ML19294B815
| ML19294B815 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/20/1980 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Barton A ALABAMA POWER CO. |
| References | |
| NUDOCS 8003060069 | |
| Download: ML19294B815 (6) | |
Text
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,pn nico UNITED STATES
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E ') ')* ( j' ^g NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555 f
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FEB 2 01980 Docket No. 50-364 Mr. Alan R. Barton Senior Vice President Alabama Power Company 600 North 13th Street Birmingham, Alabama 35291
Dear Mr. Barton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR FARLEY 2 OPERATING LICENSE APPLICATION As a result of our continuing review of the operating license application for the Joseph M. Farley Nuclear Plant Unit 2, we Fave developed the enclosed request for additional information.
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 March 17, 1980.
If you cannot meet this date, please inform us within 7 days after receipt of this letter so that we may revise our scheduling.
Sincerely, Jo n F. Stolz, Chief
'ght Water Reactors Branch No.1 Division of Project Management
Enclosure:
Request for Additional Information cc:
See next page 80030600(oq
NB 2 0198r)
Mr. F. L. Clayton, Jr.
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 fir. George F. Trowbridge Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 9
ENCLOSURE _
REQUESTS FOR ADDITIONAL INFORMATION JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 DOCKET NO. 50-364 Requests from the following branches in NRC are included in thic enclosure.
Requests and pages are numbered sequentially with respect to requests trans-mitted following issuance of SER Supplement No. 3.
Branch Page No.
Mechanical Engineering Branch 110-29 110-30 Radiological Assessment Branch 331-1
110-29 110.0 MECHANICAL ENGINEERING BRANCH 110.3 The Mechanical Engineering Branch has recently instituted a program of performing an independent confirmatory piping analysis for plants being reviewed for an operating license.
For Farley 2, this analysis will be performed by our contract personnel at the Pacific Northwest Laboratories.
The purpose of this independent analysis is to verify that the applicant's piping system meets the ASME Code stress criteria.
We do not intend to resolve differences between our calculated stresses and stresses calculated by the applicant unless unusually large discrepancies are found, or unless Code criteria are not met. This program will allow the staff to verify on a sampling basis that the applicant has correctly modeled its piping, has correctly used its computer codes, and has adequately accounted for the as-built condition of the piping systems.
Pr" vide the following information for the "A" Main Steam Line for use our confirmatory pioing analysis.
1.
piping layout and isometric drawings sufficient to model the system 2.
suppert drawings with support and hanger spring rates 3.
the piping design specification 4.
valve weights and centers of gravity 5.
appropriate response spectra 6.
appropriate anchor point movements 7.
any design change notices not yet incorporated into the piping or support drawings (later design change notices should be forwarded as received).
We will analyze this line for the faulted condition (normal loads plus safe shutdown earthquake loads). As we have discussed in our telephone call of February 11, 1980, we request that you provide a description of the steam generator model used in your analysis, since we may choose to include it in our analysis of the piping system.
Provide also a clear description of how the seismic analysis was performed on the "A" Main Steam Line, particularly how the seismic input at the steam generator nozzle was chosen. The modal frequencies of both the steam generator and main steam line should be included. The submitted information should demonstrate that the use of the response spectra at the steam generator base as input to the main steam line is appropriate.
a 110-30 Three copies of the information should be provided.
Two copies should be submitted to the NRC in the usual manner for submitting information to amend your application for an operating license.
The third copy should be sent directly to:
Mr. Merv Bampton Battelle Pacific Northwest Laboratories P. O. Box 999 Richland, Washington 99352
331-1 331.0 RADIOLOGICAL ASSESSMENT BRANCH 331.1 Radiation dose rates in excess of 100 rads per hour can (12.1-5,12.1-9) occur in the vicinity of spent fuel transfer tubes.
It is our position that the SFTT area should have structural barriers to prevent inadvertent access to the high radia-tion levels near the area and sufficient shielding to assure acceptable radiation levels in adjacent occupied areas.
Provide plan and elevation layout drawings of the SFTT areas, including these adjacent areas.
Your response should include procedures for positive access control and radiation monitoring in the areas near the SFTT, as well as audible and visible radiation alarm signals to be actuated if radiation fields increase above ambient levels in the area. Describe how your spent fuel transfer tube operation meets this position.
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