View source for IA-88-470, Trip Rept of 880620 Visit to State of Sc Dept of Health & Environ Control Re Silling Rept on high-density Polyethylene Integrity Containers.List of Attendees Encl

{{Adams
| number = ML20196K576
| issue date = 06/28/1988
| title = Trip Rept of 880620 Visit to State of Sc Dept of Health & Environ Control Re Silling Rept on high-density Polyethylene Integrity Containers.List of Attendees Encl
| author name = Tokar M
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY &amp; SAFEGUARDS (NMSS)
| addressee name = Surmeier J
| addressee affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY &amp; SAFEGUARDS (NMSS)
| docket = 
| license number = 
| contact person = 
| case reference number = FOIA-88-470
| document report number = NUDOCS 8807070038
| package number = ML20151C617
| document type = MEETING MINUTES &amp; NOTES--CORRESPONDENCE, TRIP REPORTS
| page count = 31
}}

=Text=
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MT/SC DHEC TRIP REPCRT MEMORANDUH FOR:       John J. Surmeier, Chief Technical Branch Division of low-Level Waste Management and Decomissioning FROM:                Michael Tokar, Section Leader Technical Branch Division of Lo .evel Waste Managecent and Decomissioning

==SUBJECT:==
SC DHEC TRIP REPORT l'
On June 20, 1968, John Greeves, Kathleen Schneider and I from headquarters and Robert Trojanowski from Region !!, visited Virgil Autry Heyward Shealy and members of their staff at the offices of the South Carolina Department of Health and Environ # rental Control (DHEC) in Columbia, South Carolina. The purpose of the visit was to discuss Professor Stewart Silling's report on                :
high-density polyethylene (HDPE), high integrity containers (HIC's). The meeting agenda list of attendees are attached.
As indicated by the agenda, we held a technical discussion concerning 51111ng's major findings and conclusions. We also requested that SC provide any coments they may have on the reoort for our consideration and discussed the status and future plans for the kRC review of HDPE HIC topical reports. We advised DHEC that we expect to make a decision on these topical reports late this sumer. We also advf. 9d DHEC of the Advisory Comittee on Nuclear Waste Meeting on June 27-28, and suggested that they attend. Also discussed were
(,   some of DHEC's concerns regarding the HDPE HIC's already buried at Barnwell and potential future actions concerning further receipt of HDPE HIC's at the                 ;
Strnwell disposal site.                                            .                     f DHEC expressed appre:iation for the meeting and seemed satisfied with the information that was conveyed.
p Michael Tokar, Section Leader Techn'   1 Branch Division of low Level Waste Management    l and Decomissioning                      ;
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MEETING ATTENDEES
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Je$n T. Gree.          NRC/LLWH      301-492-3344 !
Michael Tokar          NRC/LLTB      301-492-0590 Kathleen Schneider     NRC/SLITP     301-492-0320 !
I                                 Bob Trojanowski                      404-331-5597 NRC/RI!                    l Heyeard A. Shealy                    803-734-4634 :
SC/DHEC i                                                                                                    t Yirgil R. Autry SC/DF.O       803-734-4633 Pearce O'K611ey        SC/DHEC       803-734-4700 ,
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i EFRCTS OF CEMICAL AND GAMA IRRADIATION ENVIR0MENTS ON TE ECHANICAL PROKRTIES OF HIGH-DENSITY POLYETHYLEE (HDPE)
Fr N No.
