ML18085A855
| ML18085A855 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/21/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18085A854 | List: |
| References | |
| NUDOCS 8102230163 | |
| Download: ML18085A855 (1) | |
Text
... *.
1' SAFETY.EVALUATION REPORT"
. SALEM UNIT 1
. FRACTURE TOUGHNESS OF STEAM.. GENERATOR...
- . AND. REACTOR COOLANT. PUMP **SUPPORTS
-~: " '.
l~O Introdtiction In a Jetter dateci December -30, 1977, Public *service, El:ecti'iC: and Gas.
Company' responded to the *NRC Is request for information concerning ttie '
fracture. toughness design' of the steam generator and reactor coolant '
pump S(.!pp*orts at Salem Unit 1.,. This information was initially
- reviewed by Sandia Laboratories as part of generic technical activity*
,A-12.
Sandia's evaluation con~luded that the steam generator and.
reactor coolant pump supports at. Salem Unit 1 were considered to. be as good.as *careful, reasonable engineering practice. can produce.
This evaluation is contained in NUREG:..0577.. The.. informationcontained in the licensee's response was subsequently ~ransmitted to Franklin
. Research Center for an independent evaluation.. This eva,luation was based on the.criteria presented in the draf,t version,of.NUREG-0577.
- ... 2.0 Evaluatian.
- The enclosed Technical Evaluatio~ Reportwasprepar~dby the. Franklin**
Research Cen_ter as part.of NRC Contract* No.... NRC.. 03-79-" 118..,*.. **.
. The scope of Frankli~'s review was limited to those supports origin~lly reviewed by Sandia.which included the steam generator and reactor.
coolant pump supports"excluding the.upper steam generator snubber assemblies.. Subs*equent to the initial rev.iew by Sandia laboratories,*
the scope of Generic Technical Activity A-12 has been expanded to.*
include.other supports.. For thos.e supports 1dent1fi.ed by the final version of NUREG*0577 that are not included iil this review, the licensee should follow the implementation plan specified in NUREG-0577"."
. 3~0. Conclusion
- Base.d onour review of:Franklin's Technical Evaluation Report~ we agree,
with_ their conclusion that the steam generator and 'reactor coolant pump '
supports at Salem Unit 1 possess adequate fracture toughness to merit
- _:
- a group III rating per NUREG-0577.
Therefore, we consider the fracture*
toughness of _the steam generator and reactor coola.nt pump supports acce~table.