ML19318C270
| ML19318C270 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/17/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 8007010287 | |
| Download: ML19318C270 (5) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION 3 J'
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V J'3 1 7 590 Docket No. 50-364 Mr. F. L. Clayton, Jr.
Senior Vice President Alabama Power Company 600 North 18th Street Birmingham, Alabama 35291
Dear Mr. Clayton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR FARLEY 2 OPERATING LICENSE APPLICATION As a result of our continuing review of the operating license application for j
the Joseph M. Farley Nuclear Plant Unit 2, we' have developed the enclosed i
request for additional information. This information was discussed in a telephone conversation with your representatives on May 23, 1980.
Please provide the information requested in the enclosure. Our review schedule is based on the assumption that the additional information will be available for our review by June 27, 1980. If you cannot meet this date, please inform as within 7 days after receipt of this letter so that we may revise our scheduling.
Sincerely.
. g.,.,
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A. Schwencer, Chief l
Licensing Branch No. 2 Division of Licensing
Enclosure:
Request for Additional Infonnation cc: See next page 8007010 ff7
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Mr. F. L. Clayton, Jr., Senior Vice President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 cc: Mr. Alan R. Barton Executive Vice President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 Mr. Ruble A. Thomas Vice President Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Mr. George F. Trowbridge Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036
6-ENCLOSURE REQUESTS FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 DOCKET NO. 50-364 Requests from the following branch in NRC are included in this enclosure.
Requests and pages are numbered sequentially with respect to requests transmitted following issuance of SER Supplement No. 3.
Branch Page No.
Materials Engineering 121.6 1 21.7 i
I
1 121-6 121.0 MATERIALS ENGINEERING BRANCH - INSERVICE INSPECTION SECTION 121.2 Your response to Question 121.1 does not provide sufficient information to comolete our evaluation regarding your preservice inspection program. For each comoonent which cannot be completely examined in accordance with ASME Code Section XI requirements, submit a relief request in accordance with the guidelines in Appendix A of Question 121.1.
Specific information should include the extent of the Section XI requirements that were perfomed, alternative nondestructive examinations, and description of the measures required to perfom the required examinations.
In the case where relief is requested for piping system welds, provide a list of the welds that cannot be completely examined to Section XI requirements.
Where construction code examinations are substituted for preservice examination requirements, in accordance with IWB-2100b and IWC-2100b in Section XI, identify the specific construction code NDE method.
Identify the specific parts of the ECCS and RHRS where IWC-1220(a) and (c) exemptions are used and a preservice examination was not performed.
121.3 For the preservice inspection procram, the following infomation.
necessary to clarify specific ascects of the FSAR and additional information supplied in your letter of Aoril 21. 1980:
(1) A list of all welds, the percentage of volume which can be examined, and alternate examinations to be performed for which Notes 9 and 10 in Table 5.2-33 and Notes 5 and 6 in Table 5.2-34 apply.
(2) The type and extant of examination of the nozzle inner radii region of the reactor vessel, steam generator, and pressurizer, and the nozzle to safe end welds in the steam generator.
(3) A list of all welds in branch pipe connections exceeding 6 inches in diameter for wnich relief is requested. A detailed description or drawing depicting inaccessibility and estimates of the extent of examination as a percentage of total weld volume are required.
(4) Exclusion sizes in the piping pressure boundary you have used based on IWB-1220b of Section XI. Support these sizes with documentation if they are not otherwise exempted.
(5) A list of all Class 2 welds which cannot be examined volumetrically due to thin wall thickness.
(6) A relief request for the charging pump casing welds.
(7) A discussion of the imoact on plant safety of the omission of NDE on nozzle to vessel welds of the residual heat exchanger, as
O 121-7 referenced in Note 3, Table 5.2-34 of the FSAR, and of pressurizer safety welds 7, 9,10, and 11 in additional infomation of your April 21, 1980 letter.
(8) The percentage of weld volumes in the regenerative heat exchanger which can be examined volumetrically.
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