05000325/LER-1980-046-01, /01T-0:on 800711,util Informed by Contractor That Evaluation of Scram Discharge Vol Drain Lines Determined That Facilities Require Redesign of Several Supports & Loosening of U-bolts to Allow for Thermal Expansion

/01T-0:on 800711,util Informed by Contractor That Evaluation of Scram Discharge Vol Drain Lines Determined That Facilities Require Redesign of Several Supports & Loosening of U-bolts to Allow for Thermal Expansion

ML19327A251
Person / Time
Site:	Brunswick
Issue date:	07/24/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19327A248	List: 05000325/LER-1980-046-01, /01T-0:on 800711,util Informed by Contractor That Evaluation of Scram Discharge Vol Drain Lines Determined That Facilities Require Redesign of Several Supports & Loosening of U-bolts to Allow for Thermal Expansion
References
IEB-80-14, LER-80-046-01T-01, LER-80-46-1T-1, NUDOCS 8008050047
Download: ML19327A251 (1)

LER-1980-046, /01T-0:on 800711,util Informed by Contractor That Evaluation of Scram Discharge Vol Drain Lines Determined That Facilities Require Redesign of Several Supports & Loosening of U-bolts to Allow for Thermal Expansion

Event date:
Report date:
3251980046R01 - NRC Website

text

a NR8 ORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT o

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8 60 63 OOCK ET NUMBER Nd 69 Ev f NT OATE 74 75 REPORT OATE 30 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 12 l l Carolina Power & Light Company was informed by United Engineers and Constructors l

1 o t 31 1 (UE&C) that an evaluation performed on the scram discharge volume drain lines at l

1o la l l the Brunswick Steam Electric Plant Unit Nos. I and 2, as a result of LER 1-79-74 l

l o I s i I and identified in IE Bulletin 80-14, determined that both units required a redesign i

i o is I l of several supports and a loosening of existing U-bolts to allow for thermal l

[ o l 7 l [ expansion.

l t ois j l Technical Specifications 6.9.1.81 1

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33 36 34 40 41 42 43 44 47 CAUSE DESCRIPTION AND CC ARECTIVE ACTIONS 27 li 6 0 t l All drain line supports were corrected to meet the reanalvsis criteria.

l lilil l Reactor Controls, Inc., the subcontractor for the erection of CRD oipine, did~not I

iii7i l perform an analysis on this piping as they were under the belief that it was not I

i i ; 31 l safety-related. Thev have verified that all CRD piping has now been evaluated and l

iii4i [that it is acceptable as built.

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ACTIVITY CO TENT RELEASED OP RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE l Z l @ l Zl@l NAl l

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