ML20155B430
| ML20155B430 | |
| Person / Time | |
|---|---|
| Issue date: | 05/17/1988 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8806130182 | |
| Download: ML20155B430 (26) | |
Text
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MAY I7 ytt MEMORANDUM FOR: Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS FROM:
John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch
SUBJECT:
Meeting with Department of Energy (D0E)
DATE/ TIME:
May 13, 1988; 3:00 p.m.
LOCATION Room 6-B-11, One White Flint North Building, 11555 Rockville Pike, Rockville, MD ATTENDEES:
NRC DOE R. Bernero K. Klch '
R. Cunningham D. Shelor L. Rouse G. Hartkopf J. Roberts N. Dayem PURPOSE:
Initial meeting on DOE Dry Storage Cask Study to acquaint NRC with DOE's approach to the study.
DISCUSSION:
On May 13, 1988, NRC staff met with DOE staff at NRC's White Flint Offices.
Tnis meeting was arranged after an excnange of letters regarding NRC comment an the congressionally mandated DOE Dry Cask Storage Study from Charles E. Kay, Acting Director, Office of Civilian Radioactive Waste Managemcnt, to Lando W.
Zech, Jr., Chairtaan, NRC, dated April 6,1988, with a response from Hugh L.
Thompson, Jr., Director, Office of Nuclear Aaterials Safety and Safeguards, dated Ayril 27, 1988. A final report is due to the Congress with NRC comment by Octobee 1, 1988.
DOE gm a general outline of its approach to the study to NRC staff (see enclosure). A-draft report is to be issued this July for public com,ent The attendees agreed that DOE and NRC :.taff will meet in mid-June when DOE wili provide a status briefing on its progress.
MD eso6130182 880517 John P. Roberts, Section Leader PDR ORG EUSDOE Iraadiated Fuel Section PDR Fuel Cycle Safety Branch c
Enclosure:
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i DRY CASK STORAGE STUDY
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BRIEFING FOR THE NUCLEAR REGULATORY COMMISSION i.
MAY 13, 1988 i
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i OBJECTIVES OF STUDY 1
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- 1. TO CONSIDER THE CO8TS OF DRY CASK STORAGE TECHNOLOGY, THE EXTENT TO I;
WHICH DRY CASK STORAGE AT REACTOR SITES WILL AFFECT HUMAN HEALTH AND THE i
ENVIRONMENT, THE EXTENT TO WHICH THE STORAGE AT REACTOR SITES AFFECTS THE COSTS AND RISK OF TRANSPORTING SPENT NUCLEAR FUEL TO A CENTRAL j
l FACILITY SUCH AS THE MRS, AND ANY OTHER FACTORS THAT ARE CONSIDERED
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APPROPRIATE.
- 2. TO CONSIDER THE EXTENT TO WHICH AMOUNTS IN THE NUCLEAR WASTE FUND CAN BE USED, AND SHOULD BE USED, TO PROVIDE FUNDS TO CONSTRUCT, OPERATE, l
MAINTAIN, AND SAFEGUARD SPENT NUCLEAR FUEL IN DRY CASK STORAGE AT l
REACTOR SITES.
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- 3. TO CONSULT WITH THE NRC AND INCLUDE THEIR VIEWS IN THE REPORT.
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- 4. TO SOLICIT THE VIEWS OF STATE AND LOCAL GOVERNMENTS AND THE PUBLIC.
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MW 6
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REPORT CONTENTS To MEET OBJECTIVE 1, THE REPORT WILL INCLUDE:
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- A REVIEW OF THE QUANTITY OF FUEL THAT WILL REQUIRE EXCESS POOL STORAGE ASSESSMENT OF ADDITIONAL STORAGE REQUIREMENTS BOUNDING CASES FOR ADDITIONAL STORAGE INVENTORY DISTRIBUTION OF ADDITIONAL STORAGE REQUIREMENT FACTORS AFFECTING REQUIREMENTS DISCHARGE FORECASTS EFFECTS OF POOL CAPACITY ASSUMPTIONS EFFECTS OF DOE ACCEPTANCE
- A REVIEW OF REACTOR STORAGE EXPANSION OPTIONS, INCLUDING:
IN-POOL CONSOLIDATION
-TO INCREASE DRY STORAGE CASK PAYLOAD
-TO INCREASE SPENT FUEL POOL STORAGE CAPACITY METAL STORAGE CASKS CONCRETE STORAGE CASKS CONCRETE MODULES DUAL PURPOSE CASKS (STORAGE / TRANSPORT)
i TO MEET OBJECTIVE 1 (CONTINUED):
- FOR EACH STORAGE EXPANSION OPTION:
DESCRIPTION OF THE EQUIPMENT AND OPERATIONS IMPLEMENTATION EXPERIENCE, STATUS, AND PLANS CERTIFICATION / LICENSING ISSUES AND STATUS HUMAN HEALTH AND ENVIRONMENTAL IMPLICATIONS ESTIMATED UNIT COST RANGE AND UNCERTAINTIES 9
- AN ASSESSMENT OF THE OVERALL UTILITY SYSTEM COST AND RISK IMPACTS OF PROVIDING AT-REACTOR STORAGE.
