review were noted. A
{
number of minor' corrective actions were recommended by NRR, and the
{
Licensee has agreed to~ address these items.
Dr. Okrent questioned.NRR regarding the specifics of the'F&B procedures i
i for Prairie Island, as this plant was credited for F&B capability.
NRR q
l noted, in response to Dr. Okrent, that all PWR AFWSs are seismic Class i
1.
Discussion ensued on the issue of what " credit" NP.R gives to u'se of-1 F&B.
In response to Dr. Kerr, NRR said the - AFWS reliability. issue ~1s outside the regulatory requirements for these plants. - Given this, consideration of the use of F&B is appropriate.
For ANO-2, it was. concluded that. the Licensee should provide an alter-
)
nate method to get water to the steam generators.
The Licensee has agreed to look into this item.
In response to Dr. Remick, NRR said that for the above Item they would proceed under the. provisions of the,
Backfit Rule.
The impact of.the recent Court decision on the Backfit
]
Rule is unclear.at this time for this specific generic issue.
G. Mazetis, NRC/RES, discussed the. resolution of GI-93,l" Steam Binding f
of AFW Pumps."
The issue here involves the potential for steam binding i
of AFW pumps due to' backleakage of main feedwater past check valves.
The concern is that of a potential common cause failure of AFW..
As a result of numerous steam binding events in the 1980-83 time frame, i
IE Bulletin 85-01 was issued, requiring all PWRs to monitor the. tempera-ture at the AFW pump discharge, at least once per eight hours, and to develop procedurrs to deal with steam binding events. ~GI-93 was also formed, and given a high priority, to seek a permanent resolution.
The:
key question is:
Were additional requirements needed;beyond the 85-01 requirements?
RES's study of this Issue showed that. there was a large group of _ PWRs (56 plants) that had few or no steam. binding events, and a small. group (7 plants) that was experiencing numerous events.
This small group.has.
installed continuous temperature monitoring systems ~(alanned in: the.
control room) on their AFWSs to warn of an-impending event.
NRR ana-lyzed the cost / benefit of requiring similar monitoring systems on all
~
'329TH ACRS MEETING MINUTES 8.
U 1
I PWR AFWSs.
The analysis' did not-support this action, especially in -
i light of IE Bulletin 85-01 requirements.
Mr. Mazetis noted that repairing the leaking check valves sol'ves the_.
problem and said that the. Industry has taken action on a generic basis to address the issue of check valve reliability.
Mr. Reed indicated that the above two generic issues argue for adoption of a primary blowdom system.
Mr. Ward said that the resolution proposed for L GI-93 by RES' (i.e.,,
continue the Bulletin 85-01 requirements)'was found acceptable to' the DHRS Subcommittee.
He said he - did not see any need for additional Comittee action on this Issue.
The Committee concurred with Mr. Ward's.
recommendation.
V.
Meeting with Director, Office of Nuclear Reactor Regulation (0 pen)
[ Note:
Mr. D. Houston was the Designated Federal Official for this portionofthemeeting.]
'Dr. T. Murley, Director, NRR, discussed a number of topics'in regard to the new NRR organization, the mode of operations, and the interface with the Office of Research.
He described the role' of the Executive ' Team l
which meets daily to determine 'a course 'of.~ action.
He also indicated that the role of the' plant. Project Managers had been significantly increased with requirements that they spend more time at the site and~in
. the Region.
NRR will be. placing a. greater emphasis on plant operating performance.
He based some of his conclusions concerning the contribu-tion of perfomance to core melt frequency on'a Brookhaven study of the Surry plant. ' Human error increased the core melt frequency by a factor j
of 7.
He questioned the numerical values in PRAs since the adequacy 'of pli.nt operation was not considered in PRA studies.
Finally, he dis-i cussed the current NRR approach to the BWR Mark I issues as part of a more comprehensive study) involving improved plant operations, individual plantexaminations(IPEs and containment perfomance research.
5 Dr. Remick indicated that some members of NRR had' expressed concerns about the Executive Team concept and the absence of a single source for.
1 information and policy.
i Mr. Ebersole inquired about the. functioning of AEOD and whether NRR was,
satisfied with the level of ACRS review of operating events.- He also asked about the NRR function in reviewing the TVA projects. Dr. Murley-indicated that NRR has no project function for the TVA review.
Mr. Michelson questioned the interchangeable application of human error-versus operating performance. He'was also concerned about the band-aid-approach 'for operating plants and whether these - fixes are.the best t
solution to be carried forward in advanced L.WR reactor designs.
i 1
--m__________
- 329TH ACRS MEETING MINUTES 9
1 4
Dr. LKerr discussed the weakness in PRA studies of not considering operating performance. He asked about NRR's function in the'IPE effort.
Dr. Murley indicated that currently-there was no place in NRR for severe accident issues'such as the IPEs.
i Dr. Okrent expressed concerns about' NRR not having a place for. severe accident issues.. He also inquired about: studies on containment venting.
Dr. Moeller asked if NRR had received any' feedback from the Regions i
concerning the ACRS meetings with them.
Dr. Murley indicated that: all-comments that he'had heard were positive.
I Dr. Siess. asked-about the NRR. review function for advanced reactor.
j designs (non-LWR). -Dr. Murley indicated that the review was totally at R
Office of Research.
{
VI. NuclearWasteDisposal(0 pen)
)
i
[ Note:
Mr. O. S.' Merrill was the Designated Federal Employee.for: this portionofthemeeting.]
Dr. Dade W.
Moeller, Subcommittee Chai'rman, reported on' the Waste Management Subcommittee meeting held August 17-19, 1987.: He briefly discussed: (1) the berehole 'and shaft sealing. research being done for NRC by the University of Arizona, which the Subcommittee reviewed.during its visit there on July 28,1987, and (2) the solidification of decon-
~
tamination waste research being done for NRC by the Brookhaven National
,l Laboratory (BNL) and the Idaho National. Engineer.ing Laboratory (INEL),
which was reviewed during _the Subcommittee meeting.
He said that the Subcommittee had' prepared a draft report:regarding these two topics for full ACRS consideration, and that the NRC Staff was scheduled to discuss l
l them.
I Dr. Moeller also reported on several other' topics reviewed during the l
Subcommittee meeting, viz.,
1.
NRC's Quality. Assurance (QA) audit of. the mineralogy / petrology j
program at Los Alamos National Laboratory (LANL), which is in support of DOE's high-level waste repository program for Yucca Mountain, Nevada
~
2.
The Site Characterization Plan (SCP) for the Yucca Mountain,. Nevada j
site 3.
The low-level waste compacts and the issues.and problems being faced by the States in that regard.
A brief discussion ensued between Dr. Moeller,'Mr. Reed,-Mr. Ebersole.
l Dr. ~ Siess and Dr. Kerr on the subjects of the use of bitumen in. the j
solidification of decontamination wastes (resins) and 1of 'the i
l b
l 1
L_ - -
329TH ACRS MEETING MINUTES 10 flammability of these resins and other flammable low-level wastes. And, since flaninable wastes are, by definition, mixed wastes, their regula-tion might be a joint matter between the EPA and the NRC.
Research on Borehole and Shaft Sealing Dr. Jacob Philip, NRC Staff, project manager for the borehole and shaft sealing research project at the University of' Arizona, discussed this project.
He explained the NRC regulatory requirements (10 CFR 60,134),
described industry's experience in this area, stated the objectives of the research, told what experiments they are doing,(e.g., existing rock sealing technology), etc. ' In response to questioning by Dr. Siess on this matter, Dr. R. Grill, NRC Staff, said that the purpose of the research was to furnish the NRC Staff with sufficient information to independently assess the DOE license application.
Dr. Grill further explained that many of the research programs are exploratory in nature, to obtain the currently lacking information for repository licensing.
Subsequent discussion of this project included:
(1) the necessity for NRC to do this work and not rely solely on DOE's complying with existing NRC regulations; (2) the importance of this research vis-a-vis radio-nuclide transport through the surrounding medium (i.e., failure of a borehole or shaft seal provides a preferential pathway to the environ-ment); ~(3) sealing and backfill materials--bentonite, crushed rock, cement, etc.; (4) the use of distilled water in all their tests to have a common reference, with no variability attributable to water chemistry; (5) push-out tests; (6) penneameter tests; (7) drilling methods ~ and damage; (8) 1.nfluence of dynamic loading on the seals; (9)(11) prelimi rock tensile strength tests; (10) temperature influence on the seals; nary fracture grouting; (12) bentonite characterization; (13) horizontal versus vertical hole sealing; (14) flow testing and monitoring of bentonite seals in the field; (15) the relationship of this work to the l
SCP and to licensing the repository; (16) the quality, quality assur-l ance, and peer review of this research; (17) scaling effects from l
small-size seal experiments to large-size shaft sealing; and (18) the l
application of test results in various media--basalt, salt tuff, and I
granite.
