ML19248D509
| ML19248D509 | |
| Person / Time | |
|---|---|
| Issue date: | 07/26/1979 |
| From: | Solberg D NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Durst J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 7908160347 | |
| Download: ML19248D509 (31) | |
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UNITED STATES
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NUCLE AR REGULATORY COMMISSION 7 J}5lEpg {C n ASH U.1T ON C C. 20LLL G
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JUL 2 61979 MEMORANDUM FOR:
Jay B. Durst, Assistant Director for Safeguards and Systems Performance Research Division of Safeguards, Ft.el Cycle and Environmental Research FROM:
Donald E. Solberg Systems Performance Branch Division of Safeguards, Fuel Cycle and Environmental Research
SUBJECT:
FACILITY DECOMMISSIONING RESEARCH REVIEV GROUP MEETING NOTES On June 8,1979, members of the Decommissioning Rena ch Review Group met to discuss research program status and results, formal proposals for future research and additional research needs.
The meeting agenda is presented in and the list of attendees is presented in Enclosure 2.
Long-Lived Activation Products Research (Fin No. B2296)
John Evans (PNL) ? resented the plans and results of this research program.
The visual materials distributed at the meeting is presented in Enclosure 3.
Pages 3-1 through 3-4 provide background information and are self explanatory.
Available samples of unirradiated vessel, vessel internals and concrete are presented on page 3-5.
The WNP 1/4 samples of concrete, aggregate, rebar and structural steel were obtained from the WPPSS construction at Hanford.
Breakdown of the aggregate species is presented on page 3-6.
A concrete core from the SMUD Rancho Seco Plant in Sacramento has been obtained. Six stainless steel samples have been obtained from a nuclear material supplier for reactor vessel internals. A single vessel steel sample has been obtained from BCL, i.e., SA 302B.
GE sample.materi. is exist at BCL and at the time of the meeting all necessary approvals had been obtained to receive sample material, although, the samples had not actually been received at PNL.
Identified irradiated samples are presented on page 3-7.
The Point Beach
- 1 samples have been received.
Negotiations on other identified samples are in progress.
The samples identified on pages 3-5 and 3-7 represent only those identified this far by PNL; the search for additional relevant materials will continue.
It was stressed at the meeting that:
concrete samples should be obtained which cover a wide geographical o
dis tribution o irradiated concrete specimens have not been found but the search should continue since they would be mos t useful to the program, 633234 7 90816 09 V7
i Jay B. Durst JUL 2 C 1373 o vessel materials from suppliers other than Westinghouse should be obtained.
Analysis results of concrete and aggregate samples are presented in the tables on pages 3-13 through 3-16.
On pages 3-13 and 3-14 are presented results for the Rancho Seco concrete sample, three concrete sample pours (SP) from WPPSS (used for compression tests), six aggregate samples and finally data for the earth's crustal abundance for comparison. On pages 3-15 and 3-16 are presented the analysis results for several rock classifications obtained from the WPPSS aggregate. Data from both tables are shown normalized to the earth's crustal abundance in the figures on pages 3-17 through 3-20.
Of the aggregate materials analyzed, quartz appears to have the lowest concentration of materials which will potentially lead to long-lived activation products and granite appears to be the next best choice. The ratio of the abundance of elements analyzed for these two rock types to the average abundance of all aggr -gate types analyzed is presented on page 3-21.
The lines connecting data points..re only present as an aid to visualizing the results.
A list of action items developed as a result of discussions is presented in.
In response to the o,uestion of how the PNL program compares with the British program being performed by Woollam (CEGR), Evans responded that the following improvements are available in the PNL project:
o Activation calculations using a spectrum of neutrons energies will be used o The radiochemistry will be of a higher quality.
o The program will provide information on geographical effects on s 2ncrete composition and vendor effects on steel composition.
For the record, it should also be noted that the U.S. study is based on PWRs and BWRs whereas the British study was based on gas cooled reactors.
There is no clear evidence that U.S. construction materials have the same proportions of mincr. and trace elements as the British materials.