P. S00                   3D J. CLINTON PROGRAM REVIEW AT NRC
                                                                                 "          "b JUNE 23, 1988            LG~
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SCOPE OF RESEARCH TO IDENTIFY DEGRADATlW MODES FOR VARI 0llS CHEMICAL AND IRRADIATION ENVIRONMENTS THESE INCLUDE:
e   AIR, DlW                   ^'       d e   IGEPAL CO - 630                              '
(ASTM TEST SURFACTANT) e   TllRBINE OIL (POSS. LLW CONTAMINANT) e    SCINTILLATION FLUID (POSS. LLW CONTAMINANT) y                   e    GAMMA RADIATION Y    j ON Tf c.re w M v
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TYPES OF M6CHANICAL TESTS ON HDPE 1   STATIC ll-BEND
              - SIMPLE, INEXPENSIVE, VERSATILE SCOPING TEST 2   DYNAMIC CREEP-RUPTURE
              - QUANTITATIVELY COMPARES                                   '
CREEP RATES, FAILURE TIMES, DUCTILITIES FOR DIFFERENT ENVIRONMENTS i
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TYPE 1     -    THE AS-RECEIVED OXIDIZED CONDITION, WHICH WILL HAVE ' NATURAL" CRACKS PRESENT, AS A RESULT OF BENDING, TYPE II    -
AS AB0VE, BUT WITH 10 MILS OF THE OXIDIZED SURFACE REMOVED WITH SANDPAPER PRIOR TO BENDING, AND TYPE III   -
THE AS-RECEIVED 'NON-0XIDIZED' SURFACE WHICH DOES NOT CRACK Duf.ING THE BENDING PROCESS. \
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0                 90              13             0                  0 7 5 x 10'              97               3             2                  1 (AT 1 4 x 10' R/H) f 0 x 10'              95               4             2                  4 (Ar 8 4 x 10' R/u) 1 3 x 10'              82               4             0                  1 5
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CRACK LOCATION AND DEPTH FOR TYPE I SPECIMENS e  SMALL CRACK MORE EASILY INITIATED IN llNIRRADIATED SPECIMENS e  CRACKS PROPAGATE MOST EASILY AT INTERMEDIATE GAMMA IRRADIATION RATES e CRACKS PROPAGATE MOST EASILY AT INTERMEDIATE STRESS LEVELS l'
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: f. RACK LOCATION AND DEPTH FOR TYPE _11.
AND TYPE III SPECIMENS e CRACK INITIATION F0llND RECENTLY IN TYPE 11 AND III U-BENDS (DOSE 6 0 x 10 7 RADS) e  CRACKING LESS PRONOUNCED IN TYPE 11 SPECIMENS J
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Q EEP-RilPTilRE TESTS ON HDPE
        'dASIC DATA NEEDS FOR ANALYZING CREEP                         -
DEFORMATION IN HIC'S INCLUDE:
e   CREEP STRAIN (ELONGATIOW) WITH TIME e   CREEP FAILURE TIME TEST VARIABLES INCLUDE:
e   SPECIMEN SilRFACE PREPARATION e   APPLIED STRESS e   TEST ENVIRONMENT 4
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OBSERVATIONS ON CREEP IN HDPE e  CRACKS FORM EARLY IN OXIDIZED LAYER GIVING CONCENTRATED DEFORMATION.
e  REMOVAL OF OXIDIZED MATERIAL PREVENTS EARLY CRACKING AND CAUSES MAJOR INCREASES IN DIICTILITY AND CREEP LIFE.
e  AT THE' HIGHEST STRESSES, DUCTILITIES ARE ESSENTIALLY INDEPENDENT OF ENVIRONMENT.
e  TURBINE OIL AND IGEPAL CAllSE ENVIRONMENTAL STRESS CRACKING AT LOW AND INTERMEDIATE STRESSES.
e  SCINTILLATION FLUID CAUSES HIGH DUCTILITY AT INTERMEDIATE STRESSES. MORE BRITTLE BEHAVIOR AT LOWER STRESSES.
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e CONCLUSIONS 1 TENSILE STRESSES, OXYGEN AND GAMMA-IRRADIATION ENC 0URAGE CRACK INITIATION AND PROPAGATION IN HDPE.
INTERMEDIATE STRESSES AND DOSE RATES ARE MOST DETRIMENTAL.