I I
.Research on Solidification of Decontamination Waste l
Dr. Phillip R. Reed NRC Staff, NRC project manager for the Solidifica-tion of Decontamination Waste project at the Idaho. National Engineering Laboratory (INEL), discussed INEL's research efforts.
He gave an overview of this project, stating that its goals are:
(1) to determine radionuclides and chelating a tion low-level radwaste, (2) gents released from solidified decontamina-to determine and evaluate factors affecting releases of radionuclides and chelating agents from these wastes, and.
(3) to evaluate the stability of these wastes, as required by 10 CFR Part 61.
329THACRSMEETINGMiNUTES
-11 Dr. Reed said that the objectives.of this program are-to:
1.
Perform studies on-decontamination waste generated and solidified at nuclear power stations, and on wastes solidified 'under. laborato-ry conditions 2.
Study properties of. solidified waste foms generated during the decontamination process.
3.
Determine impacts of decontamination solution on solidification and.
disposal methods 4.
Detemine leach parameters for radionuclides and chelating agents.
from solidified low-level waste 5.
Study effects of chelating agents on leaching parameters and solidification-Dr. Kerr asked what specific questions this research was trying. to answer and also, what do-you need to know in' order to do a good job of regulating?
Dr. Reed said that they need (1) to have an : adequate characterization of the radionuclides present and the specific relative contributicms of each radionuclides in the solidified waste fom;1(2) to l
obtain good data on the release rates for each radionuclides 'under a variety of conditions that tend to simulate.the groundwater; (3) to study leaching under various pHs under different water: quality parame-ters; (4) to obtain infomation on the release rates of chelating agents;- and (5) to obtain information' on the ' structural stability of '
solidified waste forms, as-required by Part-61. The reason for. getting these parameters is to make better assessments in the future disposal of these wastes.
Dr. Steindler asked:
Why was it perfectly all right some six years ago to dispose of decontam'ination waste as low-level waste when Dresden-1 was being decommissioned?
The presence of chelating agents did not adversely impact on the health and safety of the public then.
He also asked: Why does the NRC Staff now say there really isn't auch informa-tion?
Dr. Reed answered that bitumen was -the solidification material being used at that time, and now they are not emphasizing bitumen, but are looking at a variety of processes and chelates.
Dr. John Surmeier, NRC. Staff, stated that right now there are no waste forms that have been approved by the NRC for disposal.
Some have bee'n conditionally approved, awaiting test results, but NRC has not as of now-approvedasphalt(bitumen).
Dr. Steindler stated that the issue he was trying to raise was whether or not the presence of corglexing and chelating agents would so mobilize or potentially mobilize any contained nuclides in the groundwater system.
j
-_x
l j
a 329TH ACRS MEETING MINUTES 12 Dr. Kerr said it was apparently a conditiona1L approval in the. case of Dresden-1.
Dr. Surmeier agreed, and then _ added that chelating agents are specifically mentioned in Part 61 and' that they are of concern to the NRC.
Dr.. Kerr continued: to ask what the NRC Staff intends 'to do with the results of this research, if the results might indicate the need to dig up and re-dispose of prior disposed wastes, why the proprietary ' nature of the radionuclides coming from a nuclear _ power station, etc. Dr. Reed said that-in order for the vendors to allow NRC/INEL to sample the power plants (since their processes, are proprietary) they will. only release the information to INEL and the NRC. Staff.
Dr. Kerr asked why there is concern about chelating agents.
Dr. Reed-replied that Part 61 requires' them to address those systems in which chelating agents are used.
Furthermore, if chelating. agents are present 'in a low-level process, the - behavior of. the radionuclides actually changes. This will offset the overall transport process in the food chain path.
The radionuclides concentration and-release. rates are needed (in combination with the chelating agent).
Dr. Reed also-said that-other concerns are the presence.of' excess chelating agent, different physical properties, and possible reactions with other materials and waste' forms, including the-high integrity metal waste containers.
In answer to Mr. Ebersole's question as to what are the units of the teachability index, Dr. Reed answered that the teachability index is the reciprocal of diffusion and is a dimensionless number--a standard that everyone can use and work with.
Dr. Ruth Kempf, BNL, discussed (1) the properties: of' solidified decon-tamination wastes -- the " Properties" Program, which is concerned with the chemical characterization of decontamination' wastes. and their behavior, and (2) the decontamination impacts on_ solidification and
(
waste disposal --the " Impacts" Program which 'is concerned with the physical and bulk mechanical performance of decontamination waste forms and in-plant processing of wastes.
She said that these. programs.are complementary in that first one looks at things that are' generated and the chemical specifics of the waste; second, one looks at the bulk j
mechanical perfonnance of compressive strengths, immersion testing, etc..
)
Dr. Kampf discussed the. chemical complexity of chelating agents and the resultant effects on the solubility of wastes on their movement in the disposal environment, and therefore the" resultant. changes in the chemical characteristics in the wastes because of the pre:ence of. the:
chelating agents.
Hence decontamination-type wastes containing these agents may exhibit behavior quite. different from other types of waste',
and are therefore new and different.
1 W
i
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329TH ACRS MEETING MINUTES 13 Mr. Reed commented on the difficulty he was having relating this re-search to~ a nuclear power plant since there are all kinds of liquid waste streams and many complexities due-to the addition of boric acid, sodium hydroxide, etc.
He then asked if certain parts of the waste stream would be separated and cast in cement, and other parts separated i
and cast in asphalt.
Dr. Kempf replied that this may end up being the result.
The BNL program is trying to simplify the system and to find out the effect on each component.
Dr. Kempf indicated that the evalu-ation or sequence of the BNL Program is:
1.
Study the effects of chelating / complexing agents on radionuclides, releases from resins within solidified waste forms 2.
Complementary study of bulk physical / mechanical performance of i
solidified wastes containing chelating / complexing agents 3.
Investigation of treatment processes that could be applied to decontamination-type wastes j
She said that these are the main thrust of the program.
' Dr. Kerr asked, given that dual performance standards exist, whether the people who are responsible have tested ~and demonstrated that their waste forms meet these standards, and if the work is affirmatory or is testing systems that have not been tested, or none of the above?
Dr. John
~Sunneier, NRC Staff, answered that, at the present time, they have about 17 topical reports on waste. forms, of which they have approved three:
two in high integrity containers. (HIC),(not teachability) as required and one in which the basic purpose of the waste form is stability under Part 61.
One of the two HICs is steel; the other is concrete-impregnated resin.
(A third HIC, which is basically a polymer, is very close to being approved.) No topical reports have as yet been approved for cement or bitumen--they were " grandfathered" as far as conditional a proval until the topical reports on them have been approved.
Dr.
Surmeier added that the vendors submitting the topical reports 'have submitted test results which they believe weet the Branch Technical Position (BTP), which was promulgated in 1933, but which did not address "some of the things we are coming across right now."
~
Dr. Kerr asked if the vendors would have to resubmit their topical reports since they would not meet today's existing standards (although they apparently met the 1983 BTP standards).
Dr. Sunneier responded:.
"If it turns out that we found problems with cracking and with cement, i.e., instability, then they would probably have to submit additional infonnation."
Dr. Kerr asked what relationship exists between this research and the licensing of these specific waste forms. Dr. Sunneier said that, within the past two years, vendors have reported problems with their own products, which is why the NRC underook research/
technical assistance to explore these areas.
+
.i 329TH ACRS MEETING MINUTES 14 Dr. Kempf discussed:
1.
Physical. testing of solidifed decontamination waste forms--compres-sive strength and immersion tests of cement, vinyl ester styrene (VES), and bitumen solidified wastes 2.
Measurement ' f chelating agent / organic acid release. by leaching o
from - solidified simulated decontamination ' waste forms--for cement and VES, but not for bitumen 3.
Detennination of the effect on cobalt-60 releases from cement-soli'difed waste forms, of leaching with solutions.containing organic acids--for cement only Study of. effect of simulated ' contamination waste solidification.
4 d
sample size on chelating agent / organic acid release--for cement and VES 5.
Study of the effects of thermal cycling on cement and VES solidi-fied simulated decontamination waste fonns 6.
Interaction between container materials and simulated decontaminate-ed resin wastes with and without irradiation-.for a variety of resin waste compositions and several.centainer materials.
Dr. Kempf described the proposed and ongoing work at BNL under these programs, namely:
1.
Characterization of simulated decontamination-type resin wastes and wade forms 2.
Continuation of chelating agent / organic acid release studies The Committee discussed a draft report on the radioactive waste research program that was prepared by the Waste Management Subcommittee during
(
its meeting August 17-19, 1987.
