ML20059J572

Discusses NRC Position Requiring Plant to Provide Anchorage Evaluation Using A-46 Criteria Applied to Safety Equipment. Plant Will Provide Info Under Protest

ML20059J572
Person / Time
Site:	Hatch
Issue date:	01/13/1994
From:	Green T BWR OWNERS GROUP
To:	Trottier E Office of Nuclear Reactor Regulation
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9402010076
Download: ML20059J572 (1)

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j BWR OWNER'S GROUP PROGRAMS j NESSAGE TRAN5NITTAL COVER PAGE RECEIVING TELECOPY NUMBER j (408) 925-2476 l i

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! DATE: January 13, 1994 4

} TO:ED TROTTIER (Ext.1427)

UTILITY: NUCLEAR REGULATORY C0ftilSSION i TELECOPYNUN8ER:(301)504-2102 i

! FROM: TOM GREEN j TELEPHONE: (408) 925-1308 j NUMBER OF PAGES FOLLOWING COVER PAGE: 0 i.

1 The NRC visit (Jabbour and Arnold Lee) to the Hatch site went extremely well. l

! GPC did agree to provide a summary of the margin assessment (in-situ versus

] seismic experience data base) in the form of a supplemental submittal.

7 i We now have a new problem that has the potential to significantly affect the i entire BWR06 program to provide an alternate non-seismic treatment pathway for ,

l MSIV leakage. You will recall the earlier discussions with Terrence Chan regarding anchors and hangers, where the BWR06 agreed "For lines' designed by rule or approximate methods such as the drain path and interfacing piping, demonstrate adequate design margins for typical'or bounding supw rt designs' .

(see page 6-14 of NEDC 31858P Rev.2). Note that we agreed to tTe supplemental l

bounding calculations for supports even though seismic experience data has '

! demonstrated that structu,ral failure of anchored equipment-leading to collapse -

2 is generally not crDble with few exceptions which are readily identifiable by i pla'ntwik=down." ~

i John Ma (Civil Engineering and Geosciences) has recently told Soorgia power that i i the NRC will not accept experience data for anchorage issues. He os requiring- l i

! Hatch to provide anchorage evaluations using the $QUE Generic Implementation

Procedure (gip) which is an A-46 criteria applied to safety related equipment, i or use FSAR a11cuable methods for safety related components. It so happens that i

Hatch can meet the SQUG GIP criteria with minimal effort. Note, however, the j anchorage for the condenser has only a small margin. Hatch will likely provide  :

this information under protest in order to facilitate the associated license f

! change request in early March.- >

a l This NRC position will cause major problems for some of the BWROG participants and we believe it is inappropriate to requie application of A-46 criteria to ,

this non-safety alternate treatment pathway for NSIV leakage.

! l

, I as requesting your assistance in resolving this new issue. Since both the MES ,

l and the Civil Engineering reviewers work for Wayne Hodges (Acting I i Manager-Engineering), this problem may be readily reso vable. If we need to  !

) meet on this subject please let me know. Hopefully we can get this resolved in i the next two weeks so that the Hatch review is not adversely affected. j i I 1

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