Dave Robertson (PNL, gave a brief summary of the planned research project
" Characterization of Radionuclide Contamination Throughout Light Water Reactor Power Stations," (Fin No. B2299)*. The only NRC staff comment on the proposed research was that shorter-lived radioisotopes should be studied as well as long-lived radioisotopes.
These are necessary to evaluate decommissioning dose rates and for the evaluation of appropriate methods to reduce those dose ra tes.
Radioisotopes with half-lives as short as 90 days should be evaluated.
- This project was officially authorized on July 5,1979.
U33233
6 }g7g Jay D. Durst.
Lyle Perrigo presented his plan for proposed reseac'h to evaluate decontamination as a precursor to decommissioning. This presentatiar. closely followed the draf t 189a which was enclosed with the notice for this meeting.
NRC staff recommendations are presented in Enclosure 5.
Mr. Perrigo will rewrite and resubmit the 189a.
Bv. rose there was insufficient time for the NRC staff to discuss the final agenda item " Additional Decommissioning Needs," this item was deferre to a later date.
^
j i
Donald E. Solberg Systems Performance Brai th Division of Safeguards, Fuel Cycle and Environmental Research
Enclosures:
1.
Agenda 2.
Attendees 3.
Presentation Material (B2296) 4.
Action Items (B2296) 5.
Action Items (Perrigo) cc and Attendees:
R. M. Bernero, SD D. Crutchfield, NRR L. Barrett, NRR/ DOR A. Abriss, NMSS/FCLB A. T. Clar, NMSS L. Rubenstein, NRR C. Bartlett, RES
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t June E. 1979 Phillips Euildina, Poo-P-ll4 8:30 a.t.
Opening Remarks, D. Solberg C:40 Presentation of Long-Lived Activation Prcject Results and Plans, J. Evans, PNL l
10:15 Coffee Break 10:30 Continuation, sl. Evans 12:00 Lunch 1:15 p.m.
Discussion of Plans to Characterize LW: contanination, NRC staff, L. Rancitelii, PNL I
2:00 Discussion of comments on Pf;L Plan for Project " Decontamination as a Precursor to Decon-issioning", NRC staff f
2:45 Coffee Break 3:00 Discu:sion of Additional Decommissioning Research Needs and Approaches to Initiating Responsive Projects t
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E!,;LDEURE E AT T E t,'? a ','T E L I ST Decommissioning Research Review Group Meeting June 8,1979 Donald Solberg, RES Don Calkins, SD Carl Feldman, SD t
Lou Rancilillo, PML i
Leo Faust, PNL Lyle Perrigo, PNL John Evans, PNL Dave Robertson, PNL Dick Bangart, DSE Richard Emch, DOR Pete Erickson, DDR Tim Johnson, NMSS C33238
l ENCLOSURE 3 Presentation Material (B2296) a 6
t,33233
p LONG LIVED ACT VATION PRODUCTS IN REACTOR M ATERIALS
- nitiated February 1979 G
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MAJOR TASKS CHEMICAL ANALYSIS OF REACTOR MATERI ALS e CALCU'LATION OF EXPECTED RADIONUCLIDE ABUNDANCES
- NEUTRON CAPTURE REACTION
- FAST NEUTRON REACTIONS
- RADl0 CHEMICAL ASSAY ON SELECTED ACTirATED SAMPLES E
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TARGET ELE #ENTS NElJf RON CAPTURE OTHER T 1/2 (YEARS) 5.3 - 100 100- 1000
> 1000 5.3 - 100 100 - 1000
>1000 Co Ag Cl, S Li K
Al Cd ir,Os Ca Rb Ca Fe Sn Ni Sr Sm Eu, Sm Se Ba Pb Hf Zr Bi U
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MATERIALS TO BE CONSIDERED e
REACTOR INTERNALS STAINLESS STEEL 304 AND 316 e
PRESSURE VESSEL LOW ALLOY STEEL e
B10 SHIELD CONCRETE CEMENT COARSE AGGREGATE FINE AGGREGATE REBAR STRUCTURAL STEEL C
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BCL - GE VESSEL STEEL TENSILE STRENGTH SAMPLES 2-4 SAMPLES e
WESTINGHOUSE STAINLESS STEEL COUPON HANGERS e WESTINGHOUSE - EPRI VESSEL STEEL 8-10 SAMPLES UP TO 30 EFPY E
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Element s_;2/
t ENCLOSURE 4 ACTIOT. I' EMS (B2296) o NRC reerghasized that the prograr should be directed towards understanding the effects of geographical distribution of aggregate used in concretes.