It was agreed to continue this dis-cussion during the 330th ACRS meeting, October 8-10, 1987.
VII.
Pipe Wall Thinning at the Trojan Nuclear Stati6n (0 pen) l
[ Note:
Mr. H. Aldennan was the Designated Federal Official for this portionofthemeeting.]
Mr. Paul Wu, NRC/NRR, noted that the recent' wall thinning at the Trojan nuclear plant was ' the result of erosion / corrosion.
He remarked that this was a flaw assisted corrosion process that' affects carbon steel piping.
It could occur under a single-or two-phase condition.
It can occur at temperatures ~ ranging from 100*C-to' 250*C.
The maximum effect is at 130*C.
4 9
a 329TH ACRS HEETING MINUTES 15 Iron dissolves from the piping to form ferrous hydroxide and hydrogen.
l Magnetite is formed.
In an oxygen-deficient environment, the magnetite dissolves and leaves the pipe walls susceptible to further corrosion..
Mr. Wu listed three conditions necessary for erosion / corrosion:
environ-mental conditions, material variables, and hydrodynamic variables.
Water pH, temperature, and dissolved oxygen and impurities are signifi-I cant environmental conditions.
The chemical composition and heat
)
treatment of the piping and flow condition are also critical parameters.
j 1
The problem at Trojan was that elbows and straight sections of the J
non-safety-related, as well as the safety-related, portions of the nain I
feedwater lines were discovered to have wall thicknesses reduced below
]
the minimum code allowable value or will reach this value before the end of the 1988 fuel cycle.
Preliminary examination indicated that the piping degradation was caused by a combination of erosion / corrosion and erosion / cavitation attack.
Detailed failure analysis is continuing and l
the mechanisms which led to the piping degradation are not yet known.
q i
Mr. Wu discussed the significance of this thinning.
With the current industry practice, many of the locations where wall thinning could occur may not have been identified.
This is the first time significant wall thinning has been reported in the safety-related portion of the feed-water line and further evaluation may reveal potential generic implica-tions.
Mr. Wu. discussed the Staff actions regarding the Trojan pipe wall thinning.
An NRC task force was established on July. 9, 1987.
The licensee's failure analysis results were received and the plant was visited by headquarters personnel shortly thereafter.
Representative l
l samples from the degraded piping sections were selected for independent analysis and verification.
The NRC Staff subsequently evaluated the l
l operability of the repaired feedwater lines.
An NRC Information Notice 87-36 was issued on August 4, 1987 to alert the industry to the signifi-l cant unexpected erosion / corrosion of the feedwater lines at the Trojan I
plant. The following corrective actions have been taken for the Trojan plant.
Inspection of all of the seismic Category I feedwater piping system.
Replacement of piping and components with wall thicknesses now below the minimum code allowable or predicted to be below minimum code allowable by the 1988 refueling outage.
}
^
The feedwater pH will be increased over the current level to about 9.2.
The process will be implemented in steps and the impact evaluated.
1
___...1
329TH ACRS MEETING MINUTES
-16 Mr. Wu discussed the conclusions of the Task Force Evaluation as noted below:
'UT techniques for pipe wall thinning monitoring is the current industry practice.
An accuracy of 0.005 inch or less is adequate for pipe wall thickness measuren:ents.
Plant operating conditions have remained essentially constant in the last 10 years.
It is reasonable for the licensee to use 10 years as the basis to derive an. estimated averaga pipe wall thin-ning rate.
Licensee's methodology for estimating remaining pipe-life is adequate and conservative for determining the short-term operabil-ity of the repaired feedwater lines.
Licensee's corrective actions are adequate to ensure the safe operation of the feedwater system throughout the 1988 operating cycle.
The long-term operability of the.feedwater system at the Trojan plant will be determined upon completion of the licensee's failure analysis and the Staff / consultants independent verification.
~
Mr. Wu concluded, his presentation with a listing of follow-up actions by the Task Force:
Determine the long-termr operability of the feedwater lines at the Trojan plant 1
Combine information obtained from the Trojan event with the indus-i try responses to the NRC Bulletin 87-01, " Thinning of Pipe Walls in Nuclear Power Plants " and formulate an NRC regulatory position regarding the pipe wall thinning issue'in operating plants Issue SECY paper on industry practices by the end of 1987 Assess the need for regulatory action by mid-1988 Working with the ASME Code Committee on Inservice Inspection to address the pipe wall thinning issue and to provide guidance to industry for pipe wall thinning monitoring.
VIII. ExecutiveSessions(0 pen / Closed)
A.
Subcommittee Reports (0 pen / Closed) 1.
Advanced Reactor Design (0 pen)
[Mr. M. El-Zeftawy was the Cognizant ACRS Staff Member for >
this portion of the meeting.)
329TH ACRS MEETING MINUTES 17 4
Mr. Ward, Subcommittee Chainnan, briefed the full Comittee in regard to the Advanced Reactor Designs Subcommittee's visit to Idaho on August 25-26, 1987. He indicated that the Subcomit-tee members heard presentations from the Argonne National Laboratory (ANL) representatives on the problems pertaining to the design, construction, and operation of liquid metal reactors. The Subcommittee members (along with the NRC Staff) l visited and toured the following facitities:
Experimental Breeder Reactor (EBR-II) - a sodium-cooled pool-type fast. reactor with a peak thermal power of 62.5 MWt Hot Fuel Examination Facility (HFEF) Complex - originally" consisted of fuel cycle facility, but now has been decontaminated (HFEF/S) and it is ready for new equipment.
for plant-scale metallic processing and fabrication.
EBR-II will be in full operation as a complete Prototype, with fuel at target burnup levels and fuel being pro-cessed, fabricated, and returned to the reactor (Integral l
FastReactor-IFRprogram).,
I Transient Reactor Test Facility (TREAT) - It provides safety-related tests in support of the Breeder Raactor l
program, such as the overpower transient.
Zero Power P1'utonium Reactor (ZPPR) - Its mission is to provide basic experimental physics data for the design o'f-l
)
fast-breeder reactor demonstration plants and large l
fast-breeder reactor central-station power plants.
Mr. Ward expressed his satisfaction with the infonnative and well-organized presentations that were made by the ANL staff and said that he was pleased with the site visit.
Mr.
Ebersole agreed and shared the same sentiment.
l 2.
NewMembers(Closed) 1
-[Hr. N. Lockard was the Cognizant ACRS Staff Member for this portion of the meeting.]
The Chairman of the New Member Nominating Subcommittee, Dr.
Lewis, reported the results of his subcommittee meeting.
It-was the recommendation of the subcommittee that nominations be -
forwarded promptly for filling the current vacancy-from names on the current list of nominees and that the Comittee consid-er criteria for filling future vacancies in light of decisions I
to be made on future ACRS activities relative to a new waste management advisory function.
The subcommittee further l
recomended, and Dr. Lewis made the motion, that the Committee 1
1 o
(.-
l 329TH ACRS MEETING MINUTES 18 nominate.two candidates [ names withheld from minutes because of. privacy considerations] for Comission selection to fill the current vacancy. Dr. Remick seconded the motion.
During the ensuing discussion, members, including Dr. Mark, Dr. Steindler, and Dr. Siess, expressed general agreement that 4
action should be taken to fill the current vacancy promptly and that the Committee must give serious consideration to the qualifications of new members to fill the vacancies occurring i
in the next several months,. based on the best information available of future Comittee activities and resources.
Dr.
Lewis added that the alternative is to do nothing and that this is not acceptable.
i The Chairman called for a vote on the motion, and it was passed unanimously. Dr. Lewis then asked members to mark up a l
copy of the current list of nominees to indicate which names should be continued on a revised list and return their mark-ups to ACRS staff members, who will circulate a revised list i
and ask for any additional nominations members wish'to.make, j
3.
FutureLWRDesigns-(0 pen) 1
[ Note:
Mr. R. Major was the Designated Federal Official for this portion of the meeting.]
j The Comittee completed its response to the April 22, 1987 Staff Requirements memorandum.
In its response, the ACRS stated their intention to stay abreast of experience and.of design features overseas and to report their findings to the Commission, as appropriate.
There was also a request that the ACRS:
"... address the feasibility, benefits, and cost effectiveness of selected and combined systems recommended in the Kerr to Chairman Zech letter dated January 15, 1987.
The review should include plant reliability, challenges, complexity, and burden on plant and maintenance personnel."
The Comittee felt that such a study is desirable; however, such a study is beyond the capabilities and resources of the i
ACRS.
The Comittee suggested that such a task was more appropriate for the NRC Staff or a contractor.
The Comittee offered to discuss this matter with the Comission.
Mr. Reed provided additional comments to this letter.
His coments stressed the importance of decay heat removal to reactor safety.
