ML19263C963
| ML19263C963 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/27/1979 |
| From: | Tollison A CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| B3516.2, NUDOCS 7903200167 | |
| Download: ML19263C963 (2) | |
Text
I IIdqtrs Pult Carolho Power & LWt Company Brunswick Steam Electric Plant F. O. Box 458 Southport, N. C.
28461 February 27, 1979 SERIALt 38,EP/79-214 FILE:
53516.2 g g g.g
$, THOMPSCJ C, E UPt!GM R t, DENDEMI R & ENM Mr. James P. O'Reilly, Director U. S. Welsar Regulatory Comunission g [ $",G E
pgy r,
- t t suintRLAND Engion 11 er 101 Marietta Street, Suite 3100 j n M. ctAnn t
Atlants, Georgia 30303 t
Dear Mr - O'Reilly to BRUNSWICK STEAM ELECTRIC PLANT, UNIT EDS. 1 & 2 C
LICENSE NO. DPR-62 AND DPR-71 DOCKET NO. 50-324 AND 50-325 CONFIRMATION FACSIMILE POR AN DGGtDIATELY REPORTABLE EVENT In accordance with Technical eyecification 4.9.1.8.1, the following event is re-ported:
we were informed by the plant architect-engineer that, On February 27, 1979, during the Annulus Pressurization Study, it was discovered that one feedwater (on each unit) was not installed as assumed in tha original pipe whip restraint pipe whip analysis.
'this restraint is located in the drywell at the 69'-2" elevation on feedwater line 'A' at reactor vessel penetration N-43, 1350 The restraint surrounds the elbow where the line vertical feedwater line inmediately upstream of the 900The pipe whip analysis assumed turns horizontal to enter the reactor vessel.
the restraint was located 36" in elevation below the centerline of the no The actual location is 54" below the nossle/ safe-end centerline.
saf e--end.
In event of a pipe break in the safe-end area, this results in a longer moment Since the arm for pipe whip and possible " plastic hinge" at the restraint.
drywell wall is approximately 22" from the feedwater line, there is a possibility of contact, a conditisrn mot permitted in the analysis.
This condition does not arist on the other three feedwater lines on each un The condition is created on feedwater line 'A' by tNr larger rectangular " win-dow" in the reactor vasesi shield wall needed to accommodate the CED r in addition to the feedwater line.
790320 0/67
i Mr. J. F. D'asilly February 27, 1979 The architect-engineer's pre 14=Nery eatinaate is that no damage would occur to the drywell liner and wall even if the pipe break and whip occurred.
Analysis is in progress to verify this. Measures for permanent solution on both units are under investigation.
This facsimile confirms the telephone conversation between Mr. To111 son and Mr. Riley on February 27, 1979.
This was also reported to Mr. Caudie Julian on-site on February 27, 1979.
Very truly yours, A. C. Tollison, Jr., Manager Brunswick Steam Electric Plant ACT/ arc cct H. R. maak=
..