2 SCINTILLATION FLUIDS INCREASE CREEP RATE AND CAUSE VERY EARLY FAILURE BECAUSE OF ' SURFACE SOFTENING" EFFECTS.
3 OIL AND SURFACTANTS CAUSE EARLY FAILURE DUE TO ENVIRONMENTAL STRESS CRACKING.
4 REMOVAL OF OXIDIZED SURFACE MATERIAL CAN GREATLY INCREASE FAILURE TIME BY AVOIDING CONCENTRATED
.             DEFORMATION AT CRACKED REGIONS.
5 GAMMA IRRADIATION WILL ENCOURAGE CRACK INITIATION /
PROPAGATION. HOWEVER, AT HIGH DOSE RATES, STRESS RELAXATION AND CHEMICAL CHANGES REDUCE THE EFFECT.
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Q IRRADIATION - CRFFP IN HDPE e RESEARCH INITIATED TG CECK ON APPARANT IKONSISTEEIES IN TWO PRIOR PROGRAMS.
e OE SHOWED THAT IN-TEST 1RRADif,T10N IEREASED CREEP RATE COPFARED TO lElRRADIATED HDPE.        TE OTER SHOWED IT RETARDCD CREEP.
e IT WAS HYPOTESIZED THAT TE TWO FINDINGS COULD BE RATIONALIZEDIF:
A) HIGHER STRESS AND LOWER DOSE RATES lEREASED CREEP RATE; AND                                                                     ,
B) LOWER STRESS AND HIGHER DOSE RATES RETARDED CREEP.
e EW TESTS EEllfASS TE C&PLETE RANGES OF STRESS AND 00SE RATES OF TE TWO PRIOR PROGRAMS.
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FINDINGS TO DATE ON LOWER DOSE RATE IRRAD13T10N CRFFP TESTS 8
AT A DOSE RATE OF 5 x 10 RAD /HR :
A)  1RRADIAT10N DECREASES CREEP RATE C& PARED TO UNIRRADIATED C0llTROLS AT STRESSES N TVEEN 1500 - 1825 PSis B)  1RRADIATION AT H!GHER STRESSES INCREASES FAILURE Tite AND ELOUGATION. POSSIBLY SNE AT LOWER STRESSES ALS0; C) THIS BENEFICIAL EFFECT OF G#f% IRRADIATION C0llTRADICTS DOUGHERTY'S EARLIEH STUDY.
TESis WILL SHORTLY, START ON HIGHER DOSE RATE CREEP (3 x 10' RAD /HR.).
e BROOKHAVEN Nail 0NAL LABORATORY l} lj l ASSOCIATED UNIVERSITIES, INC. (1 ll l

9
                                                                                                              .SlGGESTIONS FOR RJTURE nt)RK
: 1. CONTINtE LOW STRESS CREEP TESTS TO OBTAIN DATA DN THRESHOLD STRESSES AND DUCTILITIES '.N VARIOUS CE MICAL ENVIRO M NTS.
: 2. CONTINtE LOW STRESS IRRADIATION - CREEP TESTS IN AIR (0 DETERMINE CREEP RATES AND DUCTILITIES AT PROTOTYPIC SERVICE STRESSES.
: 3. CONTINUE EXISTING WORK ON EBEND SPECIENS IN CEMICAL AND IRRADIATION DNIRUMNTS.
B               l   ORATOUl}g}l ASSO(LATED UNNIR$mlS, INC(llll

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6lR7P.B Federal Register Nctice ADVISORY C0t9lITTEE ON NUCLEAR WASTE NUCLEAR REGULATORY COPMISSION Meeting Agenda - Revision 1 The Advisory Comittee on Nuclear Waste will hold a meeting on June 27-29, 1388. The sessiens en June 27-28, 1988 will be held in Room 1046, 1717 H Streec, NW, Washington, DC, The sessions on June 29, 1988 will be held in Room 2F-17, One White Flint North Bulls **9g, 11555 Rockville Pike, Rockville, MD.