0 4
329TH ACRS MEETING MINUTES 19 4.
Spent Fuel Storage (0 pen)
[ Note:
- 0. S. Merrill was the Designated ~ Federal Official for this portion of the meeting.]
Dr. Chester P. Siess, Chairman of the ACRS Subcommittee on Spent Fuel Storage, led a discussion of the proposed Final Rule Amendments to 10 'CFR Parts 2, 19, 20, 21, 70, 73, 75, 150, and Part 72, " Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive
. Waste." Dr. Siess and other members of the Spent Fuel Subcom-mittee had been provided with a copy of this. document. They were asked to review and comment, or be prepared to coment, on this proposed amendment prior to or 'during this meeting.
Dr. Moeller and Dr. Remick had some questions regarding the document. During the discussion, Dr. Moeller said that he had resolved his questions with C. W. Nilsen of the NRC/RES Staff, principal author of the document. Dr. Remick said that he had also talked with Mr. Nilsen.
Dr. Remick's principal observa-tion was that the amendment did not contain a requirement that operators of equipment and. controls at facilities licensed under Part' 72 be licensed by the NRC, and he felt that they should be.
Mr. Nilsen explained that the NRC Staff requires the operators to be certified by 'the licensee, but NRC regu-i lations do not require them.to be licensed.
The Committee prepared comments on this matter.
I 5.
RegionalPrograms(0 pen)
[ Note:
Mr. P. Boehnert was the Designated Federal Official for this portion of the meeting.]
Dr. Remick, Subcommittee Chairman, reported in the August 28, j
1987 meeting at the Region V Offices.
He said that the 1
Regional Staff was competent, open, and candid and that the meeting was very productive. He noted that this was the first time an ACRS subcommittee meeting had been held at Region V.
Details of the Region's operations were noted.
Region V is the smallest Region, with 102 FTEs.
It has more RIs at their plant sites than is the usual at other U.S. plants. They also admitted there is inconsistency in Regional regulation.
The problems of Rancho Seco were discussed candidly and in detail. -
Region V was in agreement with ACRS vis-a-vis safety con-science at plants.
Plant security problems coming from the i
adversarial relationship between security personnel and other workers were described.
y
,8
'l a
.j 329TH ACRS MEETING ~ MINUTES 20 l
The SALP process.is well thought of by Region V personnel and they believe'it is useful both for the NRC and licensees. The impact of PUC actions.on some plants (in California) was also g
discussed' l
j Overall, the Subcommittee rated the meeting'very productive.
j Mr.. Reed was favorably impressed with Region V personnel.-
The Comittee discussed the problems with Rancho Sec6..
Mr. Hernan noted that the AITs are not considered IITs in tnat the AIT' process is not supposed to draw conclusions; they. are.
fact-finding exercises only.. Mr. Michelson indicated. that.
l this is as it shw1d.be.
i Dr. Remick said he is becoming more enthusiastic over the-usefulness of meetings - with ths ? Regional' offices.
He did' l
suggest that the ACRS consider meeting, as a whole, with a.
Regional office.
i i
6 South Texas Units 1 and 2 (0 pen)
[ Note: Mr. M..El-Zeftawy was.the. Cognizant ACRS Staff Member for this portion of the meeting.]
Dr. Mark, -Subcommittee Chairman,; briefed the, full Comittee d
regarding the status of the South Texas Project (STP), Units 1 and 2.
On June 10, 1986, the'ACRS issued s-letter toLthe:NRC-j Chairman recommending. that the NRC. Staff and the Applicant
(
continue to resolve the open items.
In. addition, as a' result.
of its review and subcommittee meeting..the ACRS reported that 1
if due consideration is given to the three items 1
' environmental qualification of the residual heat removal.
pump for operation inside' containment, resolution of Construction Appraisal Team -(CAT) in-spection findings, rad testing and appropriate corrective measures to assure -
prevention of failures in the fuel oil piping and tubing by induced vibration resulting from extended operation of the diesel generators there is reasonable assurance the STP can be operated at power levels up to 3800 mit without undue risk to the health and a
safety of the public.
1 Since then, the NRC Staff has. issued four supplements ;to its.
original SER, indicating' its satisfaction with the app.11 cant's o
L
L n
s 1
1 329TH ACRS MEETING MINUTES 21 j
- resolution of those items.. On August 21.-1907, the NRC StaffL issued a low' power operating license.
Mr. Reed commented that, in view of the location of the RHR pumps insids containment and of the recent, loss of shutdown-i cooling-events, the Comittee should ask-the. NRC" Staff to verify the capability' of the South Texas. Plant to. avoid air:
binding.of the RHR pumps.
Mr. Ebersole expressed 'some concern regarding two ' items.that =
1 are pertinent to all Westinghouse plants.and suggested that it y
l may be useful to consider " fixes" prior to startup. The first, j
item is the lack of true diverzity of-the control' rod scram holding circuits of'the W design. ' The second. item:is that in i
- the timc interval afteT Post. LOCA 90.
it.. appears - that.W:
designs 'are. permitted to allow a 10-minute' run pump stoppage ij l.
during transfer from :the refueling water tank to the. sump in..
the containment.
Mr. ' Ebersole commented that core damage could occur by_ this loss of flow.
The Comittee decided not to pursue this second concern.
Mr. Michelsor, expressed - some concern regarding. the hazards associated with the transfer and storage ~of fuel. oil;in a rcom i
immediately above each diesel-generator compartment, and cited j
a reportable event (PNO-IV-86-24) in which fuel oil was:
released. Mr. Michelson said that he wanted to know the steps 1
that have been taken to assure that such an event is not likely to occur again, and how to mitigate it if it'did.
The Committee decided to invite the NRC Staff to.its October 1987 meeting. to address all of these concerns. The Committee will then decide whether to ' write a letter 'regarding this issue.
7.
Reactor Doerations (0p7n)
[ Note:
Mr. H. Alderman was the Designated Federal Official I
for this portion of the' meeting.]
The Committes discussed the conduct of the' Recent Operating i
Events meetings. Some of the coments were:
l It was concluded that the periodic discussion of operat-ing events was useful and'that further discussions should-go beyond;recent operatirg events.to include discussions of root causes and NRC and industry actions.
The Committee discussed the consolidation of the Reactor Operations Subcommittee and the Subcommittee on Systemat-.
ic Evaluation of Operating Experience.
Chairman' ' Kerr 9.
A
- e j
l 329TH ACRS MEETING MINUTES 22
~,.
1 j
reminded the Committee that the' Planning Subcommittee had j
. recommended that the two subcommittees be combined, but the Committee voted.against this.
Chairman Kerr recom-1 mended -that this t issue and the procedures _ for: reviewing -
reactor. operating events. should be discussed during the j
scheduled October _ Planning Subcommittee meeting;.
Mr. Reed pointed out thet the Committee' had an obligation to review recent' events.
Mr.. Reed noted that~ the Comit-tee had : approved many plants whose designs were not as-l good as they appeared to be'at the time of-the review'and; j
~
the designs'should now be improved in the light of better~
information. Mr. Reed believes that' operating: experience'.
should: be reviewed in light' of evaluating design adequa--
q cy.
j Mr. Michelson suggested that we should consider 1the implications of : events and develop: conclusions. and recommendations. Mr. Michelson recomended that the' ACRS -
1 give increased attention to AEOD reports and to. NRC and-A Industry follow-up actions' on' operating experience.
Dr. Siess recommended that the. Committee'should look~ at the extent that AEOD reccmendations are followed by the Staff.
Mr. Reed recommended more emphasis on auxiliary feedwater l
and residual heat removal events.
~
8.
International Quality Asgurance (QA) Workshopi(Open) d
[ Note:
E. G.
Igne was the Designated Federal Official ' for thisportionofthemeeting.]
In reply to our letter to Chairman Zech o'f June 10, 1987, pro-posing an international workshop'on QA in design and construc-tion of nuclear Operations (EDO) power plants, V. Stello, Executive ~ Director of
, in his August'~ 7, ~ 1987. lettee, stated that-
. the NRC Staff ~ has implemented several - key initiatives. i.e.,
readiness reviews, integrated Design Inspections (IDIs) and Construction Appraisal Team (CAT) inspections'in assessing the-contribution of licensee QA programs in assuring quality in nuclear power plant design and construction.
-He further L
stated that, because of these initiatives.by the NRC Staff, he felt that we should defer consideration of the. proposed work-shop at this time.
W. Kerr stated that the reasons the' EDO gave for deferring our-proposed international wcrkshop on-QA are $uch that he must
.i 329TH ACRS MEETING MINUTES 23
'I have misinterpreted our June 10, 1987 letter.
The Comittee subsequently approved a letter clarifying this issue, a
9.
