ML20206C089
| ML20206C089 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/08/1988 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-PROJ-M-49 NUDOCS 8811160093 | |
| Download: ML20206C089 (33) | |
Text
. _ _ _ _ - _.. _ _ _ _ _ _ _ _ _
k NOV 0 81998 i
Docket No. 50-317 & 50-318 Project No, M-49 MEMORANDUM FOR:
Leland C. Rouse, Chief l
4 Fuel Cycle Safety Branch Division of Industrial anu Medical Nuclear Safety, NMSS FROM:
John P. F
- ts, Section leader Irradia,a tv.1 Section Fuel Cycle Strety Branch Division of
- dustrial and Medical NLict Safety, NMSS
SUBJECT:
MEETING WITH BALTIMORE GAS AND ELECTRIC COMPANY (BG&E)
ANE CUTECH, INC.
DATE/TIHE:
November 4, 19683 9:00 a.m.
LOCATION:
Room 6-B-ll, One White Flint North Building, Rockville, MD i
ATTENDEES:
Fqe enclosure 1.
i PURPOSE:
Discussion of a license application under 10 CFR Part 72 i
I BG&E for dry spent fuel storage at the 1,ita of its calvert Cliffs nuclear power plant.
DISCUSSION:
After introduction of attendees, BG&E spoke. BG&E generally followed its j
agenda and presentation (see enclosure 2). However, for purposes of
~
familiarizing many of those present with the NUTECH NUHOMS-24P design (which BG&E proposes to reference for use in its application) for a concrete module and stainless steel canister dry storage system, NUTECH made a presentation l
on the system (see enclosure 3).
f 1
i BG&E seeks to avoid loss of full-core reserve for the two Calvert Cliffs units enclostre 2 final page for sc1edule requirements) plication in May 1989 (see in 1992. Consequently, BG8E
)lans to file its ap q
Assuming license approval.
i BG&E would construct an initial set of 24 modules. A total of 120 modules to give capacity through year 2016 is planned. BG&E spent fuel is Combustion Engineering (CE) 14 x 14 pressurized water reactor fuel.
Proposed limits of 4.3 to 4.5 weight percent initial enrichment and 47,000 MWD /MTU were mentioned.
l Use of CE fuel would in general lead the applicant to downsizing the NUHOMS-24P, i
as presently designed (reference:
Project No. M-49), although the stainless i
[
steel dry shielded canister (DSC) diameter is not expected to change.
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I GS11160093 estgog hDR ADOCK0500g7 1
l
i Leland C. Rouse 2
N O V 0 s 1989 Some arr.endmer.ts to Calvert Cliff operating licenses associated with dry storage are expected. These would include areas, such as security and provision for a single-failure proof crane to accomodate a transfer cask encompassing a DSC for fuel leading in the reactor pool. Under BG&E's proposal, a loaded DSC after sealing would be moved in the transfer cask designed to hold it from the reactor to the module site for offloading into a module (see enclosure 2, Figure 2.1) on a flood-free site.
During the meeting, NUTECH mentioned that there was potential for designing a transfer cask to also meet the requirements of 10 CFR Part 71 for direct offsite shipment of loaded DSC's at the end of licensed storage. At the end of the meeting, BG&E explained that an incentive of $15,000 per DSC was included in BG&E's contract with NUTECH to encourage such direct offsite shipment of DSC's to foster compatibility by direct offsite disposition of spent fuel to the Department of Energy at the termination of storage.
OfW Sened By:
John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS
Enclosures:
1.
Attendance List 2.
Agenda / Presentation 3.
NUTECH NUHOMS Presentation DISTRIBUTION:
L 9bd Docket Ro70-317 & 50-3i8 Project'No. H-49 PDR NRC File Center IMIF R/F' IMNS Central File NHSS R/F IMSB R/F JPRoberts FLBrown Beveridge/ Cornell 1-23
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'1/8/88 j
DATE:
0FFICIAL RECORD COPY l
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NOV 0 019%
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November 4, 1988 Baltimore Gas and Electric Company /NUTECH i
Heeting with NRC Staff Attendance list r
{
John P. Roberts NRC/NHSS Jim Schneider NRC/NMSS l
4 Fritz Sturz NRC/NHSS John R. Stokley SAIC Steve Ruffin NRC/NHSS Penney File BG&E Normen Wagner NRC/NRR/ DEST 4
Jack Parry HRC/ACNW j
Moses Taylor, Jr.
