ML19273D308
| ML19273D308 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/05/1980 |
| From: | Wermiel J Office of Nuclear Reactor Regulation |
| To: | Silver H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8004020731 | |
| Download: ML19273D308 (1) | |
Text
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MAR 5(980~
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DISTRIBUTION:
cEJiTRAL FILE NRR READItiG f ( ? ?
Ih, $ U ? Mi}TJ MEMORAi100M FOR: Harley Silver, Project Manager, THI-l Restart THRU:
G. R. Mazetts, Section Leader, Reactors 9;stens Branch, CSS FROM:
Jared Wermiel, Auxiliary R9 stems Branch, DSS
SUBJECT:
1NI-l RESTARZ REVIEW, APPLICATI0;l 0F SRP SECTION 10.4.9,
" AUXILIARY FEEDWATER SYSTEM" REQUIREMENT FOR PIPE RUPTURE ny 3,,,5.
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As part of our review for restart of TMI-1, we are ev'aluating the present THI-1 emergency feedwater (EFW) system design against:the current require-ments of SRP.Section 10.4.9, Auxiliary Feedwater System. This review resulted in an SER open item concerning postulated pipe tuptures in the EFW pump dis-charge lines (Question 12, Supplemerst 1, Part 2 of the Restart Report).
The enclosure is our evaluation of the licensee's response to this item.
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find the existing EFW system acceptable.
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Jared Hermiel n Auxiliary Systems Branch
. Division of Systems' Salfety
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Enclosure TMI-l SER SUPPLEffENT Status Report, Pace Cl-10, Additional Items, No 8;
In Amendment 12, Met-Ed provided additional infomation to our concern with a pipe rupture i n the ERf pump discharge line.
The TMI emergency feedwater system does not meet all our present criteria, specifically, the system is not designed as a high energy system.
The licensee points out that their EFW system is not used for startup and shutdown, but functions only under emergenc y and periodic testing conditions, thus reducing the probability of a pi pe rupture.
The licensee further indicates that the normal system ooerati ng stresses are substantially less than the minimum yield strength of the system
- oiping, and therefore, a double-ended high energy pipe break is extremel y improbable.
In addition, Met-Ed has agreed to perform a volumetric nondestructive exa-mination (NDE) prior to restart of 10 welds in the system pipi ng with the highest combined stresses to verify that no undesirable fla ws exist. We have also noted that B&W plants with the once-through steam generator have not experienced any water hammer phenomena in the ER4 system which could impose additional stresses.
Based on the above design features, we agree with the li censee that the probability of an EFW system pipe rupture is sufficiently remot e to accept the system design without modification in this area
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