Ad Hoc Planning -Subcommittee on Advice on Nuclear Waste Matters (closed)
[ Note:
Dr. S. Parry was the Cognizant ACRS Staff Member for i
this portion of the meeting.]
I Dr. -Moeller summarized the discussions and recommendations from the Ad Hoc Planning Subcommittee's meeting of September 9, 1987. The Subcommittee identified three~ principal alterna-tives for the organization of an advisory group to the Comis-
- sion on nuclear waste affairs.
They were:
- 1) an' entirely separate comittee, 2) - a group, coequal. to but contained within, the administrative structure of the ACRS, and 3) the current subcommittee structure, but with additional resources for waste activities.
The Subcommittee recomended that the best 6pproach for obtaining advice on nuclear waste matters would be to legisla-H tively mandate 'such a group.
Recognizing that that option will require some time to implement, the Subcommittee proposed that during the interim the ACRS would. allocate additional I
resources to the current ACRS Subcommittee on Waste Manage-ment. After discussion, Dr. Moeller agreed to provide a' draft letter incorporating those points fori the full Comittee's consideration.
Dr. Siess said that he would prepare an alternate draft that would be similar in fonnat to that normally found in SECY papers.
- 10. Ad Hoc Group Meeting with Itely's ENEA Technical Comittee (Closed)
[ Note:
Dr. T. McCreless was the Designated Federal Official
)
for this portion of the meeting.)
Dr. Kerr reported that the subject meeting was very success-i ful. He noted that currently all of the. Italian nuclear power plants are shut down. There i.s : however, considerable activi-j ty within ENEA as it prepares for a national referendum on the future of nuclear power in 1thly that is scheduled for this-fall.
Emergency planning is an important consideration and many questions were raised concerning the.10-mile radius emergeitcy evacuation zone in the U.S.
Dr. Kerr said that an Italian reactor design includes enhanced emergency decay heat removal capability, He said that this 1
o
)
)
329TH ACRS MEETING MINUTES 24 was brought about by political considerations and not because of the result of PRAs.
The discussions also included advanced PWR trends, severe i
accidents, training and licensing of personnel, and occupa-tional exposures.
Dr. Remick added that population densities around Italian j
power plants were generally higher than those in the U.S, He said that the Italians seem to be moving toward national emergency planning.
He noted that, while the cost of nuclear power in Italy is high, the cost of coal power is even higher.
B.
Reports, Letters,andMemoranda~~(0 pen)
)
1.
ACRS Coments on Code Scalinq, Applicability and Uncertainty (CSAU) Methodology for Detem' nation of Uncertainty Associated with the Use of Realistic Evaluation Models (Report to Chairman Zech, dated September 16,1987)
The Comittee agreed that the CSAU Methodology offers an acceptable means to estimate uncertainty associated with the use of realistic codes for the calculation of thermal-1 i
hydraulic phenomena as'sociated with loss of coolant accidents but recommended that certain actions be completed before the codes are released.
The Comittee indicated that it intends to follow the progress of this effort and wishes to be kept informed.
J 2.
ACRS Comments on Developments in Emergency Planning (Report to Chairman Zech, dated September 16,19E7)
The Comittee recomended that the NRC Staff conduct an inde-pendent and prompt assessment of the benefits of sheltering as an option in nuclear emergency response.
3.
ACRS Comments Regarding Proposed International Worksho) on Quality in Design and construction of Nuclear Power P' ants (Report to Chairman Zech, dated September 15,1987)
The Committee provided coments regarding the desirability of proceeding with and the scope of such a workshop.
4.
ACRS Action on the Proposed Final Rule Amendments to 10 CFR Part 72, " Licensing Requirements for the Independent Storage of 5 pent Nuclear Fue' and High-Level Radioactive Waste" (Report to Chairman Zech, September 17, 1987)
The Comittee agreed with the NRC Staff's proposal to issue the Final Rule Amendments but stated that it would 'like to
1 c
329TH ACRS MEETING MINUTES 25 have an opportunity to review the gu'idance and criteria used to determine the adequacy of the program for qualifications, training, continuing training and certification of equipment operators at facilities licensed under 10CFR72.
5.
ACRS Coments on Improved Safety for Future Light Water Reactors (Report to Chairman Zech, September 15, 1987)
~ The Comittee, in response to a recent memorandum from the i
Secretary noted that, as requested, it would continue to i
pursue the review of the experience and design features of some European plants, but while the 'Comittee agreed that a study of the feasibility, benefit, and cost effectiveness of systems and combinations of systems recomended in the ACRS
)
letter dated January 15, 1987 is desirable, it is beyond the j
Comittee's capabilities and resources.
I C.
Other Comittee Conclusions-(0 pen) 1.
Steam Generator Tube Ruptures The Comittee agreed that the ACRS Subcommittee on Metal Com-1 ponents should consider steam generator tube ruptures and
)
l their impact on ECCS as noted 1.n a letter from Mr. Dan L.
l Johnson of Southern California Edison Company.
2.
Basdekas' Concerns The Comittee agreed that Mr. D. Basdekas' concerns regarding several USIs should be considered by appropriate ACRS subcom-mittees, namely:
Subcommittee on Instrumentation and Control Systems, Subcommittee on ' B&W Plants, Subcommittee on Metal i
l Components and Subcommittee on Safety Philosophy, Technology, I
and Criteria.
It was also agreed that the Subcommittee on B&W I
Plants would have the lead responsibility in coordinating the overall,ACRS review and response regarding Mr. Basdekas' concerns.
3.
Reorganization of Nuclear Industry Activities The Comittee did not object to the recommendation that a spokesman be invited to a future ACRS meeting to discuss recent reorganizations of nuclear industry activities.
4.
Improved Safety Features Mr. Wylie recomended that the ACRS Subcommittee on Advanced Light Water Reactors continue to review improved safety features of both domestic and foreign nuclear power plants and l
329TH ACRS MEETING MINUTES 26 to report its findings to the ACRS. There was no objection to this recommendation.
5.
Reactor Vendors Mr. Wylie recomended that the ACRS subcommittees on the respective domestic reactor vendors keep the ACRS informed (at a frequency such that the ACRS is kept current) of the pro-gress of the design and of the review of the respective j
advanced light water reactors. There was no objection to this recommendation.
3.
Scope of PRAs for CE Plants The Committee agreed that it was not necessary to meet at this time with re{CE) to discuss the scope of PRAs proposed by CE
{
resentatives from the NRC Staff and Combustion Engineering for standardized plants beyond System 80.
This was in re-sponse to initial concerns raised by Dr. Okrent regarding the scope of this PRA.
7.
Post Accident Releases The Committee did not object to the suggestion that an ACRS Fellow gather information on how post accident releases of radioactivity are used in emergency response.
This informa-tion will provide background for further discussion of a letter to NRC proposed by Dr. Okrent.
8.
Schedule of Meeting Dates for CY 1988 It was agreed that Mr. Fraley will incorporate ch'anges sug-gested during this meeting and will provide a revised set of proposed meeting dates for CY 1988 to the members for their review and approval during the October ACRS meeting.
(See 1
Appendix II for revised set.)
9.
Nominating Panel for ACRS Officers for CY 1988
\\
Members were informed that a nominating panel was being set up.
This Panel consists of Mr. Ward, Chairman, Dr. Shewmon and Mr. Reed, members.
Hoff 1.ockard will support Panel activities.
D.
Future Activities (0 pen) i 1.
Future Acenda l
The Committee agreed on the tentative agenda for the 330th meeting, Octobe* 8-20, 1987 as shown in Appendix III.
329TH ACRS MEETING MINUTES 27 2.
Future Subcomit' tee Activities A schedule of future subcommittee activities was distributed tomembers(AppendixIV).
The 329th ACRS meeting was adjourned at 10:15 a.m. on Saturday,: Septem-ber 12, 1987.
-a p
e t
5 4
a i
&f$-9dcRf
.i APPENDICES TO MINUTES OF THE 329TH ACRS MEETING SEPTEMBER 10-12,'1987-i
~ WASHINGTON, D.C.
I.
List of Attendees l
II.
Schedule of Meeting Dates for CY 1988 III.
Future Agenda l
IV.
Future Subcommittee Activities V.
Other Documents Received
.l l
a l
l i
i l
i
1 j
1 330 331 332 333 334 335 336-337 338 ACRS MEETING f
DATE b 10 1(987 4
ATTENDEES Thursday Friday Saturday i
Dr. William Kerr, Chairman 7
I V
Dr. Forrest J. Remick, Vice Chairman Mr. Jesse C. Ebersole V
V w
[
r h
Dr. Harold W. Lewis 1
Dr. Carson Mark
/
t-i-
/
V' L-Mr. Carlyle Michelson
/
/"
Mc Dr. Dade W. Moeller
/
/
fdo.
