ML20052G896
| ML20052G896 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/07/1982 |
| From: | Garrity J Maine Yankee |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20052G897 | List: |
| References | |
| MN-82-93, NUDOCS 8205190129 | |
| Download: ML20052G896 (8) | |
Text
.
IENIEM%9?AQllHEE 'AT0lmoPOWER COMPAIW *
,e,,woacEaTennoAo O
ENGINEERING OFFICE FRAMINGH AM M ASSACHUSETTS 017o1 b
617 872 8100 O
nd May 7, 1982 MN 82-93 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch /l3 Mr. Robert A. Clark, Chief
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) MYAPC Letter to USNRC, dated October 5,1981, FMY-81-151
Subject:
Spent Fuel Storage Modification
Dear Sir:
Enclosed are replacement pages for Reference (b).
The information provided in these pages has been previously discussed with the staff and is transmitted to clarify certain details of the subject design.
In addition, three drawin; s are provided, to be included as Attachment III of Reference (b). These c'rawings contain information which is proprietary to Maine Yankee Atomic Power jompany.
In accordance with 10 CFR 2.790 (b)(1),
an af fidavit attesting to t.e proprietary nature of these drawings is attached i
to this letter.
Very truly yours, MAINE YANKEE ATOMIC POWER COMFANY rg/A-John H. Carrity, Senior Di ector Nuclear Engineering and Licensing
\\
RilG:JHG : dad Enclosures
'J cc Listing
[
Page List j
Replacement Pages 4-9 and 4-9a Affidavit Drawings ( 3)*
o 6 }g c, 8205190129 820507 PDR ADOCK 05000309 P
Maina Yankcs Atomic Pawer Corpiny cct Robert M. Lazo, Chairman, Esq.
Office of the Executive Legal Director Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 l
Jay M. Gutierrez, Esq.
Dr. Cadet H. Hand, Jr.
Staff Counsel
, Director, Bodega Marine Laboratory U. S. Nuclear Regulatory Commission University of California Washington, DC 20555 P.O. Box 247 Bodega Bay, CA 94923 Thomas G. Dignan, Jr., Esq.
Ropes and Gray Mr. Peter A. Morris 225 Franklin Street Administrative Judge Boston, MA 02110 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission R. K. Gad, III, Esq.
Washington, DC 20555 Ropes and Gray 225 Franklin Street James E. Tierney, Esq.
Boston, MA 02110 Attorney General Department of the Attorney General David Colton-Manheim State House - Station #6 Box #386, Bedfords Barn Augusta, ME 04333 Gouldsboro, ME 04607 Rufus E. Brown, Esq.
Deputy Attorney General Department of the Attorney General State House - Station #6 Augusta, ME 04333 1
Philip Ahrens, Esq.
l Assistant Attorney General Department of the Attorney General l
State House - Station #6 Augusta, ME 04333 Robert S. Frank, Esq.
Assistant Attorney General Department of the Attorney General State House - Station #6 Augusta, ME 04330 David Santee Miller, Esq.
Counsel for Petitioner 213 Morgan Street, N.W.
Washington, DC 20001 Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, DC 20555 Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, DC 20555
-PAGE LIST All Pages Dated October 5, 1982 Except for the Following:
g Date 4-9 05-07-82 4-9a 05-07-82 4-10 02-10-82 4-10a 02-10-82 4-10b 02-10-82 4-13 02-10-82 4-13a 02-10-82 4-13b 02-10-82 4-14 02-10-82 4-21 02-10-82 4-21a 02-10-82 4-21b 02-10-82 4-21e 02-10-82 4-21d 02-10-82 4-21e 02-10-82 4-41 02-10-82 4-44 02-10-82 4-47 02-10-82 l
4-51 02-10-82 l
l l
MAY 71982 Ill -
uI
4.3.3 QUALITY ASSURANCE 4.3.3.1 Materials 4.3.3.1.1 The ASTM-A666 material is equivalently qualified to the ASME Code, Subsection NF (SA 240 material) with the exception of the higher yield stress (Grade B) which is documented by certified material test reports.
- 4. 3. 3.1. 2 The allowable stresses in the heat af fected zones of the weld and base material, utilizing ASTM-A666 in storage rack construction, are higher than the allowable stresses of ASME-SA240 steel.
Neither the ASME Code or the ASTM Code requires an assumed reduction in yield stength in heat affected zones of the weld and base material. Tests have been performed by the independent testing laboratory on samples of welded A666, Grade B material. These tests indicate an insignificant reduction in yield strength in the Heat Affected Zone of the weld and base metal.
