ML19247B673
| ML19247B673 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/18/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Clayton F ALABAMA POWER CO. |
| References | |
| NUDOCS 7908130091 | |
| Download: ML19247B673 (2) | |
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'o UNITED STATES l ',,, (f[,j NUCLEAR REGUL ATORY COMMISSION
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o,, p AT LANT A, G E ORGI A 30303 JUL 181979 In Reply Refer To:
RII:JP0 50-348
,-50-364 Alabama Power Company Attn:
F. L. Clayton, Jr.
Executive Vice President Post Of fice Box 2641 Birmingham, Alabama 35291 Gentlemen:
IE Bulletin 79-14 is revised to limit the scope of work required.
The changes are indicated on the enclosed replacement page for the bulletin.
If you desire additional information regarding this matter, please contact this office.
Sincerely, t
mAh g James P. O'Reilly Director
Enclosure:
Page e of 3 to IE Bulletin No. 79-14, Rev. 1 f. 4 ( L ', C 9 r *-
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JUL 181979 r
3 Alabama Power Company cc w/ encl:
A. R. Barton Executive Vice President Post Office Box 2641 Birmingham, Alabama 35291
- 3. T. Young Vice. President-Production Post Office Box 2641 Birmingham, Alabama 35291 C. Biddinger, Jr.
Manager-Corporate Quality Assurance Post Office Box 2641 Birmingham, Alabama 35291 H. O. Thrash Manager-Nuclear Generation Post Office Box 2641 Birmingham, Alabama 35291 H. G. Hairston, III Plant Manager Drawer 470 Ashford, Alabama 36312 R. E. Hollands, J:
QA Supervisor Post Office Box U Ashford, Alabama 36312
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IE Bulletin No. 79-14 July 18, 1979 3
Revision 1 Page 2 of 3 Action to be taken by Licensees and Permit Holders:
All power reactor facility licensees and construction permit holders are requested to verify, unless verifiet to an equivalent degree within the last 12 months, that the seismic analysis applies to the actual configuration of safety-related piping systems.
The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, " Seismic Design Classification" Revision 1, dated August 1, 1973 or as defined in the applicable FSAR.
The action items that follow apply to all safety related piping 2 1/2-inches in diameter and greater and to seismic Category 1 pipingu regardless of size nbiet was dynamically analyzed by computer.
For older plants, where c 'smic Category I requirements did not exist at the time of licensing, it must be shown that the actual configuration of safety-related systems, utilizing piping 2 1/2 inches in diameter and greater, meets design requirements.
Specifically, each licensee is requested to:
1.
Identify inspection elements to be used in verifying that thc seismic anslysis input information conforms to the actual configuration of safety-related systems. For each safety-related system, submit a list of design documents, including title, identification number, revision, and date, which were sources of input information for the seismit analyses.
Also submit a. description of the seismic analysis input information which is contained in each document.
Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3.
Submit all of this information within 30 days of the date of this bulletin.
2.
For portions of systems which are normally accessible *, inspect one system in each set of redundant systems and all nonredundant systems for con-formance to the seismic analysis input inforcation set forth in design documents.
Include in the inspection:
pipe run geometry; support and restraint design, locations, function and cle.rance (including floor and wall penetration); embedments (excluding those covered in IE Bulletin 79-02); pipe attachments; and valve and valve operator locations and weights (excluding covered in IE Bulletin 79-04).
Within 60 days of the date of this bulletin, submit a description of the results of this inspec-tion.
Where nonconformances are found which affect cperability of any system, the licensee will expedite completion of the inspection described in Item 3.
K ormally accessible refers to those areas of the plant which can be entered N
during reactor operations.
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