Dr. David Okrent V
V' v
l Mr. Glenn A. Reed Dr. Paul G. Shewmon O
Dr. Chester P. Siess
/
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Dr. Martin J. Steindler
/
V Mr. David A. Ward V
d6 Ro-Mr. Charles J. Wylie
/
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I
ATTENDEES 329TH ACRS MEETING 1
l SEPTEMBER 10-12, 1987
)
i WASHINGTON, D.C.
1 THURSDAY, SEPTEMBER 10, 1987 i
NRC ATTENDEES R. Hernan, NRR l
Tom McKenna, NRR I
F. Skopec, NRR D. B. Matthews, NRR l
E. M. Podolak, NRR PUBLIC ATTENDEES Irwin Coffenberry, Heritage Reporting Co.
Kim Arn, SERCH Licensing S. P. Kalm, EPRI R. Copeland, ANF D. Adkisson, ANF A. Emerson, Heritage Reporting Co.
C. K. Lewe, NUS Michael Rathje, Doc-Search Leroy Hefley, Heritage Reporting Herschel Specter, New York Powr Authority Lynn Ritchie, Sandia National Labs.
Frank Rowsome, IEA Dale Kardos, IEAL Johnathan E. Carter, Bishop, Cook et al.
Mark Phillis, Bishop, Cook et al.
Edwin M. Good, Florida Power Corp.
L. Connor, DSA H. M. Fontecilla, Virginia Power R. James - Heasing 2-b I
o l
ATTENDEES 329TH ACRS MEETING SEPTEMBER 10-12,~1987
'l FRIDAY, SEPTEMBER 11 ~,.1987 1
NRC ATTENDEES R. W. Hernan, NRR David Tiktinsky, NMSS John Buckley, NMSS l
l PUBLIC ATTENDEES Irwin Coffenberry, Heritage Reporting Corp.
John Trotter, NUS David H. Bjorkbom, Serch Licensing, Bechtel A. Emerson, Heritage Reporting Corp.
Victor Frank, SPPT C. Ruth Kempf, BNL P. Soo, BNL John Richardson, WESTON/UCofC Paula Wade, SAIC Lynn Casnor, DSA Frank Rowsome, IEA j
David Fox,. Associated Press d
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APPENDIX III FUTURE AGENDA October 8-10, 1987 j
USI A-44, Station Blackout (CJW/MME)
Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> -
Discuss the proposed resolution of ACRS coninents dated June 9, 1987, and to hear a status report of NUMARC activities concerning
- tation blackout.
Integrated Safety Assessment Program (DAW /MDH)
Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> - Discuss.the NRC Staff plan for. implementing this Program and consideration given to ACRS comments dated July 15, 1987.
Seismic Qualification of Equipment (CJW/RKM)
Estimated time = li
)
hours - Briefing by NRC Staff and Seismic Qualification Utility Group on seismic walk-through of the Zion Nuclear Station.
Zion Full Field Exercise (DWM/CYM/EGI)
Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> -
Briefing by NRC Staff (AE00) on a simulated fuel failure at the i
Zion Nuclear Power Plant.
Advice on Nuclear Waste Matters (DWM/JSP)
Estimated time = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- Continue the discussion of alternate methods for the NRC to obtain advice on nuclear waste matters.
TVA Management and the Proposed Restart of Sequoyah Nuclear Plant I
(CJW/RPS)
Estimated time = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> - Discuss the proposed TVA Nuclear Management Reorganization Plan and the. restart of Sequoyah.
OperatingIncidentsandEvents(JCE/HA) Estimated time = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -
I Discuss, as appropriate, recent nuclear power plant transients, incidents and events.
Use of PRA in Regulation (WK/HDH)
Estimated time = If hours -
l Discuss August 6 reply of the ED0 to ACRS report dated July 15 on NUREG-1150.
Regulatory Guide 1.99, Rev. 2, Radiation Embrittlement of Reactor Yessel Material (PG5/EGI)
Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> - Discuss the proposed revision to this regulatory guide.
Advanced LWR Design (CJW/HA)
Estimated time = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> - Discuss the NRC Staff SER regarding Chapter 1 of the EPRI Advanced LWR Requirements document.
Generic Issue 124, Auxiliary Feedwater System Reliability (DAW /PAB)
Estimated time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> - Discuss requirements for auxiliary
=
feedwater system reliability.
Waste Management Research (DWM/0SM)
Estimated time = 1) hours -
Discuss NRC research program on waste management.
l l
u_________
j i
l 1
329TH ACRS MEETING l
Meeting with the Commissioners (WK/RFF) Estimated time = 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -
Discuss topics of mutual interest including advice regarding nuclear waste matters.
l Appointment of'New ACRS Members (HWL/NSL)
Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- Discuss qualifications of candidates proposed as nominees for i
appointment to the Committee.
Implications of Chernobyl Accident (DAW /MDH)
Estimated time = 3/4 hours - Discuss proposed NRC Staff implementation of ACRS recommen-dations in its report of January 15, 1987.
Reorganization of Nuclear Industry Activities (FJR/RFF)
Estimated Briefing by representatives of the nuclear time = li hours industry regarding reorganization and realignment of responsibil-ities among industry groups to achieve operational excellence, improve the interface with NRC, and effectively address the full spectrum of unresolved generic safety issues.
i I
ACRS Subcommittee Reports l
l Thermal Hydraulic Phenomena - Report on steam generator over-l fill (GI-135), new LOCA scenario, and water hammer.
(DAW /PAB) Estimated time = 3/4 hour 3
Decay Heat Removal Sy(DAW /PAB) port on GI-A-23, Reactor Coolan stem - Re Pump Seal Failure.
Estimated time = i hour I
i Regulatory Policies and Practices - Report on the regulatory process (HWL/GRQ) Estimated time - i hour Auxiliary Systems - Report on HVAC, instrument air and chilled water systems.
(CYM/SD) Estimated time = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Extreme External Phenomena - Report on PWR seismic design margins.
(CPS /RPS) Estimated time = i hour Future ACRS Activities (WK/RFF)
Estimated time = i hour - Discuss anticipated ACR5 subcommittee activity and items proposed for consideration by the full Committee.
November 5-7, 1987 Renewal of Nuclear Power Plant Licenses (CJW/RKM) - Discuss the proposed NRC policy regarding the extension of nuclear power plant licenses beyond 40 years.
Technical Specifications (CYM/EGI) - Review proposed improvements in nuclear power plant technical specifications.
l III-2
j 329TH'ACRS MEETING' USDI A-47 Safety Implications of Control-Systems (JCE/MME)
Discuss the resolution of A-47 for B&W nuclear plants.
Meeting with Director of RES - Discuss items of mutual interest.
l Subcommittee Reports Systematic Evaluation of Operating Experience report on the impact of AE0D activities on the regulatory process.
December 3-5, 1987 1
1 Advanced Reactor Review (DAW /MME) - Discuss key issues associated -
with advanced reactors.
l USI' A-47, Systems Interactions in Nuclear Power Plants - Discuss 1
proposed resolution of A-17.
i i
l j
III-3 1
o l
l ACRS SUBCOMMITTEE MEETINGS i
Extreme E$ternal Phenomena, September 29, 1987, 1717 H Street, NW, Washing-ton, DC (Savio), 9:00 A.M., Room 1046. The Subcommittee will discuss the NRC Staff's Seismic Design Margins Program and the application of the methodology to Maine Yankee. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of September 28:
Dr. Siess ANTHONY Mr. Wylie DAYS INN Generic Items, September 30, 1987, 1717 H Street, NW, Washington, DC
)
(Duraiswamy), 8:30 A.M., Room 1046. The Subcommittee will continue the i
discussion on the effectiveness of the programs that address generic j
issues and USIs. Also, it will discuss with selected licensees the contri-bution to plant safety resulting from the implementation of the resolved generic issues and USIs. Attendance by the following is anticipated, and j
reservations have been made at the hotels. indicated for the night of September 29:
Dr. Siess ANTHONY Mr. Michelson DAYS INN I
Mr. Ebersole DAYS INN Mr. Wylie -
DAYS INN Auxiliary Systems, October 1, 1987, 1717 H Street, NW, Washington, DC (Duraiswamy), 8:30 A.M., Room 1046. The Subcommittee will discuss the following:
(1) heating, ventilating,andairconditioning(HVAC) system malfunctions and their impact on safety systems and (2) problems associated with instrument air systems, AEOD findings on instrument air system mal-functions and its recommendations to alleviate this problem. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of September 30:
Mr. Michelson DAYS INN Mr. Reed DAYS INN Mr. Ebersole DAYS INN Mr. Wylie DAYS INN Dr. Moeller LOMBARDY TVA Organizational Issues, October 2,1987, War,hington, DC has been de-ferred.
