ML20032D837
| ML20032D837 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/28/1981 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8111180070 | |
| Download: ML20032D837 (5) | |
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GEdison TERA Docket No.: STN 50 482 JHopkins NRC/PDR MRushbrook L/PDR SHanauer NSIC RVollmer TIC lir. Glenn L. Koester Vice President - Muclear T!!urley ACRS(16)
RMattson Kansas Gas and Electric Company 201 North Market Street RHartfield, itPA Wichita, Kansas 67201 OELD OIE (3)
Dear Mr. Koester:
BJElliot Subj ect: Request for Additional Infomation for the Review of the Wolf Creek Plant, Unit 1 Regarding !!aterials Engineering As a result of our continuing review of the llolf Creek Plant, Unit 1 FSAR, we find that we need additional infomation to complete our evaluation. The specific infornation required is in the area of naterials engineering and is presented in the Enclosure.
To naintain our licensing review schedule for the Wolf Creek Plant FSAR, we will need responses to the enclosed request by !!ovember 13, 1981.
If you cannot teet this date, please infom us within seven days af ter receipt of this letter of the date you plan to suteit your responses so that we nay review our schedule for any necessary changes.
Please contact Dr. G. E. Edison, Volf Creek Licensing Project Manager, if you desire any discussior, or clarification of the enclosed request.
Sincerely, O DI.ll%,
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"Origirmi signed by
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B. J. Youngblood D. J. Youngblood, Chief a
t Ny g0 0'l, g m bj Licensing Branch No. I h!
Division of Licensina
Enclosure:
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As stated cc: See next page Op{0o 8
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NRC FORM 318 (10-80) NRCM O240 OFFICIAL RECORD COPY, usom.mi-m. a
r Mr. Glenn L. Koester Vice President - Wuclear Kansas Gas and Electric Company 201 North Market Street Post Office Box 208 Wichita, Kansas 67201 cc: Mr. Nicholas A. Petrick Ms. Wanda Christy Ex~ecutive Director, SNUPPS 515 N. Ist Street 5 Choke Cherry Road Burlington, Kansas 66839 Rockville, Maryland 20750 Eric A. Eisen, Esq.
Mr. Jay Silberg, Esquire Birch, Horton, Bittner & Moore Shaw, Pittman, Potts & Trowbridge 1140 Connecticut Avenue, N. W.
1800 M Street, N. W.
Washington, D. C.
20036 Washington, D. C.
20036 Kansas for Sensible Energy Mr. Donald T. McPhee Post Office Box 3192
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Vice President - Production Wichita, Kansas 67201 Kansas City Power and Light Company 1330 Baltimore Avenue Post Office Box 679 Kansas City, Missouri 64141
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Ms. Mary Ellen Salva Route 1, Box 56 Burlington, Kansas 66S39 A. Scott Cauger, Esq.
Assistant General Counsel Public Service Commission P. O. Box 360 Jefferson City, Missouri 65102
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Mr. Tom Vandel Resident Inspector / Wolf Creek NPS c/o U.S.N.R.C.
Bost Office Box 1407 v poria, Kansas 66801 m
x Mr., Michael C. Kenner Wolf Creek Project Director State Corporation Commission State of Kansas Fourth Floor, State Office Bldg.
Topeka, Kansas 66612 O
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l ENCLOSURE REQUEST-FOR ADDITIONAL'INFORMATION WOLF CREEK UNIT NO. 1
'251'. 0WC Materials Engineering Branch 251.1WC ~ To demonstrate compliance with the beltline material. test requirements of Paragraph II.C.2 of Appendix G, 10 CFR Part 50:
a.
Provide a schematic for the reactor vessel showing all welds, plates.
and/or forgings in.the beltline.
Welds should be identified by shop control number, weld procedure qua,lification number, the heat of filler
. metal, and type of and lot-of flux.
Provide..the chemical composition for
. r these welds (particularly.Cu, P, and S content).
b.
Indicate the post-weld heat treatment used in the fabrication of the test welds.
c.
Indicate the plates used to fabricate the test welds.
d.
Indicate whether the test specimen for the longitudinal seams were removed from excess material and welds in the vessel shell course-following completion of the longitudinal weld points.
s 251.2WC To demonstrate compliance with the fracture tougness requirements of Paragraph IV. A.1 of Appendix G,10 CFR Part 50:
a.
Provide the RT f r all RCPB welds which may be limiting for operation NDT of the reactor vessel.
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b.
Indicate whether there are any RCPB heat-affected zones which require CVN impact testing per Paragraph NB-4335.2 of the 1977 ASME Code.
Provide CVN impact test data for these heat-affected zones which may be limiting for operation of the reactor vessel.....
c.
Indicate that there are no ferritic RCPB base metals other than in vessels which require fracture toughness testing to NB-2300 of the ASME Code.
If there are ferritic RCPB base metals other than in vessels which require fracture toughness testing to NB-2300 of the ASME Code, provide CVN impact and drop weight data for all materials which will be limiting
' for operation o'f' the reactor vessel.
J Provide actual pressure temperature limits for Wolf Creek Unit 1 based 251.3WC
'upon' the limiting fracture toughness of the reactor vessel material and the predicted shift in the adjusted reference temperature, RTNDT, resulting from radistion damage.
The pressure-temperature limits for the following conditions must be included in the technical specifications when they are submitted:
or 1.
Preservice hydrostatic tests, 2.
Inservice leak and hydrostatic tests, 3.
Heatup and cooldown operations, and 4.
Core operation.
251.4WC Provide full CVN impact curves for each weld and plate in the' beltline region.
Provide the data in tabulated and graphical form.
~251.5WC To demonstrate the surveillance capsule program complies with Paragraph II.C.3 of Appendix H:
l a.
Provide the withdrawal schedule for each capsule.
i b.
Provide the lead factors for each capsule.
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l c.
Indicate the estimated reactor vessel end of life fluence at the 1/4 wall thickness as measured from the ID.
251.6WC Identify the location of each material surveillance capsule and the materials in each capsule.
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1-c.
For each base metal and heat-affected zone surveillance specimen provide the specimen type, the orientation of the specimen relative to the prin-cipal rolling direction of the plate,'the heat number, the component code number from which the sample was removed, the chemical composition espec-ially the copper (Cu) and phosphorus (P) contents, the melting practice and the heat treatment received by the sample material.
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b.
.For each weld metal surveillance specimen, provide the weld identification from which the sample was removed, the weld wire type and heat identifica-
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tion, flux type and lot identifiction, weld process and heat treatment used for fabrication of th'e weld sample.
c.
Provide a sketch which indicates the azimuthal location for each capsule relative to the reactor core.
251.7WC Indicate the normal operating temperature of the flywheels and provide CVN impact and drop weight test data from each flywheel that indicates the RT f the flywheels are at least 100*F less than their normal operating KDT terperatures.
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