o In choosing sarapies to establish the geographical distribution of aggregate near reactors, priority should be given to (1) those facilities to be docomnissioned, and (2) areas where reactors are now concentrated. The Northeast and North Central U.S. should receive a high priority.
o PNL should consider making gross estimates of the distributicn of mineral types which constitutc the aggregate in concrete by visually inspecting a cross section of the core.
This would supplement analysis data on the overall aggregate composition.
o Attention should be directed to modern reactors.
PNL agreed to contact the architectural engineers of the reactor sites of interest to detennine the types of concrete which were used (high density versus standard concrete) and also, if possible, determine the sources of the aggregate.
o Variability in composition of rebar was noted, e.g., as a result of the large influx of rebar from Japan that could produce a great deal of variability vs.
the U.S. product.
o A primary objective should be to place bounds, e.g., upper and lower limits, on aggregate composition so that we may ultimately understand the minimum and maximum long-lived radionuclide concentrations which could be produced.
b!}I3,20j.
o fiRC agreed to contact Woolan of the U.K to infom him (
the existence, goals and progress of our program and to ask him to keep us up to date on his progress.
o The origin of reactor vessels should be established and NSS vendors other than Westinghouse contacted for samples so that the issue of variability of I
construction materials can be addressed. The ASTM guide to composition of 1
f construction materials was suggested as a good starting point.
o PNL should contact Jim Divine for an inventory of materials in reactors (e.g.,
the gross composition of a reactor) and for composition from ASTM standards.
o Data on the composition of construction materials should be transmitted to those individuals who provide us with samples as both a courtesy to them and to improve our rapport.
o PNL should plan the next program review just prior to the NRC workshops to be held this fall and provide NRC with program sunriary slides for their use at the workshop.
o Jim Divine has several contacts with Canadian colleagues who might help Us obtain samples of reactor materials from Canada. F.4L should explore this possibility at the earliest possible time.
o The problem of obtaining highly irradiated concrete from a facility was discussed and it appears that this will be difficult to do in the near tem.
PNL should investigate the feasibility of obtaining a representative concrete sample and subjecting it to a long irradiation, possibly in the N-Reactor.
Sufficient material should be irradiated so that some could be archived for future use by ourselves or other researchers.
o ud rm r.1.o
.<.w-
o Pf;L should also contact persons in charge of mothballed reactors for sample availability as soon as possible.
k i
+
9
E ?ic D a x 5
Action items for Froposal to Evaluate Decontamination as a Drecursor to Decomnissioning t
1.
The modified prorosal (189) should provide much more detail on specifically what will be done and how it will be accomplished.
i 2.
Emphasis on the program is a.
reduction of occupational exposure b.
reduction of exposure to general public f
c.
reduction of waste volume 3.
The effect of each decontamination process studies on each item listed in 2 above should be determined.
+
4.
Task 2 should be expanded because it produces the principal results from the project. The investigation should not be limited to existing processes and should utilize duplicate samples obtained from the NRC sponsored project B2299 for experimental assessment of decontamination effectiveness.
The proposal should estimate the number of experimental samples required.
5.
Decontamination chemicals should be identified, at least generically, and j
any special considerations for their use presented.
i 6.
The study should include decontamination effectiveness in all parts of the plant, including primary coolant system, cooling towers and soil (although the latter two are intended to represent only a small part of the project effort, e.g., to determine feasibility).
7.
Wherever practicable decontamination as a method to permit recycle of components or materials should be considered.
r 8.
Timing of decontamination following facility shutdown is a parameter which should be considered as a variable in the study.
'F)
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9