ML19291H197
| ML19291H197 | |
| Person / Time | |
|---|---|
| Issue date: | 05/06/1983 |
| From: | Speis T Office of Nuclear Reactor Regulation |
| To: | Mattson R, Thompson H, Vollmer R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19291H196 | List: |
| References | |
| NUDOCS 8305170658 | |
| Download: ML19291H197 (19) | |
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I-3A - Part I Pa!le:
o f _ ___.
11.5. IlllCLEAR REGULATORY ColtfilSSI0tt Date prepar,l:
f Y 198!>-1906 Internal Review Dudget - Office Request Ollice:
lil 5 Decision Unit Justification 11ccision linit: ' Reactor and l acility (Dollars in lhousands) bgineering tvaluate seismic design margins of selected components and structures and develop procedures and methods for o
assessing operating plants subjected to increased postulated loads.
Provide test and analysis results that 1 cad to improved equipment qualification criteria to assure safety function o
during or after postulated accidents or events.
Develop the technical basis for establishing more realistic pipe break design criteria.
o Dased on results of research conducted in FY 1905 on analytical and test methods for structural integrity of o
a shipping casks, new standards will be initiated.
e P
structural Engineering g
In FY 1985 and FY 1986, tTuctural engineering research will see expanded programs in containment structures and their penetrations, and Se amic Category I structures, with new programs beginning on the detection and evaluation of the aging of structural 6taterials.
Consistent with national policies and prior.ities, research may also be initiated in the areas of waste management and fuel reprocessing.
Standards development offort will be devoted to maintaining and improving existing standards and developing high priority standards which codify research results.
IY 190!,
Completion of separate cf fccts tests related to pressure bountlary integrity of containments, inclinling base-mat o
shear.behavinr, n4/29/lu 3
RLAC10R AllD FACil.11Y I.flG l-3A
Schedule:
I-3A - Part 1 Page:
of 11.5. IlUCLEAR REGULATORY C0lilllSS10tl Date Preparcel:
fY 19115-1986 Internal Review flutiget. - Of fice Request Oflite:
fil ',
Decision linit Justification Uccision iloit; Iteactor and Iacility (Dollars in Thousands)
Ingineering
~hClawdul.
Comparison of t he predicteel capabilities of concrete containments uncler static internal pressure ag' ainst g
o
$%1yx S <w&
experimental results of containment model tests completed in FY 1904.
'f y "(C un Q
> j ?'r * % Yo %
Completion of seismic huckling tests on small steel containment models, cfMwc,
f, o
&CY WW W
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Perform experiments on models offmajor containment penetrations to relate laakage behavior to local deformations, o
a}VI-pressure-temperature environments M 0,
g) dA9,
j Perform model tests of multi-story concrete seismic Category I structures.
Obtain response, damping, anil failure o
o data for validating design requirements and scismic risk assessments, initiateimprovementstoexistingstandardsonthedesgorsteelcontainmentsincorporatingtheresultsof f(
o research on loati combinations, containment buckling and penetrat. ion integrity.
IY 1986 Compare predictions of steel containment capacity under (lynamic pressure loads with' experimental results.
o Establish and verify methods for predicting major,r.ontainment penetration leakage as a function of pressure-o temperature environments.
Develop recommendations for structural Ipad combination criteria for Seismic Category I structures.
o 04/29/83 4
REACIOR Aft 0 I ACil.IIY tilG I-3A
t Schedule:
I;- 3 A - l'a r t i Page:
of l1.5. ilVCLEAR REGULATORY Col 1MISS10ll Date Prepared:
FY 1985-1986 Internal Review Budget - Office Request DIlice:
lil 5 Decision tinit Justification Decision IIUIt: M actor and facility (Dollars in lhousands) tygincering SECT 10ll H - PLAllllED ACCOMPLISilMElli DETAIL planneil Accomp_1).hment. # 60190104 - Process Control fY 1983 FY 1904 Current.
Current FY 1905 TY 1986 Estimate Estimate Request.
t1 ARK Request itAHv (i10)
(5)
(5)
(5)
(
)
(5)
(
)
- Program Support $
3,305 2,625 3,550 4,300 liarrative:
Ihe results of process Control Research will be used by the NRC:
(1) to verify the effect.iveness of mitigation _fcatures for hydrogen and fission product control under I.WR accident. conditions, (2) to provide the bases for evaluating Iacilities for dry storage of spent fuel and.(3) to estah11sh guidelines on facilitat. ion methods, termination surveys
.itul Al.AHA railiat. ion exposures for decommissioning of nuclear facilities.
Standards development efforts will contentral.c on liigh priority regulations, regulatory guides and national standarels in these areas.
Pt;ocess Control IY 1985 Complete analytical and experimental investigat. ion of hydrogen control systems in intermediate scale facilities.
o Select appropriate hydrogen cont.rol schemes and perform tests integral with other accident. mitigation systems.
04/29/03 16 REACTOR AllD FACil.liY lilG E-3A
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Schedule:
f-3A - l' art 1 Page:
of C.S. IluCI. EAR REGULATORY C011HISSION llate Prepared:
FY 1985-190G Internal Review Dudget - Office Request 01Iice:
ills Decision Unit Just.ification Decision ilnit:
Rsictor and l'acility (Dollars in liiousands) l_ng i nee ri ng Perform model tests of steel and concrete Seismic Category I structures to obtain response, damping, and failure.
o data.
tvaluate methods for detecting and determining the ef fect of degradat. ion of concrete structures due to cliemical o
reactivity between concrete ingredients.
initiate improvements to existing standards on design of concrete containment and other concrete structures o
incorporating the results of research on load combinat.lons, o
s r
04/29/03
'S REACIOR Affl) l'ACilllY lilG I-3A
,