ML19207B772
| ML19207B772 | |
| Person / Time | |
|---|---|
| Issue date: | 08/22/1979 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 7909050252 | |
| Download: ML19207B772 (2) | |
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- pa ascoq'o UNITED STATES l'
,gg'n NUCLEAR REGULATORY COMMISSION 3
REGION 111 5-
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799 ROOSEVELT ROAD
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GLEN ELLYN, ILLINOls 60137 p
gN State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Bulletin No. 79-02, Rev. 1, Supplement No. 1, titled " Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts" was sent to the following licensees on August 20, 1979, for action and information:
ACTION American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Commonwealth Edison Company Dresden 1, 2, 3 (50-10, 50-237, 50-249)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Ccmpany Big Pock Point (50-155)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern States Power Company Monticello (50-263)
Prairie Island 1,2 (50-282, 50-306)
Toledo Edison Company Davis-Besse 1 (50-346)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation O ^g~
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Kewaunee (50-305) 790905 0 tsa
AUG 2 31979 State of Illinois,
INFORMATION Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441) t, Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
La Salle 1, 2 (50-373, 50-374)
Consumers Power Company Midland 1, 2 (50-329, 50-330)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Northern Indiana Public Service Company Bailly (50-367)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Sincerely, cd Y Helen Pappas, Chief Administrative Branch
Enclosures:
IE Bulletin No. 79-02, Rev. 1, (Supplen.ent No. 1) cc w/encls:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction P;at NRC 20b Local PDR NS_IC TIC Di.10Q
SSINS:
6820 Accessien No:
7908150164 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 20, 1979 IE Bulletin No. 79-02 Revision No. 1 (Supplement No. 1)
PIPE SUPPORT BASE PLATE DESIGNS USING CONCRETE EXPANSION ANCHOR BOLTS Description of Circumstances:
The supplement to IE Bulletin No. 79-02 is intended to establish criteria for the evaluation of interim acceptability of plant operation with less than the design factors of safety for piping supports due to as-built problems, under design, base plate flexibility, or anchor bolt deficiencies.
In the reviews for system operability of the Duane Arnold and Crystal River facilities, criteria have been developed by the NRC staff that defines pipe support operability. The criteria has been applied in lieu of other analysis or evalua-tion. Specifically, the licensees identified problems with pf.ge supports in which the original design factors of safety were not met but some lesser margin was available. The design margins of four or five are intended to be final design and installation objectives but systc:as may be classed as operable on an interim basis with some lesser margin providing a program of restoration to at least the Bulletin factors of safety has been developed.
Facilities which fall oncside the operability criteria are considered to probably require a Technical Specifica-tion exception and will require review en a case by case basis.
Action to be Taken by Licensees:
For the following two cases, plant operation may continue or mey begin:
a.
For the support as a unit, the factor of safety compored to ulti-mate strengths is less than the utiginal design but equal to or g'reater than two.
b.
For the anchor bolts the factor of safety is equal to or greater tnan tws and for the support steel the original design factor of safety com-pared to ulitmate strengths is met.
_The above criteria may be applied provided that the affected systems are up-graded to design margins of safety expeditiously for normally hecessibile supports and by the next refueling for nonaccessible supports.
Accessibility is as de-fined in Bulletin No. 79-14 where "normally accessible" refers to those areas of the plant which can be entered during reactor operation.
IE Bulletin No. 79-02, Revision No. 1 Page 2 of 2 Supplement No. 1 August 20, 1979 1.
Any support not satistying the criteria should be classed as inoperable and the Technical Specification action statement met unless it can be shown that the system can function in a design basis seismic event without the support.
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,2.
Repairs to supports should result in return to the design factor of safety.
3.
Operations may be continued while repairs to upgrade the system from a factor of safety equal to or greater than two with respect to design loads are performed.
Consideration must be given to the effect of the repair process on support function and system operability.
In other words the time the support is not functional should be limited to T.S. action statement times or the support mus be determined not to cause the system to be unable to perform its function in a seismic event. The licensee should also exercise care not to take several supports on a given system out of service at the same time or cause both trains of one safeguards system to be made inoper-able at the same time.
Control over workmen on safety related systems during plant operation requires a high degree of control by the licensee.
4.
There are no special reporting requirements for this supplement to the Bulletin; however, the reporting requirements as set forth in the regula-tions and licenses must be met.
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