Standardization of Nuclear Facilities, October 6, 1987, 1717 H Street, NW, Washington, DC (Alderman), 8:30 A.M., Room 1046. The Subcommittee will review the Staff SER and Chapter I of the EPRI Requirements document.
Attendance by the following is anticipated, and reservations have been made at the hotels indicated for the night of October 5:
Mr. Wylie DAYS INN Mr. Reed DAYS INN Mr. Michelson DAYS INN Dr. Siess ANTHONY APPENDIX IV
R i
Safety PMiosophy, Technology, and Criteria, October-7, 1987, 1717 h Street, NW, Washington, DC (Savio/ Houston), 6:00 P.M., Room 1046. The Subcommittee will meet with the NRC Staff and' discuss their plans for incorporating the ACRS recommendations on Safety Goal Policy implementation into the Policy implementation plan. Attendance by the following is anticipated, and reservations have been made at the hotels indicated for i
the night of October 6:
1 l
Dr. Okrent (AR 10/7) ANTHONY Dr. Remick NONE Dr. Kerr (tent.)
LOMBARDY Dr. Siess (tent.)
ANTHONY Dr. Lewis (tent.)
HYATT Mr. Ward NONE Mr. Michelson DAYS INN Mr. Wylie DAYS INN 330th ACRS Meeting, October 8-10, 1987, Washington, DC, Room 1046.
i Instrumentation and Control Systems, October 14, 1987, 1717 H Street, NW, Washington, DC (El-Zeftawy), 8:30 A.M., Room 1046. The Subcommittee will discuss the NRC's proposed final resolution of USI A-47, " Safety Implica-tions of Control Systems."
In addition, the Subcommittee will discuss and l
consider the comments by Mr. Basdekas regarding the resolution of this USI.
Attendance by the following is anticipated, and reservations have been made j
at the hotels indicated for the night of October 13:
')
Mr. Ebersole DAYS INN Mr. Michelson DAYS INN l
Dr. Kerr LOMBARDY Mr. Reed DAYS INN Dr. Lewis HYATT Mr. Wylie DAYS INN Waste Management, October 15 and 16,1987,1717 H Street, NW,' Washington, DC (Merrill), 8:30 A.M., Room 1046. The Subcommittee will review pertinent TiEW, LLW, and associated research topics to be determined at an agenda planning session with NMSS and RES staffs on September 23, 1987. Atten-dance by the following is anticipated, and reservations have been made at the hotels indicated for the nights of October 14 and 15:
Dr. Moeller LOMBARDY Dr. Shewmon NONE Dr. Mark LOMBARDY Dr. Steindler NONE Dr. Remick NONE Joint Scram Systems Reliability and Core Performance, October 28, 1987, 1717 H Street, NW, Washington, DC (Boehnert/ Houston), 8:30 A.M., Room 1046.
The Subcommittees will review the current status of LWR plant operations (core reload designs, etc.) as they impact on core reactivity control operational limits (e.g. moderator temperature coefficients in general, and ATWS analyses in particular). Attendance by the following is anticipated:
Dr. Kerr Mr. Reed Mr. Ebersole Dr. Shewmon Dr. Lewis Mr. Ward Dr. Mark Dr. Lee IV-2
' Systematic Assessment of Operating Experience, November 3, 1987, 1717 H
)
Street, NW, Washington, DC (Major), 1:00 P.M., Room 1046. The Subcommittee 1
will discuss AE0D's role in helping the NRC learn from operating experience.
Lodging will be announced later. Attendance by the following is anticipated:
Dr. Lewis Mr. Michelson Mr. Ebersole Mr. Ward 331st ACRS Meeting, November 5-7, 1987, Washington, DC, Room 1046.
1 Maintenance Practices and Procedures, November 12, 1987, 1717 H Street, NW, Washington, DC (Alderman), 1:30 P.M., Room 1046. The Subcommittee will'be l
briefed and will discuss the proposed Policy Statement on Maintenance of l
Nuclear Power Plants.
Lodging will be announced later. Attendance by the l
following is anticipated:
Mr. Reed Dr. Moeller Mr. Ebersole Mr. Wylie Mr. Michelson Quality and Quality Assurance in Design and Construction, November 23 or 24, 1967, 1717 H Street, NW, Washington, DC (Igne), 8:30 A.M., Room 1046.
The Subcommittee will review QA Experience in Readiness Reviews as applied to nuclear power plants, with a view toward possible application to HLW geologic repositories and monitored retrievable storage (MRS) facilities.
Lodging will be announced later.
Attendance by the following is antici-pated:
1 Mr. Reed Dr. Siess i
Dr. Moeller Mr. Wylie Dr. Remick 332nd ACRS Meeting, December 3-5, 1987, Washington, DC, Room 1046.
Thermal Hydraulic Phenomena, Date to be determined (October), Washington, DC (Boehnert).
The Subcommittee will review: (1) the final version of revised ECCS Rule, and (2) the status of the RES thermal hydraulic research I
program. Attendance by the following is anticipated:
l Mr. Michelson Dr. Catton 1
Mr. Ebersole Dr. Schrock l
Dr. Kerr Mr. Sullivan Mr. Ward Dr. Tien Mr. Wylie IV-3 i
W___________
. TVA Orgardzational Issues, Date to be determined (October), Washington, DC (Savio). The Subcommittee will review the safety issues associated with TVA management reorganization and the Sequoyah restart. Attendance by the following is anticipated:
Mr. Wylie Mr. Reed Mr. Ebersole Mr. Ward I
Mr. Michelson Dr. Remick Severe Accidents, Date to be determined (October / November) (tentative),
Washington, DC (Houston). The Subcommittee will review the final version of the NRC Staff's proposed generic letter on Individual Plant Examinations (IPEs). Attendance by the following is anticipated:
Dr. Kerr Dr. Shewmon l
Dr. Mark Dr. Siess l
Dr. Okrent Mr. Ward DecayHeatRemovalSystems,'Datetobedetermined(October), Washington,DC (Boehnert).
The Subcommittee will continue its review of the NRR Resolu-tion Position for USI A-45.
Attendance by the following is anticipated:
l Mr. Ward Mr. Wylie Mr. Ebersole Dr. Catton Mr. Michelson Mr. Davis Mr. Reed l
Containment Requirements, Date to be determined (October / November),
Washington, DC (Houston). The Subcommittee will review the hydrogen control measures for BWRs and Ice Condenser PWRs (USI A-48). May also involve EPGs for BWRs. Attendance by the following is anticipated:
Dr. Mark Dr. Okrent (tent.)
Mr. Ebertole Dr. Siess Dr. Kerr Mr. Wylie Metal Components, Date to be determined (October / November), Charlotte, NC (Igne). The SuEcomittee will review the status of the NDE of cast stain-less steel piping. Attendance by the following is anticipated:
l Dr. Shewmon Mr. Ward Dr. Lewis Mr. Rodabaugh Mr. Michelson Dr. B. Thompson IV-4
.. s
.r 4
Advanced Beactor Designs, Date to be determined (November), Washington,' DC, (El-Zeftawy).. The Subcommittee will review and. comment on the draft Commission paper that will be prepared by the NRC Staff regarding the severe accidents and containment issues for the DOE-sponsored advanced reactor designs. Attendance by the following is anticipated:
Mr. Ward Mr. Michelson Mr. Ebersole Dr. Okrent Dr. Kerr Dr. Siess Dr. Mark Mr. Wylie Containment Requirements, Date to be determined (November / December),
Washington, DC (Houston). The Subcommittee will review the proposed Containment Performance / Improvement Program Plan. The Plan is in three parts: (1)ImprovedplantoperationsincludingE0Ps,(2) Severe' accident vulnerabilities via IPEs and (3) Containment performance in the event of-a severe accident. Attendance by the following is anticipated:
Dr. Mark Dr. Siess Mr. Ebersole Mr. Wylie Dr. Kerr l
Diablo Canyon, Date to be determined (late November /early December),
Location to be determined (Igne). The Subcommittee will review the status of the Diablo Canyon Long-Term Seismic Program. ' Attendance by the follow-ing is anticipated:
Dr. Siess Dr. Page Mr. Ebersole Dr. Maxwell i
Dr. Kerr Dr. G. Thcmpson j
Dr. Lewis Dr. Trifunac Dr. Moeller Dr. Scavuzzo i
Combustion Engineering Reactor Plants, Date to be determined (November /
Decembst), Washington, DC (Houston). The Subcommittee will initiate its reviewofCESSAR-Plus(CE'sAdvancedLWRforthe1990's). Attendance by the following is anticipated J
Dr. Remick Mr. Reed (tent.)
