ML20248D538
| ML20248D538 | |
| Person / Time | |
|---|---|
| Issue date: | 08/01/1989 |
| 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 8908110070 | |
| Download: ML20248D538 (9) | |
Text
{{#Wiki_filter:, s ?( g e AUG 0116 JR/ MEETING WITH NUTECH Project No. M-49 MEMORANDUM FOR: Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety FROM: John P. Roberts Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety l
SUBJECT:
MEETING WITH NUTECH, INC. DATE/ TIME: July 27, 1989; 2:00 p.m. LOCATION: Room 6D17, One White Flint North Building, Rockville, Maryland ATTENDEES: NRC NUTECH JRoberts WMcConaghy PURPOSE: To discuss spent fuel storage compatibility L Discussion: NUTECH had learned (from one of its attendees) of a meeting on July 26, 1989, with Virginia Electric and Power Company in which spent fuel storage compatibility had been discussed. NUTECH asked for a meeting to keep up with developments. NUTECH is concerned with developing a method to be ab?e to ship NUHOMS canisters directly off reactor sites and recentl Material Safety and Safeguards (NMSS) y met with NRC's Office of Nuclear Transportation Branch (SGTB) on this matter. I referred NUTECH to SGTB on the matter of a multiple barrier and satisfying 10 CFR Section 71.55. NUTECH's NUHOMS-24P canister is being included by Department of Energy for consideration in its " Specialty Cask" program for its i repository transportation cask fleet. NUTECH provided a copy of a letter with enclosed article. Fuel loading of all eight modules has been completed at Carolina Power and Light Com Storage Installation (ISFSI)pany's.H.B. Robinson Independent Spent Fuel Dose rates are shown in the article. Actual dose rates appear to be lower than predicted. With experience, NUTECH noted that occupational dose per cr.nister loaded has dropped to less than 1 man-rem. l Most of the occupational dose is traceable to canister welding. 1 OFo3 8908110070 890801 PDR FROJ ilt PDC M-49
>:,., ;n m .x 1 _jk ~ -? 1 .j 'JR/NEETING.WITH NUTECH j. NUTECH believes that t' he occupational dose can be further reduced considerably in future operations. 4 . Original Signed by. l John P. Roberts - l John P. Roberts, Section Leader .O Irradiated Fuel Section i Fuel Cycle Safety Branch E
Enclosure:
NUTECH Letter with Article I Mrit;.th::: i Project _M-49 PDy. NRC File Center Febb K/ r IMSB R/F IMIF R/F. 4 JRoberts: JSchneider FSturz-KCleu FBrown GBeveridge/SCornell 1-23 (VK) 0FC
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- MI NAME-'
- J berts:jc n
~ ..---:-..---------{7c//89 DATE;:7//l/89 N/
1. ne 145 MARTINVALE LANE e SAN JOSE, CALIFORNIA 95119 e PHONE: (4081 629 9800 TELEX: (RCA) 278971 e TELECOPY: (408) 281 6106 July 17,1989 WJM-89-137 Mr. Robert K. Kunita Carolina Power and Light Company l Post Office Box 1551 Raleigh, NC 27602
Subject:
NUHOMS8-07P Article for " Nuclear Engineering International" Magazine
Dear Bob:
Thank you for your quick review and approval for release of the subject article. I am making the minor changes you suggested. Enclosed for your information is a final draft copy of the article with a better copy of the photographs. Very truly yours, GhMcC=0 William J. McConaghy, P.E. Vice President, Waste Management Business Unit WJM/d Enclosure bc: M. Taylor, Jr.
.j. ~, L (TITLE) CP&L COMPLETES LOADING OF SPE!<T FUEL INTO NUHOM5 tm) DRY STORAGE SYSTEM AT ROBINSON (SUDTITLE) Caro,11na Power and Light has recent3y enmpl?ted the successful loading of SG P9R fuel assemblies into the NUHOMS dry storage system. This U.S. Department of Energy demonstration program is playing a major role in advancing the-development of dry storage technology. In-mid March 1989 the first NUHOMS-07P stainless steel canister CLntaining seven irradiated PWR fuel assemblies was successfully tranri*cred into a concrete horizontal storage module (HSM) at the H. 8. Robinso., site. By e6*ly July the three modules included in the demonstration program were loaded, along with five additional modules. With the completion of loading of these modules, an important milestone was achieved in the demonstration of NUHOMS concrete modular storage of spent fuel. Demonstration Program Background. In March 1984, CP&L entered into a cooperative agreement with the'U.S. Department of Energy (DOE) to
- enduct a demonstration program of the NUTECH Horizontal Modular Storage (NUHOMS) System at their H.
