ML073460630
| ML073460630 | |
| Person / Time | |
|---|---|
| Site: | 07201021 |
| Issue date: | 06/12/1997 |
| From: | Mcduffie S NRC/NMSS/SFPO |
| To: | Kane W NRC/NMSS/SFPO |
| References | |
| NUDOCS 9706180325 | |
| Download: ML073460630 (22) | |
Text
JA~t REG&o2l UNITED STATES NUCLEAR REGULATORY COMMISSION 01 WASHINGTON, D.C. 20555-0001 June 12, 1997 MEMORANDUM TO:
William F. Kane, Director
.I o Spent Fuel Project Office, NMSS FROM:
Stephen McDuffie, Project Scienti Spent Fuel Licensing Section Spent Fuel Project Office, NMSS
SUBJECT:
MEETING WITH TRANSNUCLEAR TO DISCUSS PLANS FOR AMENDING THE TN-32 TOPICAL SAFETY ANALYSIS REPORT (TSAR) AND SUBMITTING THE TN-68 TSAR On May 8. 1997. a meeting was held between representatives of Transnuclear, Inc. (TN) and the Nuclear Regulatory Commission to discuss TN's plans for submitting amendments to the TN-32 TSAR and the initial TN-68 TSAR.
The meeting was held at the request of TN.
On November 7. 1996. NRC approved the TN-32 TSAR, allowing its use in conjunction with site-specific licenses.
TN now plans to request amendments to the TN-32 TSAR to expand the variety of pressurized water reactor (PWR) fuel that can be stored.
In addition, TN will submit a TSAR for the TN-68 cask designed to allow storage of boiling water reactor (BWR) fuel. is a meeting attendance list, and Attachment 2 is a copy of the handout provided by TN.
This meeting was noticed on April 21, 1997.
In July 1997, TN plans to request an amendment to the TN-32 TSAR that will allow the storage of fuel with higher burnup and initial enrichment.
The amendment will also request permission to store burnable poison rod assemblies in the TN-32 cask as presently designed.
TN plans to request approval of this amended TSAR under 10 CFR Part 72, Subpart K. allowing use of the TN-32 under the general license of Section 72.210.
The request for Subpart K approval is also expected in July 1997.
NRC can expect to receive a TSAR for the TN-68 cask in September 1997.
This general cask design will be similar to that of the TN-32, but modified to store BWR fuel.
TN has not decided whether Subpart K approval will be sought for the TN-68 cask.
Finally, TN plans to submit another-amendment to the TN-32 design in 1998.
This cask will be named the T*-32L, and the design will be lengthened by approximately 10 inches so the cask can store 15 X 15 Babcock & Wilcox assemblies and control rod assemblies.
An NRC staff member advised TN that the cask tip-over analyses will need to be repeated for the lengthened TN-32L cask.
TN responded that it plans to repeat the tip-over structural analyses using the modified values for the TN-32L, using the same method used for the TN-32.
TN expressed reservations about ursuing Subpart K approval for the TN-68.
TN's experience leads them to believe that NRC approval comes faster through a TSAR submittal, and the fabrication restrictions of Section 72.234(c) make the Subpart-K approval process unattractive.
NRC reminded TN that fabrication prior to TSAR approval does require a 10 CFR Part 72 site-specific license holder to have an approved quality assurance plan.
NRC FILE CENTER COPY' 97O&1SO325 970612 PDR ADOCK 07201021 C
W. Kane Several representatives of PECO Energy, a potential user of the TN-68 cask, attended the meeting.
One member of the public attended as well.
A brief proprietary discussion on future plans for the TN-68 took place at the end of the meeting, but no proprietary written material was disseminated.
No regulatory decisions were requested or made at this meeting.
Docket 72-1021 Attachments:
- 1. Attendance List
- 2. TN Handout Distribution:
Docket 72-1021 SFPO R/F PEng NRC File Center SGagner, OPA EEaston PUBLIC CHaughney JJankovich NMSS R/F SShankman FSturz NRC Attendees WReamer.
&~ SFPQ-rI"' SFPO NAME SMcDuffie: d VTharpe' EJLeeds 4
y I
DATE 06/ 10 /97 06/ (0
/97 06/ fr/97 C - COVER E -
COVER & ENCLOSURE N - NO COPY OFFICIAL RECORD COPY G:\\TN-32\\050897.MS 6/12/97 :dd Mru"')
170103
ATTENDANCE LIST NRC/TRANSNUCLEAR MEETING ON PLANS FOR AMENDING THE TN-32 TOPICAL SAFETY ANALYSIS REPORT MAY 8. 1997 NAME Steve McDuffie William Ward Jim Spets David Tang William F. Kane Eric J. Leeds Charles J. Haughney Dennis Vinson Michael Waters Tara Neider Alan Hanson William Eckman Dave Foss Matt Eyre Steve Hesse Sidney Crawford ORGANIZATION NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO NRC/SFPO Transnuclear Transnuclear PECO Energy PECO Energy PECO Energy PECO Energy None PHONE NUMBER 301-415-1085 301-415-8526 301-415-8553 301-415-8535 301-415-8500 301-415-8540 301-415-8560 301-415-2142 301-415-3875 914-347-2345 914-347-2345 717-456-3459 717-456-3013 610-640-6829 717-456-3641 301-515-6398 ATTACHMENT 1
~q-~
NRC Meeting May 8, 1997 TN-32 and TN-68 Casks Agenda
- i.