Dr. Lewis Mr. Wylie Mr. Michelson IV-5
)
I r
l \\
l
-)
l Babcock &-Wilcox Reactor Plants, Date to be determined (November / December),
l Washington, DC (Major). The Subcommittee.Will continue its review of the j
long-term safety review of B&W reactors. This effort was begun during-the-l summer of 1986; initial Committee comments offered on July 16, 1986 in a l
1etter to V. Stello, EDO.. Attendance by the following is anticipated:
Mr. Wylie Mr. Michelson Mr. Ebersole Mr. Reed i
Dr. Kerr Mr. Ward Dr. Lewis 1
Structural Engineering, Date to be determined (late November. or January' 1988), Albuquerque, NM (Ignc). The Subcommittee will review the results i
of the model concrete containment test. Attendance by the following is anticipated:
i Dr. Siess Mr. Bender l
Mr. Ebersole Dr. Pickel Dr. Shewmon Mr. Rodabaugh Westinghouse Reactor Plants, Date to be determined (December / January 1988),
Lashington, DC (El-Zeftawy). The Subcommittee will discuss and hear presentations from Westinghouse representatives regarding the important designfeaturesandobjectivesofWAPWR(RESARSP/90)andtheAP600 I
designs. Attendance by the following is anticipated:
Mr. Ward Mr. Reed (tent.)
Mr. Ebersole Dr. Shewmon Dr. Kerr Mr. Wylie Mr. Michelson Auxiliary Systems, Date to be determined (January, tentative), Washington, 1
DC The Subcommittee will discuss:
(1)criteriabeingused Ey u(Duraiswamy).tilities to design Chilled Water System, (2) regulatory requiremen for Chilled Water System Design, and (3) criteria being used by the NRC Staff to review the Chilled Water System design. To facilitate this discussion, some members of the Subcommittee will tour the Shearon Harris plant to look at the Chilled Water System design at that plant. Attendance by the following is anticipated:
1 Mr. Michelson Dr. Moeller Mr. Ebersole Mr. Wylie Containment Requirements, Date to be determined (April 1988), Washington, DC (Houston). The Subcommittee will review the NRC Staff's document on containment performance and improvements (all containment types).
Attendance by the following is anticipated:
Dr. Mark (tent.)
Dr. Siess l
Mr. Ebersole Mr. _ Wyli e Dr. Kerr IV-6
j Y
I APPENDIX V l
MINUTES OF THE
]
329TH ACRS MEETING SEPTEMBER 10-12, 1987 OTHER DOCUMENTS RECEIVED 1.
Project Status Report - Review of NRC Best Estimate Thermal I
Hydraulic Code Uncertainty Methodology 2.
Memo for P. Boehnert from Ivan Catton,
Subject:
Experts' Meeting on Code Uncertainty Quantification dated 3/21/87 3.
Memo for C. Michelson from P. Boehnert,
Subject:
ACRS Consultant
- 1. Catton's Report:
"Ad Hoc Meeting on the Availability of Data i
Needed for Scaling LB LOCA" Jan. 6-7, 1987, Rockville, MD, dated I
2/13/87 i
4.
Memo for C. Michelson from P. Boehnert,
Subject:
I. Catton's Report on NRC-RES Meeting to Address the Scaling Capability of NRC's Advanced T/H Codes, dated 12/8/86 5.
Memo for C. Michelson from Virgil Schrock, Re: Comments on subjects covered at August 4 Thennal Hydraulics Subcommittee i
Meeting, dated 8/13/87 6.
Excerpt from Minutes of Thermal Hydraulics Phenomena Subcommittee April 28-29, 1987 Meeting (pp.18-21) 7.
Excerpt from Minutes of Thermal Hydraulics Phenomena Subcommittee August 4,1987 Meeting (pp.12-13) 8.
Excerpt from " Compendium of ECCS Research for Realistic LOCA Analysis," NUREG-1230 (pp. 4-102 to 4-140) 9.
Project Status Report - Committee Discussion on Emergency Planning
- 10. Minutes of Meeting of June 22-23, 1987 of Subcommittee on Occupational and Environmental Protection Systems
- 11. Background Information on Graded Response j
- 12. Project Status Report - Auxiliary Feedwater Systems Generic Issues
- 13. Excerpt from RES Report on Resolution of GI-93 (Memo for T. Murley from E. Beckjord,
Subject:
Arkansas Nuclear One, Unit 2 -
Resolution of GI-124, Auxiliary Feedwater System Reliability, dated 7/13/87) l l-
- 14. Excerpt from RES Report on Resolution of GI-93 l
329TH ACRS MEETING MINUTES
.V-2
- 15. Minutes of Meeting of. August 5, 1987 of the Subcommittee on Decay.
Heat Removal Systems
- 16. Memo for ACRS Members from R. Fraley
Subject:
Meeting with I
Director, NRR Dur_ing 329th ACRS Meeting - September 10-12,.1987, dated 9/3/87
- 17. Project Status Report - Subcommittee on Waste Management re Nuclear H
Waste Management and Disposal
- 18. ACRS Subcommittee Meeting List j
- 19. Project Status on Spent Fuel Storage including statement of purpose and ACRS actions required
- 20. Memo for C. P. Siess from 0. S. Merrill','
Subject:
" Final Rule l
Amendments to 10 CFR Part 72 (and other parts), titled, " Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-level Radioactive Waste, dated 8/24/87 l
- 21. Project Status Report on Trojan Pipe Wall Thinning l
- 22. NRC Informati_on Notice No. 87-36, Significant Unexpected Erosion of i-Feedwater Lines, dated 8/4/87 1
- 23. Project Status Report on Future LWR Designs l
- 24. Staff Requirements Memo for R. Fraley from John Hoyle,
Subject:
Staff Requirements - Periodic Meeting yith Advisory Committee on Reactor Safeguards (ACRS),10:00 A.M., Friday, April 10, 1987, Commissioners' Conference Room,' D.C. Office (0 pen to Public l
Attendance), dated 4/22/87
- 25. Project Status Report on Regional Programs
- 26. Minutes of August 28, 1987 Meeting of Subcommittee on Regional Programs
- 27. Project Status Report on International Workshop on Quality in Design and Construction of Nuclear Power Plants
- 28. Memo for W. Kerr from V. Stello,
Subject:
Proposed International Workshop on Quality in Design and Construction of Nuclear Power Plants, undated but received 8/7/87
a 329TH ACRS MEETING MINUTES V-3 Presentations Vu-Graphs NRC Staff, L. Shotkin Overvoew pf ECCS Review Package NRC Staff, N. Zuber - Code scaling, Applicability and Uncertainty 1
(CSAU) Evaluation Methodology l
ACRS Consultant Ivan Catton, Comments on 10CFR50.64 requirements Frank Rowesone, Oak Ridge Associated Universities, Perspectives on Emergency Preparedness Based Upon PRA (with WASH-140D Source Terms)
NRC Staff, S. Diab, Auxiliary Feedwater System Reliability, Generic Issue No. 124 NRC Staff, G. R. Mazetis, Resolution of GI-93, " Steam Binding of AFW Pumps" NRC Staff, Thomas Murley, NRR Items of Interest to ACRS NRC Staff, Sealing of Boreholes and Shafts NRC Staff, Solidification of Decontamination LLW l
NRC Staff, Peer Review of Research Work EG&G, Parts 1 and 2 Characterization of LL Radioactive i
Decontamination Waste BNL, C. Ruth Kempf, Review of Decontamination Waste Research Programs at Brookhaven National Laboratory Others Letter to T. Murley from Frank Rowsome, Oak Ridge Associated Universities, dated 7/28/87 Handouts 1.
Meno to ACRS Members from Dean Houston,
Subject:
Potential Items for Discussion with Dr. T. Murley, Director, NRR, dated 9/4/87 2.
Minutes of Meeting of August 25-26, 1987 of Subcommittee on Advanced Reactors 3.
Memo for J. C. Mark from Medhat El-Zeftawy,
Subject:
Status of ACRS Items on South Texas, dated 8/21/87 1
l 329TH ACRS MEETING MINUTES V-4 1
4.
Memo for F. Remick from P. Boehnert,
Subject:
Regional Operations' '
Subcommittee Meeting - Region V Offices. August 28, 1987 -
Follow-Up Comments, dated 9/9/87.
1 5.
Memo for J. Ebersole et al. from Mednat El-Zeftawy,
Subject:
Relationship of the B&W Plant Reassessment to' Unresolved Safety Issues A-46/49/17, dated 9/2/87 4
6.
Memo for P. Boehnert from I. Catton,
Subject:
Third Meeting of the'.
. Technical Program Group on Code Uncertainty _Quantification, August 19-20, 1987, Rockville, MD, dated 8/30/87 8.
Future Activities
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