B. Robinson site. The Electric Power Research Institute and NUTECH also were participants in the demonstration program, with NUTECH providing the necessary design and licres'ng support for the system. NUTECH submitted a Topical Report for :P s generic design in November 1984 and CP&L submitted the 10 CFR 72 ;it e license application in February 1985. NRC approval for the NUHOMS-07P Topical Report was received in March 1986, followed shortly 'thereafter ey CPSL's site license approval j, August 1986. Design, Fabrication, and Construction. The NUHOMS system is designed to provide long term dry storage of irradiated fuel assemblies, The ruel assemeltes are confined in a helium atmosphere within a stainles: steel canister. When placed in storage, the carister is protected and chfelded by the reinforced concrete storage mocule structure. The module provides the necessary shielding while decay heat is removed by cassive ventilation, and radiation to and conduction through the walls and roof. With the passive ventilation heat removal, air flows through, l 'nlet vents located or, the lowe. front wall of the module, up around l the canister. and exits througF outlet vents in the module roof. Thp construction of the HSMs was carried out by CP&L in se.eral phases. Soil sampling and testing war first perfe T.ed to select the site for the storage facility, The area for the HSM; was excavated and forms I were placed for the foundation slab. Once the foundation slab i placement was completed, the installation of wall reinforcement, embedments, and formwork proceeded. Prior to placement of concrete fo-the walls and roof, approximately 50 thermocouple were installed for the purpose of measuring concrete tempera *ures with fuel loaded in canisters. Two of the' canisters also contained thermocouple for measurement of fuel assembly and structural compenent temperatures. Fabrication of the three demonstration progran and five exoansion progr-' cenisters was performed by Equipos Nucleares, S.A. in
_y L d /*. 31 k 3-Santander, S c a i.1 The' canisters were #abricated in accordance wit,~t"a ASME. Code, Section III and then delivered to the site to begin tha necessary QC inspections, and system checkout' activities. The transfer equipme-t, which consisted of'a transfer trailer, transfer
- kid,and hydrauiSc ram for canister insertion into'the module was also procured, delivered to the site and checked out in trial runs in
'accordance with CP&L procedures. The cask utilized for the transfer operations from the fuel building to the independent spent fuel storage ! installation (ISFSI) was an !F-300 shipping cask. The IF-300 cask, although certified for,off-site transportation of spent' fuel, was utilized for en-site' transfer 'n acccrdance with the requirements of 10 CFR 70. Fuel Loading Operations. The feel transfer operati ns began in the fuel building with the piscement of seven irradiated PWR fuel - assemblies into the canister contained within the cask. The assemblies had been irradiated in the H. B. Robinson reactor to approximately 00,000 to 34,000 MWO/MTU, and subsequently cooled in the spent fuel .oool for 5 years, resulting in decay heat values of.80 to.86 Kw/ assembly. Following placement of a lead shield plug in the canister, the cask / canister was removed from the spent fuel pool'and moved to the cask decontamination area. In the decon area the shield plug was welded, and the canister was subsequently drained, vacuum dried and backfilled with helium. After the necessary weld dye penetrant examinations and helium leak checks'of the lead shield plug-weld, the canister cover plate was welded to the canister and additional dye penetrant examinations were completed. Following installation of the cask bolted head and completion of the normal cask surface decontamination activities, the cask and canister were then ready for the short journ,y on the transfer trailer from the fuel building to the horizontal storage module. At the horizontal storage module, the cask head was removed, the cask was aligned ~with the module and the hydraulic ram was extended for ths
- ansfer cperation.
A grapple on the end of the ram engaged the canister and the ram pulled it into the module. The trar.Jfer Operations at the module took but a few hours. The entire fuel 1:adin; and transfer sequenca for a canister ton', m five days. Fuel ^ loading of subsequent canisters continued until al' eight modules
- a e
- adsd with NJHOM3
.,7P canisters. A total of 55 irradiated fuel a:cmblies are.now stored in the NUHOMS-07P system at Robinsen. Demonstration Program Results. as part of the c:: perative agreement, the measured results of the NUHOMS-07P demonst ation program will bc
- ublished in upcoming reports by the Electric Power Research Institute.
Topics to be addressed include operations sequences, occupations' axcosare, measured thermal performance, and measured shielding L performance. Initial radiation measurements taken at the horizontal l mcdule storage location shortly after the first canister was leaded showed very low contact radiation levels. Figure 1 shows ths
- cmcarison of the measured results with the technical specification limits.
fte shielding performance of the reinforced concrete has bec-
- hown.c ae very effective.
Initial thermal results also show amole margin, demonstrating the capability of NUHOMS to store future nigher E
[.. ;. l \\ 1 l turnue fuels ..:w tein; planned par :: many 33;;or3, The Future of NUHOMS Technology, a site license application er u:e :r the NUHOMS-07P system at CP&L's Brunswick plant has been submitted to the NRC and is currently under review. Subsequent to the complett:n of the NUHOMS-07P design, a larger version =f the same system. which held: 24 PWR or 52 BWR fuel assemblies, was : mpleted by NUTECH for application.at other plants considering on-site dry storage. The NUHOMS-24P system was documented in a new Tooical Report which was submitted to the NRC in February 1988, and approved by the NRC in Apri' ?989. The larger system was selected by Duke Power for use at their Oconee Nuclear Generating Station beginning in January 1990. (NE!, Fabruary 1989) Duke received their NRC site license acproval in July 1999, and construction of the facility is nearing completion. Saltimore Gas & Electric is also planning cn utilizing the NUHOMS-24P system at their Calvert Cliffs Plant. A site license 'pplication 1 zurrently being prepared and is expected to be submitted within a few l 1 i
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g. h A!R:NLET Q = h HSM WALL DRY SHIELDED CANISTER SURFACE DOSE RATES ACTUAL UCENSE h AIRINLET(LOCAL) 1315 MR/HR 200 MR/HR h AIREXiT(LOCAL) 40 MRHR 200 MR/HR h HSM DOOR <4MRHR 200 MR/HR h HSM WALL < 2.5 MR/HR 50 MR/HR h HSM ROOF < 2.5 MR/HR 50 MR/HR 4 I j
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Concrete Horizontal Storage Modules (HSMs) after loading of first two canisters (see closed doors.) Subsequently a!! modules have been loaded. 8' g e p l 's l l li I c ~; M.2 .}}