ML20046B520
| ML20046B520 | |
| Person / Time | |
|---|---|
| Site: | 07109256 |
| Issue date: | 08/02/1993 |
| From: | Mellor R YANKEE ATOMIC ELECTRIC CO. |
| To: | Chappell C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20046B521 | List: |
| References | |
| BYR-93-056, BYR-93-56, NUDOCS 9308050003 | |
| Download: ML20046B520 (5) | |
Text
YANKEE ATOMIC ELECTRIC COMPANY
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August 2,1993 BYR 93-056 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Mr. Cass R. Chappell, Section I2ader Cask Certification Section Storage and Transport Systems Branch
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Division of Industrial and Medical Nuclear Safety Office of Nuclear Materials Safety and Safeguards
References:
(a)
Docket No. 71-9256 i
(b)
Letter, J. Thayer, Yankee Atomic Electric Company, to R. Bernera, U.S. Nuclear Regulatory Commission, dated April 12,1993
Dear Mr. Chappell:
Subject:
NRC REQUEST FOR ADDITIONAL INFORMATION - CERTIFICATE OF COMPLIANCE In a meeting between the Office of Nuclear Materials and Safeguards and Yankee Atomic Electric Company (YAEC) on March 23,1993, the Staff requested additional information regarding the adequacy of the road and private bridge which will be i
traversed by the hydraulic transporter during the transport of the steam generators from the Yankee Nuclear Power Station (YNPS) site to the rail line.
In response to the Staff's request, we are submitting the following calculations and reports for your review.
Enclosure m YAEC Calculation YRC-1027, R.evision 0, " Evaluation Of River Road For Transport Of Heavy Loads From The Component Removal Project" This calculation presents the results of analyses performed for all buried pipe and other conduit in the road between the YNPS site and the Hoosac Tunnel. It is based upon a field walkdown, performed by YAEC engineers, of the entire six mile route. The calculation was prepared in accordance with the " Standard Specifications for Highway Bridges," 15th edition, as adopted by AASHTO.
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i U.S. Nuclear Regulatory Commission Docket No. 71-9256 August 2,1993 Page 2 Our at:alyses concluded that all the buried conduit along the travel route can adequately support the transporter loads. The buried conduit consists mainly of corrusated metal drainage pipe of various sizes. There is also some water and sewer pipe near the center of Monroe Bridge. This pipe is well below grade.
There is also a large concrete box culvert which carries water from the Deerfield i
River to Canal No.1. It is owned by New England Power Company. This, too, is well below the road grade and not affected by the steam generator transport.
i Only one subgrade structure, a stone arch culvert with about 11 feet of soil cover, located near the Hoosac Tunnel, required additional evaluation. Although it currently handles truck traffic on a daily basis, YAEC will bridge or brace this 6 foot wide structure with steel beams and platework as a safety precaution.
The field walkdown identified a section of roadway near Canal No. I which is situated along a relatively steep embankment. Upon further investigation we determined that both New England Power Company and the Commonwealth of Massachusetts had utilized the services of GEI Consultants, Inc. to evaluate the subsurface conditions in this area for work each party has in progress. YAEC l
requested that GEI perform a specific evaluation of the steam generator haul utilizing data which GEI had recently obtained for these other projects. The results of GEI's slope stability analyses are contained in Enclosure (2).
t Enclosure (2)
GEI Consultants, Inc., letter report entitled, " River Road Stability - Transportation Of Steam Generator, Monroe, l
Massachusetts" GEI evaluated that section of the roadway which YAEC determined during its walkdown to be the most critical section for slope stability reasons. GEI concluded that the steam generator transporter can travel over the subject section of roadway with an acceptable margin of safety.
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Enclosure (3)
YAEC Calculation YRC-1011, Revision 1, "Sherman Dam Spillway Bridge - Analysis Of Temporary Bridge For Steam Generator Transport" i
This calculation presents the results of an analysis of a temporary bridge system which will be used to span the existing bridge over the Sherman Dam spillway.
The existing bridge is owned by New England Power Company. YAEC engineers evaluated the existing bridge and concluded that the bridge would support loads
l U.S. Nuclear Regulatory Commission Docket No. 71-9256 August 2,1993 Page 3 i
less than the transporter loads. As an alternative, YAEC will install a temporary system of beams over the existing bridge; this temporary bridge system will not '
result in any additional load on the spillway bridge. A similar bridge spanning was performed during the Millstone 2 steam generator replacement project.
The temporary beams will be supported at each end by the existing bridge abutmt,nts. New England Power Company requested that GEI evaluate the safety i
of using this temporary bridge system. GEI performed analyses of both abutments and the underlying rock. GEI issued separate reports on each abutment and summarized their results in Enclosure (4).
7 Enclosure (4)
GEI Consultants, Inc., letter report entitled, " Proposed j
Modifications Of Temporary Bridge Submittal - Sherman Dam Spillway Bridge Sherman Station Monroe, Massachusetts" We plan to support the temporary bridge on the existing bridge abutments in accordance with gel's suggestions. Both abutments are founded on rock which constitute the side walls of the Sherman Dam spillway. The rock beneath the west abutment was strengthened with rock bolts after the spillway was enlarged in 1991. GEI evaluated the stability of the rock beneath both abutments and determined that it was satisfactory. GEI recommends that prior to the first steam generator shipment, the rock bolts be inspected and tested to assess rock bolt performance and adjusted as necessary; this will be done under the direction of New England Power Company and their consultant.
Enclosure (5)
GEI Consultants, Inc., letter report entitled, " Evaluation Of Stability - Sherman Dam Transportation Of Steam Generator f
Monroe, Massachusetts" The initial part of the haul route from the YNPS site is over the road which is on the Sherman Dam crest. This final enclosure presents the results of an evaluation of the dam by GEI. It was conclasd that the dam can support the steam generator transporter load with an acceptable margin of safety.
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U.S. Nuclear Regulatory Commission Docket No. 71-9256 August 2,1993 Page 4 It is our understanding from the March 23rd meeting that NRC will forward these documents to the Federal Highway Administration for an independent assessment. It is also our understanding that if issuance of the Certificate of Compliance precedes completion of the Federal Highway Administration assessment, then the Certificate will be conditioned to require confirmation by the Federal Highway Administration of the adequacy of the road / bridge prior to transport of the steam generators.
In addition to the enclosed copy of the subject calculations and reports, we are providing five copies of the same enclosure under separate cover to Ms. Nancy Osgood, Project Manager. If you should have any questions regarding the road / bridge calculations and reports, please contact me at 508-779-6711.
Sincerely, YANKEE ATOMIC ELECTRIC COMPANY h
1 Russell A. Mellor Project Manager Yankee Rowe Project c:
N. Osgood, NRC, NMSS (Letter + 5 copies of Enclosures)
M. Fairtile, NRC, NRR (w/o Enclosures)
E. Kelly, NRC Region I (w/o Enclosures) l l
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