                ,Nonday. June 27, 1988 - Room 1046, 1717 H Street, NW. Washington, DC 10:00 A.M. - 10:15 A.H.:            Cospents by ACNW Chairme- (Optn) - The ACNW
,               Chairman will repert briefly regarding items of cui' rent interest.                 .
10:15 A.M. - 12:00 N00N: Design Basis Accident Limits for the HLW Repository (0 pen) - The D0E staff will discuss their preposed request for a rulemaking defining the design basis accident limit for the HLW repository.
;               1:00 P.M - 5:00 P.M.:             Licensing of LLW Treatment Processes and the Dry 5torace and           Consolidation of 5 pent Fuel    (0 pen) - The MRR 5taff will report on the licersing of waste manager:ent activities at reactor sites with emphasis on the consolidation of spent fuel, LLW treatment prucesses, and dry storage.
Tuesday, June 28, 1988 - Room 1046, 1717 H Street, NW, Washington, DC 8:00 A.M. - 10:00 A.M.: LLW Form and Polyethylene High-Integrity Con-tainers (HICs) (0 pen) - The Division of Low-Level Waste and Decomission-
.               ing will report or recent staff and contrac'.cr actions concerning LLW solidified by cement, and studies regarding the serviivability of polyethylene HICs. The Division of Regulatory Researth will report on the proposed final rule for the revision to 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-level hadioactive Waste".
10:15 A.M. - 12:00 N00N: Consultation Draft Site Characterization Plan (open) - The DOE staff will review the content of the CD5cP and describe their plans te address the NRC Staff's comments on it.
1:00 P.M. - S AO P.M.: Alternative Site Models of the Yucca Mountain Site (0 pen) - The DOE 5taff and contractors will report on alternative models of the hydrologic structure of the Yucca Mountair, site.
 ,                                                                                                 by

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Wednesday. June 29. 1988 - Room 2F-17. 11555 Sockville Pike, kockville. MD ,
8:30 A.M. - 10:00 A.Mr: ACNW Future Activities and Preparation of ACNW     .
Reports (0 pen) - The ACNW will meet and continue to discuss anticipated AC1W activities, future meeting agendas, program plans, and organizational matters.
10:00 A.H. - 11:30 A.M.: Meeting with the NRC Commissioners (0 pen) - The ACNP will meet with the NRC CCMmissioners to discuss ACNW future activ-ities.
1:00 P.M. - 2:00 P.M.: HRC's Review of DOE's Consultation Draft Site characteritation Plan (0 pen) - The NRC 5taff will discuss their response to the May ll, 1988 memo from R. Fraley to V. Ste11o on the NRC Staff's review of DOE's Consultation Draft Site Characterization Plan (CDSCP).
2:00 P.M. - 2:30 P.M.: New Members (Closed) - The ACNW will discuss appointments of proposed members and the qualifications of individuals to be considered for nomination.
I have determined in accordance with Subsection 10(d) P.L. 92-463 that it is necessa'ry to close portions of this meeting as noted above to discuss information the release of which would represent a clearly
         ,   unwarrantedinvasionofpersonalprivacy(5U.S.C.552b(c)(6)]or involve internal personnel rules and practices of the agency [5 U.S.C.
SS2b(c)(2)].
1 Procedures for the conduct of and participation in ACNW meetings are similar to those used by ACRS and published in the Federal Regd star on October 2, 1987 (51 FR 32241). The procedures which will be used         ,
are as follows.
BACKGROUND Procedures to be followed with respect to meetings conducted pursuant to the Federal Advisory Committee Act by the Nuclear Regulatory Commission's Advisory Committee on Nuclear Waste (ACNW) are published in this notice.
These procedures are cet forth and may be incorporated by reference in future individual meeting notices. The Advisory Committee on Nuclear Waste has been established pursuant to the Federal Adviscry Committee Act 2
of October 6, 1972 (P.L. 94-463, 86 Stat. 770-776). The Commission has determined that the establishment of this Connittee is necessary and in I
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