ML20127N535
| ML20127N535 | |
| Person / Time | |
|---|---|
| Issue date: | 05/07/1985 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8505230563 | |
| Download: ML20127N535 (5) | |
Text
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- PRDA MEMORANDUM FOR:
Leland C. Rouse, Chief Advanced ' Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety FROM:
John P. Roberts Advanced Fuel and Spent Fuel Licensing Dranch '
Division of Fuel Cycle and Material Safety Location:
5th floor conference room; W111ste Building v
Silver Spring, MD Date and Time:
May 2,1985; 9:00 a.m.
SUBJECT:
DEPARTMENT OF ENERaY AND NUCLEAR REGULATORY COMMISSION MEETING
-I Attendees:
See enclosure 1.
Purpose:
DOE presentation to NRC staff of spent fuel storage research and development and demonstration efforts being or to be performed under the Nuclear Waste Policy Act in support of NRC rulemaking.
Discussion:
The agenda of the meeting generally followed the items proposed by DOE
, 'i (see enclosure 2). NRC staff agreed that DOE's efforts were comprehensive and adequate to meet NRC needs in the area of spent fuel storage.
DOE staff also mentioned that information on 00E shipment of spent fuel to the Idaho National Engineering Laboratory will be published and also will be publicized at the Office of Civilian Radioactive Waste Management Spring 1985 Meeting on May 14-15, 1985, in Kansas City, Missouri.
Original ciCned by Jebu F. IM b m't B 8505230563 850507 John P. Roberts PDR ORG EUSDOE Advanced Fuel and Spent Fuel PDR Licensing Branch Enclosures :
1.
Attendance List 2.
Discussion Items A
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OFFICIAL RECORD COPY c us.m usa-4ao-247 NRC FORM 318 hot 96b NRCM O240
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Ex. /
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ATTENDEES--MAY 2,1985 John Roberts NRC Jim Daily DOE-Richland y
Glenn Russcher PNL-Richland Fritz Sturz,
NRC Gordon Beeman PNL
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, Tom Clark NRC Jim Schneider NRC ln Norman Davison NRC Dwight Shelor DOE /RWL32 Joe Epstein.
DOE /RRL32
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En: 2 4
a PROPOSED DISCUSSION ITEMS FOR DOE /NRC MEETING (May 2, 1985)
I.
Current Program Activities Dry Storage Development and Demonstration c.
Modeling and Code Verification Spent Fuel Verification Testing II.
Further Items for Discussion Cover gas operating conditions for spent fuel dry storage systems I'
Monitoring inert cover gas Storage of aged spent fuel in air.
' Failed fuel storage and handling requirements for spent fuel storage 2m_.
systems
- Canister utilization Containment requirements for storage Crud impacts upon spent fuel storage and handling Dispersal and spallation conditions and consequent operational limitations
- Crud accumulation and radiation exposure
- Decontamination limitations Storage cask requirements for intact or ' consolidated spent fuel Accountability
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- Cask closure Reactivity credits for burnup, boronated H 0, etc.
2 Consolidated spent fuel dry storage limitations -
Heat transfer analysis Radiation self-shielding analysis Compromised fuel integrity III. Other Items 9
W.
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~t Spent Fuel Verification Testing Spent Fuel Storage Testing 1.
CASTOR IC - 16 BWR:
nodular cast iron and polyethelene 2.
R'EA 2023 - 52 BWR:
lead and,ettelene glycol / water.
3.
CASTOR V/21 - 28 PWR 4.
TN-24 5.
Westinghouse MC-10 Spent Fuel Simulation Tests 1.
Single Assembly Heat Transfer Test '
~
Soent Fuel Calorimetry Tests 1.
Monticello and Dresden fuel assemblies - BWR 2.
. Cooper fuel assemblies - BWR 3.
WEPCO, San Onofre, Turkey Point - PWR
~
U0,, 0xidation Tests 1.
Controlled moist air 2.
Controlled moist N2 - completed Spent Fuel Oxidation Tests 1.
Controlled moist air 2.
Controlled moist N2 Storage in Controlled Cover Gas 1.
NTS-EMAD storage 2.
NTS-EMAD Fuel Temperature Test 3.
Foreign storage Storage in Water, Subsecuently Air 1.
Waterlogging of failed fuel 2.
Borated H O effects on stainless steel (and fuel handling failure) 2
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I, Modeling and Code Verification Computer Code A:,alyses for Licensing Purposes r.
e 1.
Benchmark Analyses of the BWR Cask Characterization Tests 2.
Analysis of PWR Tests at INEL 3.
Code Evaluation using. measured data,for comparison 4.
Code Documentation (to meet NRC standards)
.~.
Zircaloy Stress Rupture Modeling of Spent Fuel Failure-1.
Creep Rupture Model for Dry Storage 2.
Other Applications b
9
.