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- AN ASSESSMENT OF THE OVERALL TRANSPORTATION SYSTEM COST AND RISK IMPACTS OF PROVIDING AT-REACTOR STORAGE.
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- AN ASSESSMENT OF THE LONG-RANGE IMPLICATIONS OF EXTENDED AT-REACTOR STORAGE.
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To MEET OBJECTIVE 2, THE REPORT WILL INCLUDE:
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- SEPARATE DISCUSSIONS FOR "CAN THE WASTE FUND BE USED" AND "SHOULD THE WASTE FUND BE USED" l
- CAN THE WASTE FUND BE USED?
DOE IS REVIEWING THE NWPA AND CONGRESSIONAL TESTIMONY TO DETERMINE WHETHER AND HOW THE DOE IS AUTHORIZED TO USE THE WASTE FUND TO SUPPORT AT-REACTOR STORAGE.
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- SHOULD THE WASTE FUND BE USED?
DOE IS DETERMINING AND DEVELOPING THE CIRCUMSTANCES UNDER WHICH IT COULD BE APPROPRIATE FOR THE WASTE FUND TO BE USED TO SUPPORT AT-REACTOR STORAGE.
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l To MEET OBJECTIVES 3 AND 4:
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- EARLY DISCUSSIONS WITH THE NRC TO OBTAIN THEIR VIEWS j
- MEETINGS WITH EPRI AND EEI TO DISCUSS THE VIEWS OF THESE UTILITY l
INDUSTRY REPRESENTATIVES
- THE "INITIAL VERSION" OF THE STUDY WILL BE REVISED, AS NECESSARY, TO i
INCORPORATE THE COMMENTS / SUGGESTIONS OF THE NRC AND UTILITY GROUPS i
- AN "INITIAL VERSION" OF THE STUDY WILL BE RELEASED THIS SUMMER FOR j
PuBLIC COMMENT i
- AFTER REVIEWING THE COMMENTS RECEIVED, THE DOE WILL MAKE ANY NECESSARY MODIFICATIONS TO THE REPORT BEFORE IT IS SUBMITTED TO THE CONGRESS.
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COMMENTS RECEIVED WILL BE INCLUDED IN A COMMENT APPENDIX i
- TIME PERMITTING, A
SUMMARY
OF COMMENTS MAY BE INCLUDED IN THE REPORT.
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- THE FINAL REPORT WILL AGAIN BE SENT TO THE NRC FOR REVIEW AND COMMENTS, PRIOR TO ITS SUBMISSION TO THE CONGRESS.
NRC'S COMMENTS WILL BE INCLUDED IN THE SUBMISSION TO CONGRESS.
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1 MAJOR SCHEDULE MILESTONES INITIATE STUDY AND PREPARAlION OF DRAFT REPORT LATE JANUARY 1988 i
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ISSUE FEDERAL REGISTER NOTICE AND LETTER To NRC APRIL i
"INITIAL VERSION" RELEASED TO PUBLIC EARLY SUMMER l
1 j
PUBLIC COMMENT PERIOD SUMMER-EARLY FALL i
l "FINAL REPORT" COMPLETED AND SENT To NRC EARLY SEPTEMBER 1
"FINAL REPORT" WITH NRC COMMENTS ATTACHED SUBMITTED TO CONGRESS OCTOBER 1, 1988 i
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PROPOSED PLAN FOR CONSULTATION WITH NRC
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- INITIAL MEETING TO PRESENT GENERAL SCOPE OF STUDY AND PRELIMINARY RESULTS TO NRC.
