ML19253B995
| ML19253B995 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/19/1973 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7911040004 | |
| Download: ML19253B995 (3) | |
Text
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.4 P9TRIBUTION
- 1., FDR Local FDR Docket RP Reading FWR-4 Reading SHHanauer FJBoyd 8
RCDeYoung Docket Nos. 50-289
- N 13g DSkovholt and 50-320 RFraccary DKnuth EDenten FWR Branch Chiefs HFaulkner OGC Metropolitan Edism Compeg ATIN: Mr. John C. Mille, RO (3)
Vice Presiderit EGoulbourne P. O. Box 542 Resuiing, Pennsylvania 19603 Gartle:
'lte enclosed Errata Sheet for " General Infb2sation Requimi for Consideration of the Effects of a Piping System Break Outside Ocntnirmait" amends our letters to you of December 15,1972. 'Ibene letters concemed the potential effects of steamline breaks in the 'Ihree Mile Island Plant, thits 1 and 2.
Please ecrztact us if you desire av div=atm or clarification of this innterial.
SiDeerely, Origical 5;gnea y, Albert Schwencer A. &he, Chief -
Pressur1 rod water Reactora Branch no. 4 Directorate of Licensing Enclosum:
1505 094 Errata Sheet cc: General Public Utilities Service General Public Utilities Service Cuq = stion Corporatical A' FIN: Mr. R. W. Heward ATIN: Mr. T. Crirmina, Manager Project Marager Safety and Licensing 260 Cherry Hill Road 260 Cherry Hill Road Parsippaq, New Jersey 07054 Parsippaq, Ikw Jersey 07054 Gerald Charnoff L. D Shaw, Pittmn. Potts 'Perwbriden; nnd vndann P
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d.
ERRATA SHEET FOR " GENERAL INFORMATION REOUIRED FOR CONSIDERATION OF THE EFFECTS OF A PIPING SYSTEM BREAK OUTSIDE CONTAINMENT" The following lists the changes that have evolved on our initial information request:
1.
Page 2, Item 2--Insert the following in 2. to precede the existing first sentence:
" Design basis break locations should be selected in accordance with the following pipe whip protection criteria; however, where pipes carrying high energy fluid are routed in the vicinity of structures and systems necessary for safe shutdown of the nuclear plant, supplemental protection of those structures and systems shall be provided to cope with the environ-mental effects (including the effects of jet impingement) of a single postulated open crack at the most adverse location (s) with regard to those essential structures and systems, the length of the crack being chosen not to exceed the critical crack size. The critical crack size is taken to be 1/2 the pipe diameter in length and 1/2 the wall thickness in width."
2.
Page a Item 2(a)(2)--Change nomenclature to read "any intermediate locations between terminal ends where the primary plus secondary stress intensities Sn... "
3.
Page 4, Item 2. (b)(2)--Change 0.9 (Sh*S)t 0.8 (S
+S).
A 4.
Page 6, Item 7 --Add " structural" to read "The structural design loads..."
5.
Page 7, Item ll. (a)--Add " required" so as to read, " Loss of recaired redundancy..."
6.
Page 7, Item ll. (a)--Delete "the steam line break" and replace with "that" to read "...the consequences of that accident..."
7.
Page 8, Item 11.(b)-- Replace (b) with the following: (b) " Environmentally induced failures caused by a leak or rupture of the pipe uhich would not of itself result in protective action but does dischle protection functions. In this regard, a loss of redundancy is permitted but a loss of function is not permitted. For such situations plant shutdown is required."
1505 095
8.
Page 8, Item 13--Change wording in the first sentence to read
" Environmental qualification should be demonstrated by test for that electrical equipment required to function in the steam-air environment resulting from a hich energy fluid line break."
... L 1505 096