Amendment to TN-32 Topical Report to Store Higher Burnup Fuel and Burnable Poison Rod Assemblies Ii.
Lengthening of the TN-32 Cask to Accommodate Fuel with Control Rod Assemblies Ill.
Subpart K Submittal IV.
TN-68 Cask to Store BWR Assemblies V.
Schedule VI.
Summary/Conclusions ATTACHMENT 2
"1 094ýTRANSNUCLEAR TN 32. SPENT FUELSTORAGE CASK PROTECTIVE COVER DRAIN ORIFICE NEUTRON SHIELDING CONTAINMENT VESSEL JLTILAYER STEEL BODY NEUTRON SHIELDING OUTER SHELL
Amendment to TN-32 Topical Report to Store Higher Burnup Fuel and Burnable Poison Rod Assemblies
- 1.
Currently Licensed Fuel Parameters 40,000 MWD/MTU Burnup 3.85 w/o U235 Initial Enrichment, Maximum 7 year cooling time, minimum 15 x 15 and 17 x 17 Westinghouse Fuel Assemblies 27.1 kW If.
New Fuel Parameters 45,000 MWDIMTU Burnup 4.05 w/o U235 Initial Enrichment, maximum 7 year cooling time, minimum 15 x 15 and 17 x 17 Westinghouse Fuel Assemblies; Also Include B&W MKBW 17xl 7 assemblies 31.5 kW With or Without Burnable Poison Rod Assemblies
Amendment to TN-32 Topical Report to Store Higher Burnup Fuel and Burnable Poison Rod Assemblies Ill.
New Analyses A.
Structural
- Evaluation of Increased Weight of Fuel Assemblies due to Inclusion of BPRA's B.
Shielding
" Gamma shielding reevaluated
" Neutron shielding reevaluated
" Occupational dose rates revised as necessary C.
Criticality
" New analysis to evaluate new fuel parameters
" New analysis performed modeling BPRA's D.
Thermal
" New Analysis performed for higher fuel assembly heat load
" Include effective conductivity for fuel assembly and helium within the basket cavity.
" Credit taken for radiation heat transfer between the basket rails and the basket
" Credit taken for basket contacting bottom of cavity; no credit taken for fuel contacted bottom of cavity.
- Credit taken for heat transfer through the top of the cask E.
Operations No Changes.
Lengthening of the TN-32 Cask to Accommodate Fuel with Control Rod Assemblies (TN-32L)
- 1. Design Changes
" Length of cask cavity increased to 173 inches
" Basket Cell Opening increased from 8.7 inches to 8.8 inches
- Thickness of Aluminum Plates in basket reduced from 0.5 inch to 0.38 inch
" Increase Borated Aluminum thickness to 0.075 inches from 0.04 inch and allow Boral to be used as substitute material (No change in areal density of boron)
If.
New Fuel Parameters Contents to be stored would include:
15 x 15 B&W Fuel with or without NFA Hardware including BPRA's, Axial Power Shaping Assemblies, Control Rod Assemblies 15 x 1S and 17 x 17 Westinghouse Fuel Assemblies With Control Rod Assemblies
- 40,000 MWDIMTU Burnup
- 3.85 w/o U235 Initial Enrichment, maximum
- 10 year cooling time, minimum
Lengthening of the TN-32 Cask to Accommodate Fuel with Control Rod Assemblies (TN-32L)
Ill.
New Analyses A. Structural
- Design Criteria consistent with Approved TN-32 Topical Report
- Cask ANSYS Model revised to incorporate longer length
- New Basket ANSYS Model to incorporate larger cell size, reduced aluminum thickness, new fuel parameters and revised fuel temperatures B. Shielding
" Perform New Source Term Calculations
" Evaluate effect of reduction in basket aluminum thickness C. Criticality
- New analysis to evaluate new fuel parameters and control rod assemblies D. Thermal
" New Analysis performed for higher fuel assembly heat load
" Include effective conductivity for fuel assembly and helium within the basket cavity.
" Credit taken for radiation heat transfer between the basket rails and the basket
- Credit taken for basket contacting bottom of cavity; no credit taken for fuel contacted bottom of cavity.
" Credit taken for heat transfer through the top of the cask E. Operations - No Changes
Subpart K Submittal
- i.
Length of Time Required For Approval II.
Required for BWR Cask, TN-32L and Already Approved TN-32 Topical Report
- 1.