- FOLLOW-UP MEETING TO PRESENT MORE DETAILED RESULTS AND CERTIFICATION / LICENSING RELATED CONTENTS OF STUDY.
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- INCORPORATION OF ANY NRC COMMENTS / SUGGESTIONS INTO THE "INITIAL l
VERSION" OF THE STUDv.
- NRC PROVIDES COMMENTS ON THE "INITIAL VERSION" DURING PUBLIc COMMENT PERIOD I
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- "INITIAL VERSION" IS MODIFIED BASED ON COMMENTS RECEIVED.
FINAL REPORT 1s PREPARED AND SENT TO NRC.
- NRC PROVIDES COMMENTS ON THE FINAL REPORT.
THESE COMMENTS ARE ATTACHED TO FINAL REPORT IN THE SusMISSION TO CONGRESS.
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STATUS 4
OVERVIEW 0F STUD)
CONTENTS DEVELOPED TO DATE i
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Table 2.2 Summary of Additional Spe<it reel marage Nequirements for Changes I
in Initle) Acceptance Date Initial Acceptance Date 3 98 2003 C T3 None Additional Storage Neguirement (NTU)
No New Orders Projection 4530 9780 17230 25550 32090 hgregateN-859?rojection 7650 16210 26430 34100 42450
'ask Storage inventory (NTU)
No New Orders Projection 2830 7180 II52G 20880 32090 Aggregate NW.859 Projection 5130 11780 20090 34100 42450 Peak Storage Inventory year No New Orders Projection 1999 2004 2009 2014 N/A Aggregate N-859 Projection 2002 2005 2009 2014 N/A Year Storage hequirement is Eliminated Po New Orders Projection 2025 2030 2035 2040 N/A A2gregate NW-859 Projection 2029 2034 2039 2044 N/A Average Length of Storage - Years No New Orders Projection 9
12 14 15 N/A Aggregatr RW-859 Projection 13 15 17 19 N/A 16
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Drganizations Effects on vorher/
Certification /
Technology /Wethee Locations Descriptier Time Period Public/ Environment Licensing Status IN-P88L R8D C8NS8tIDATI8N Westinghouse Duke /Oconee 24seved all rods r' ance: mas.
1982 Data unavailable No action censoledstien ratio of 2:1 for 4 assemblies; NTUC= compacted 6:1 Proto-Power Corp.
Waine Yankee Removed PWR rods one at a time, 1981-1984 Worker - s.88 to s.2 Delayed to 199ss 1.8:1 consolidation ratio for 1 man-ree/ fuel assembly assembly in 1-3 areefh bach-
[
ground; I
P/E aegligible NAC RCAE/ West Valley Removed PER rods one at a time; 1985-1988 Worker - S.8 aree/S No action 1.8:1 man. consolidation ratio in 1-2 areefh bach-for 8 assemblies eith damaged ground; rods known to esist P/E - negligible USTAD RG8E/Battell-Removed one row of PWR rods et a 1988 Data unavailable No action time; 1.85:1 to 2:1 consolidation ratio for 5 assemblies with damaged rods known to exist CE NUSCD/Willstone Ree2ved one row of PWR rods at 1983-1988 Data unavailable Issued Warch 1988 a time; 2:1 consolidation ratio for the Willstone-for all 8 assemblies; NFBCs Il pool awaiting compaction Westinghouse NSP/ Prairie Removed all rods at once; 2:1 1987 Worker - 21 eres Espected in 1989 Island consolidation ratio for 38 average assemblies (most rods consoli-P/E - negligible dated in a demo to date); NFBCs to be compacted by WasteChee a
TABLE 3-9.
SUMEARY BF U.S. IN-PSOL R00 CSNSOLIDATISM AOD DRY STSRACE STATUS Organizations Eifects on Worker /
Certification /
Technology /Wethod Locations Description Time Period Public/ Environment Licensing Status DRY ST9AACE Wetal Casks REA-2823 DOE /CE-Morris REA-2823 BOR; 52 Cooper 1983-1985 Worker - 25 ores No action 1
assemblies; 115kW decay heat; everage fuel / cash toep. t cask surface P/E - negligible dose rate esas.