NUTECH I
Jack D. Rollins NUTECH l
Jin Bennett CG&E David Trimble NRC/ Reg I-SRI Vincent Pritchett NRC/ Reg I-RI j
Scott McNeil NRC/NRR j
Bruce Montgomery BG&E - P.E./ Licensing l
Freda C. Phifer SERCH t
Stephanie Shamen SERCH l
f William McCaughey BG&E-Licensing
[
i Thomas Hagette State of MD William McConaghy NUTECH
{
5 Bruce Proctor BG8E i
J
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AGENDA Baltimore Gas and Electric Comnany Calvert Clihs Nuclear Power Plant NUHOMSW-24P ISFSI Licensina "Kickoff" Meetina NRC Headquarters Rockville, Maryland 9:00 a.m., November 4,1988 Introduction and Purpose Calvert Cliffs ISFSI Facility Overview Fuel Storage Status at Calvert Cliffs Facility Location and Basic Features Summary of Principal Des!gn Criteria / Parameters Fuol Assembly Selection Dry Shielded Canister (DSC)
Horizontal Storage Module (HSM)
Transfer Cask and Transfer Equipment Licensing Approach Schedule Requirements Discussion and Summary t
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L
BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUHOMS@ ISFSI ISFSI FACILITY OVERVIEW Spent Fuel Storage Status at Calvert Cliffs Spent Fuel Storage History Sp9nt Fuel Pool Operating Reserve Status without Dry Storage Spent Fuel Pool Operating Reserve Status with Dry Storage Facility Location and Basic Features Location Dimensions and Capacity Basic Features l
l
CALVERT CLIFFS SPENT FUEL STORAGE CAPACITY EXPANSION HISTORY DATE UNIT 1 UNIT 2 "0TAL OHGINE 200 200 400 1978 200 528 728 1981 830 528 1858 1983
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l POOL STORAGE STATUS TY1T110UT NUHOMS i
A 1915 POOLFUll l
1819 j
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1827 IDSS OF FG.
M 1531 1435 h
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1243 1147 l
87 88 89 90 91 92 93 94 96 96 l
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POOL STORAGE STATUS WITH NU110MS 4
1915 1819 1723 b
1827 IDSS OF FCR, M
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LEGEND l
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- 1. Unit No.1
- 2. Unit No. 2 1 Aur!!!ary Building 11-J
- 4. TIJrt4ne Bulk!!ng
- 5. Offke/Tiralning Facility l
- 6. Nuclear Engineering Facility i
- 7. Matertate ProcessJng Facility I
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F BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUHOMS@ ISFSI PRINCIPAL DESIGN CRITERIA / PARAMETERS Desian Criteria Design Criteria Same as That Defined in NUHOMS@-24P Topical Report 10CFR72 July 'i988 ANSI 57.9-1982 NRC Regulatory Guide 3.54 NRC hegulatory Guide 3.60 l
Acceotance Cellerht Maintain Subcriticality with Koff <.95 Maintain ALARA and Meet 10CFR100 Limits Ensure Fuel Cladding Integrity Meet Structural Code Allowables (ASME and ACl) l l
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F' BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUHOMS@ ISFSI PRINCIPAL DESIGN CRITERIA / PARAMETERS (cont.)
Fuel Assembly Selection Qualification of Fuel Assemblies for Dry Storage Based on Development and Comparison to Burnup Equivalence Curve Using NUHOMS@-24P Topical Report Methodology Comparison of TR (B&W 15 x 15) and Calvert Cliffs CE 14 x 14 Fuel Smaller Fuel Envelope Lichter Weight Less Reactive Wider Range of Burnups Wider Range of initial Enrichments Wider Range of Cooling Times
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BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUHOMS@ ISFSI PRINCIPAL DESIGN CRITERIA / PARAMETERS (cont.)
i Dry Shielded Canister (DSC)
Basic Criteria and Con!!guration Same as Described In NUHOMS@-24P Topical Report, Modified for CE 14 x 14 Fuel Basket Assembly Design Stainless Guide Sleeves (No Poison)
Credit for Bumup Credit for Boron (if Necessary)
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Horizontal Storaae Modelle (HSM)
Basic Configuration Same as Described in NUHOMS@-24P Topical Report Length Adjusted for DSC/CE 14 x 14 Fuel Back-to Back HSM's Maximum Array Size Meets Tcpical Report Criteria ACI 349 Code Reinforced Concrete Structure AISC Structural Steel DSC Support System l
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Transfer Cask and Transfer Eauloment Basic Criteria and Confai uration of Cask Same as Described in NUHOMSW-24P Topical Report Length Adjusted for DSC/CE 1< x 14 Fuel Solid Neutron Shield 4
Cask Drop Criteria Enveloped by Topical Report ASME Code Class 2 Vessel 100 mrem /hr Maximum Contact Dose Rate Transfer Equipment Same as Described 'n NUHOMS@-24P Topical Report Transport Trailer 1
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LICENSING APPROACH System Based on NUHOMS@-24P Topical Report Design with the Following Calvert Cliffs Unique Features:
CE 14 x 14 Fuel vs. B&W 15 x 15 Solid vs. Liquid Neutron Shield for Transfer Cask 100 mrom/hr vs. 200 mrem /hr Transfar Cask Maximum Coritact Dose Rate Safety Analysis Report Incorporate CE 14 x 14 Fuel 4
Address Plant Specific Criteria / Loads Address Any Design Differences Environmental Report Security Plan 10CFR50 vs.10CFR72 Interface i
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BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUHOMS@ ISFSI SCHEDULE REQUIREMENTS File Site License Application 5/15/89 ER Approval Needed 11/15/89 Begin Facility Construction 11/15/89 Release Equipment Fabrication Contracts 3/15/90 SAR Approval Needed 7/15/90 Pre-Operational Testing Begins 2/91 Facility Complete, First DSC's Delivered 4/91 Loss of Full Core Reserve 4/92 l
Load First 24 DSC's 7/91-10/92 Load 8 DSC's 1994 Load 8 DSC's 1996 1
Load Additional DSC's at Approximately 2 Year Intervals Thereafter l
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