4.3.3.1.3 The material certification records document the yield strength of the material to be less than 90,000 psi.
4.3.3.1.4 in this particular design, the stress corrosion cracking problem is not a concern due to several f
factors. Stress corrosion cracking may occur where j
extensive intergranular precipitation is found in i
combination with tensile stresses. While some
(
residual stresses cannot be avoided in this design, the amount of heat input from welding is small and the rate of cooling is rapid.
Intergranular precipitation occurs when a high temperature -is i
held for a long period of time; i.e.,
a typical sensitizing treatment would be 12000F for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> which will not be the case.
In addition to the above factors, all welds will be made with 308L filler metal and the bottom grid and foot corner casting assembly, on which most of the welding is done, will have a 0.03-percent maximum carbon content. These factors also greatly reduce the level of susceptibility to stress corrosion.
par has manufactured many spent fuel storage modules and other equipment of welded Type 304 stainless steel for nuclear applications with no indication of stress corrosion cracking problems.
4-9 MAY 71982
'4
4.3.3.1.5
- faine Yankee will document all of the above as part of the normal design process. This documentation will be iceluded in the final design package and will be available.on-site for inspection.
4.3.3.2 Fabrication and Installation Requirements All. welders and welding procedures shall be qualified in accordance with ASME Section IX.
Tack welds that.are incorporated into the final weld shall-be, at a minimum, visually examined, and defective tacks removed.
All weld filler metals shall meet the chemical and mechanical requirements of the applicable filler metal specifications as noted in ASME Sections II, Part C.
Acceptance standards for discontinuities in the castings, including size and frequency per unit area and location shall be in accordance with ASME Section III, Subsection NF for Class III supports.
The exttnt and f requency of ret. airs, and method of inspection of repaired areas shall be in accordance with ASME, Section j
III, Subsection. NF for Class 3 supports.
l 4.3.3.3 Inspection, Examination and Test Requirements 4.3.3.3.1 General Examinations, measurements or tests shall be performed for each work operation where necessary to assure quality.
Inspection frequency and type shall be, at a minimum, in accordance with ASME Section III, NF for Class 3 supports.
4.3.3.3.2 Dimensional Verifications of Spent Fuel Modules Each cell of the spent fuel module will be inspected using a dummy fuel bundle sized to assure the minimum required square opening-including allowances for squareness, twist, and bow.
I 4-9a MAY - 7.1952
AFFIDAVIT PURSUANT
'TO 10CFR2.790 Yankee Atomic Electric Company)
Nucle,ar Services Division
)
Commonwealth of Massachusetts )
Middlesex County
)
SS.:
I, W. P. Johnson, depose and say that I am the Vice President of Maine Yankee Atomic Power Company duly authorized to make this affidavit, and have reviewed, or caused to have reviewed, the information which is identified as proprietary. I am submitting this affidavit in conformance with the provisions of 10CFR2.790 of the Commission's regulations for withholding chis information.
The information for which proprietary treatment is sought is contained in:
l DrawinF !!Y-D-00-014-2 " Grid Assembly" l
Drawing MY-D-00-015-2 " Cage Assembly" Drawing MY-D-00-016-6 " Miscellaneous Details" Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Conunission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above-referenced document, should be wi thheld.
1.
The information sought to be withheld from public disclosure are drawings of the components which will comprise a fuel pin storage assembly which is cuned and has been held in confidence by Maine I
Yankee Atomic = Power Company.
2.
The material contained in this transmittal was obtained at considerable expense to Maine Yankee Atomic Power Company, and the release of which would seriously affect our competitive position.
3.
The material contained in this transmittal 's of the type customarily held in confidence and not customarily disclosed to the public.
4.
This information is being transmitted to the Commission in confidence under the provisions of 10CFR2.790 with the understanding that it is to be received in confidence by the Commission.
5.
This information is for Commission internal use only and should not be released to persons or organizations outside the Directorate of Regulation and the ASLB without prior approval of Maine Yankee Atomic Power Company. Should it become necessary to release this information to such persons as part of the review procedure, please
contact Mains Yankme Atomic Powsr Cospiny, and they will aske ths necessary arrangements reouired to protect their proprietary interests.
6.
Further the deponent sayeth not.
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/
Gh W. P.
hnson Sworn to before me this 7th day of May, 1982,
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=c'l Robert H. Groce Notary Public
- ri L.ny j,
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My Commission Expires September 14, 1984 s6'
.p n 99#
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I
' iWithhold Attachment
'From Public Disclosure 2.790 Information ATTACHMENT III Drawing MY-D-00-014-2 " Grid Assembly" l
Drawing MY-D-00-015-2 " Cage Assembly" Drawing MY-D-00-016-6 " Miscellaneous Details" Withhold Attachment From Public Disclosure MAY 71982
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