1 CASTOR-V/21, TN-24P, VP/00E/EPRI/INEL CASTOR-V/21, Tu-24P, & WC-15 FWR 1984-1987 Worker - 1.2 to 1.8 CASTRE+'V/21 and WC-18 casks: 21 to 24 Sorry essemblies; san-ree MC-18 approved by 13 to 28 kW decay heat; fuel / cask P/E - negligible NRC; TN-24P being toep. A cask surface dose rate reviewed by NRC seas.
CASTOR-V/21 VP/DDE/EPR1/
3 CAST 8R-V/21: 21 Sorry assemblies 1988-1989 Worker - 58 ares Issued July 1988 Surry per cask; 8-8 kW decay heat; NAC manieus for ISFS1 e/ CASTOR-and another vendor's cash in 1988-P/E - negligible V/21s; NAC cask 1989 m/consol. fuel being reviewed by NRC CASTDR-V/21 VP/5urry 2 CASTOR-V/21: 21 Sorry assemblies 1987 Worker - 58 eroe Issued July 1988 per cask; 18 kW decay heat assimus for ISFS1 e/CASTO.4-P/E - negligible v/21s; to be seended for other casks in 1988
)
TN-24P DOE /EPRI/1NEL TN-24P consolidated PWR; 38 Surry 1987-1988 Wor %er - 1.2 No application
& 12 Turkey Point assemblies enn-ree submitted for consolidated into 24 canisters; 23 P/E - negligible consol. fuel in l
kW decay heat; fuel / cash toep.
TN-24P esas. A cask surface dose rate seas.
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Organizations Effects on Worker /
Certification /
Technology /Wethod Locations Description Time Period Public/ Environment Licensing Status NAC26-ST NAC Ceneric NAC 26 assembly cask; 1987-1988 Data vivai!,ble Approved by NRC modified version to be demon-strated at Surry in VP/DDE cooperative program Horizontal Concrete Hodules NUHOMS/NUTEC,H CP8L/DDE/EPRI Three NUl10MS modules; 7 PER 1984-1988 Date ansvailable Issued August 1988 l
assemblies each; 15 kW decay heat; for 8 medule ISFSI fuel / canister /sodule/ air toep.,
air flee and eodule surface dose rate esas; E add'l modules to be dded as needed NUHOWS/NUTCCH Duke /NUTECH 88 module licensed ISFSI; each 1988 - Open Data unavailable Intent for 88 module contains 24 assemblies module ISFSI for total of 2112 assemblies submitted to NRC in September 198F Modular Vaults Foster-Wheeler Foster-Wheeler Vault modules store 83 PWR and 1988 - Open Data unavailable Approved by NRC in 158 BER assemblies; einieue March 1988 for facility consists of 2 modules, nitrogen storage cask handling area, and shielded only; note that fuel handling eachine NRC did not approve tha system for air storage until sufficient osida-tion data are obtained Concrete Casks CP-9/VSC-11/NUPAC/
DOE /NUPAC/ REEDY One 9 assembly / canister PWR cask 1987-1989 To be generated in 9 assembly / canister i
REEDY and one 17 asstably/ canister PWR 1989.
PER cask being cask; Surry sad Turkey Point reviseed by NRC consolidated fuel; fuel / cask toep.
& cask surface dose rate seas.
TABLE 3-10.
RANGE OF UNIT COST ESTIMATES FOR ADDITIONAL SPENT FUEL STORAGE REQUIREMENTS
($/kgu)
Storage Technology Unit Cost Range $kqU for Site Capacity 100 MTU 300 MTU 1000 MTU Consolidated ' fuel stored in reactor pool 42-73 31-51 N/A i
Metal Cask 62-113 57-103 55-99 1
Concrete Cask 52-105 47-92 45-87 i
j Horizontal Concrete Modules 47-71 42-63 40-60 5
Modular Vault 105-157 72-107 47-70 i
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8 8,
8 8
8 m
n9W$
T*E*p aJnSTJ
_ - - - - - _ ~.
Figure 4.2.2 manges of System-Wide Storage Requiressents Cost Estianates
[
for Various DOE Initial Acceptance Dates i
l 1
4 1 3
j j
l 1
.h 1
m 2
m a
i
(
i, i
.i.
1 I
-~.
~
~..
t i
I I
O i
1998 2003 2008 2013 Initial DOE Acceptance I
j I
I l
4