Process to Amend or Update Subpart K Certificate
~Rw TN-68 Cask to Store BWR Assemblies
- 1.
Fuel to Be Stored
- 40,000 MWd/iMTU maximum burnup
- 3.3% maximum initial enrichment
- 25 kw maximum heat generation
- 10 year minimum cooling time
- 7x7, 8x8, 9x9 and 1 Ox10 assemblies
- with or without channels
- 680 lbs with channels
- 11.
Design Criteria
" NUREG -1536
" ANSIANS 57.9
" Containment Vessel
" Basket
" Gamma Shielding
" Trunnions Ill.
Cask Characteristics ASME Code Section i1i, Subsection NB ASME Code Section Ill, Subsection NG ASME Code Section VIII ANSI N 14.6 Capacity Empty Weight Loaded Weight Closure Seals Penetrations Fuel Cell Opening 68 BWR assemblies 94.3 tons 117.4 tons Bolted; No on-site welding Double Metallic O-Rings Two in Lid for Draining and Venting 6.0 inches square
4 I
-225.00* 127-111) REP FIGURE WITHHELD UNDER 10 CFR 2.390
TN-68 TOP VIEW BASKET INSTALLED RAIL BASKET RAIL RESIN ALUMINUM BOXES 1/2" OUTER SHELL SA516. GR.70
1/4 SECTION OF TN-68 BASKET ALUMINUM BASKET INSERT KEYWAY (IN ALUM. INSERT)
ALUMINUM BASKET INSERT
-I"-8UNC WELD STUD SHIM STOCK CASK
TN-68 BASKET PLATE SECTION
.375' ALUMINUM
.075" BORATED ALUMINUM 5.407 BORATED ALUM.
1*.72" REF.
FIGURE WITHHELD UNDER 10 CFR 2.390
DESIGN DIFFERENCES BETWEEN TN-68 CASK AND TN-32 CASK
- Dimensional Differences in Cask Body (Accommodate BWR fuel parameters)
- Basket Rails attached to Basket, Rather than Cask Wall (Simplicity in Fabrication and Holding Tolerances)
- Basket Plug Welds in Center of Cell (Required due to Reduced Cell Size)
COMPARISON OF TN-68 AND TN-32 CASKS TN-68 TN-32 CAVITY SIZE Length Diameter SHELL THICKNESS Containment Gamma Shield Neutron Shield BOTTOM Containment Gamma Shield LID Containment Gamma Shield Neutron Shield LID BOLTS 178.0 69.75 163.25 68.75 1.5 7.5 4.25 1.5 8.0 4.0 1.5 8.25 1.5 8.75 4.5 4.5 4.5 4.5 6.0 4.5 Quantity Size 48 1.5-8 UNC x 6.5 48 LG BASKET Compartment Size
- of Compartments 6.0 sq.
68 8.70 sq.
32
FUEL PARAMETERS TN-68 BWR FUEL 3.3 WT% U235 INITIAL ENRICHMENT, MAX.
40,000 MWD/MTU BURNUP, MAX.
10 YEARS MINIMUM DECAY TIME 25 KW MAX DECAY HEAT PER CASK TN-32 PWR FUEL 3.8 WT% U235 INITIAL ENRICHMENT, MAX.
40,000 MWD/MTU BURNUP, MAX.
7 YEARS MINIMUM DECAY TIME 27 KW MAX DECAY HEAT PER CASK
MATERIALS (IDENTICAL TO TN-32 MATERIALS)
CONTAINMENT GAMMA SHIELDING NEUTRON SHIELD Radial Top TRUNNIONS LID BOLTS BASKET RAILS BASKET Compartment Boxes Plates SA-203 GR A or D SA-350 LF3 SA-105 OR SA-516 GR 70 Borated Polyester Polypropylene Resin SA-105 SA-320 GR L43 6061-T6 Aluminum SA-240 TP 304 6061-T6 / BORAL or Borated Aluminum
DESIGN LOADINGS NORMAL CONDITIONS 100 PSIG INTERNAL PRESSURE AMBIENT TEMPERATURE -200 TO 100°F SOLAR HEAT LOAD 1475 BTU/ft2 25 PSIG EXTERNAL PRESSURE BOLT PRELOAD GRAVITY
ACCIDENT LOADINGS HANDLING ACCIDENT 18 inch vertical drop on bottom onto 3 ft concrete pad Tipover SEISMIC LOADING 0.12 G Horizontal 0.08 G Vertical TORNADO WINDS 360 mph 3 psi pressure differential TORNADO MISSILES 1800 kg Automobile 125 kg 8 in diameter artillery shell 1 in solid steel sphere All missiles impact at 126 mph horizontal FLOOD 50 ft. immersion MINOR FIRE 200 gallon fuel fire
Schedule Submittal Date Initiate Storage TN-32 Amendment 7/97 611999 Subpart K 7/97 5/2000 TN-32L 1998 2004 TN-68 9/97 4/2000 Fabrication Time 18 months