ML19247A807
| ML19247A807 | |
| Person / Time | |
|---|---|
| Issue date: | 07/20/1979 |
| From: | Pappas I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 7908020366 | |
| Download: ML19247A807 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION o,
UNITED STATES
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cLEN ELLYN, ILL 1Nois 60137 JUL 2 01379 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jef ferson Street Springfield, IL 62761 Gentl2=en:
The attached IE Bulletin No. 79-14, page 2, Revision 1, was sent to the follcwing licensees on July 19, 1979.
American Electric Power Service Corporation Indiana and Michigan Pcwer Cetpany D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas & Electric Company Zi=mer (50-358)
Cleveland Electric Illu=inating Company Perry 1, 2 (50-440, 50-441)
Co=cenwealth Edison Company Braiducod 1, 2 (50-456, 50-457)
Byren 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consu=ers Power Company 31g Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LAC 3WR (50-409)
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Detroit Edison Company
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Fer=1 2 (50-341) s
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State of Illinois.
JUL 2 01979 Illinois Pcwer Company Clinton 1, 2 (50-461, 5r-462)
Iowa Electric Light 5 Power Conpany Duane Arnold (50-331)
Northern Indiana Public f ervice Co=pany Bailly (50-367)
Northern States Pcwer Conpany Monticello (50-263)
Prairie Island 1, 2 (5'-282, 50-306)
Tyrone Energy Paz. 1 (50-484)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Cc=pany Davis-3 esse 1 (50-346)
Union Electric Cc: pan--
Callaway 1, 2 (50-452 50-486)
Wisconsin Electric Power Oc=pany Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
The Chio Edison Company Pre-CPP Since ely, 8
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'delen Pappas, Chief Administrative Branch Enclesure:
II Eulletin No. 79-14, Page 2, Revision 1 cc w/ encl:
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Central Files yUm Reproduction Unit NRC 20b Local PDR NSIC TIC D. W. Kane, Sargent I
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IE Bulletin No. 79-14 July 18,1979 Revision 1 Page 2 of 3 Action to be taken by 1.icensees and Pemit Holders:
All pcwer reactor facility licensees and construction pemit holders are requested to verify, unless verified to an equivalent degree within the last 12 months, that the seismic analysis applies to the actuaT configura-tion of safety-related piping systems. The safety related piping includes Seismic Category I systems as defined by Regulatory Guide 1.29, *5eismic Design Classification" Revision 1, dated August 1,1973 or as defined in the applicable FSAR. lhe action items that follow apoly to all safety related pioinq 21/2-inches in diameter and greater and to seismic Category I piping, regardless or sizc wnicr. was dynamically analyzed by cce. outer. For older plaats, where Seismic Category I requirements did not exist at the tirne of licensing, it must be '.hown that the actual configuration of f#Hd safety-related systems, utilizing pioing 21/2 inches in diameter and greater, meets design requirsrnents.
Specifically, each licensee is requested to:
1.
Identify inspuction elements to be used in verifying that the seismic analysis inp..: information conforms to the actual configuration of safety-related systems. For each safety-related system, submit a list of design documents, including title, identification nurber, revision, and date, which were sources of input infomation for the seismic analyses. Also submit a dascription of the seismic analysis input infonution which is contained in each document.
Identify systems or portions of systems which are planned tu be inspected during each sequential inspection identified in item <, 2 and 3. Submit all of this infomation 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-femance to the seismic analysis input infonration set forth in design documents.
Include in the inspection: pipe run geometry; support and restraint design, locations, function and clearance (including fleor and wall penetration); erbedments (excluding those covered in IE Bulletin 79-02); sipe attachements; and valve and valve operator locations and weights (excluding those covered in IE Bulletin 79-04}.
Within 60 days of the date of this bulletin, submit a description of the results of this inspection. Where nonconformances _are found which affect operability of any systom, the licensee will expedite ccepletion of the inspection described in Item 3.
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- Mormally accessible refers to those areas of the plant which can be entered during reactor operation.
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