ML20126D007
| ML20126D007 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte |
| Issue date: | 03/24/1980 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML110820478 | List: |
| References | |
| REF-PT21-80-206-000 NUDOCS 8004150210 | |
| Download: ML20126D007 (3) | |
Text
__.
.y Report on Safety Concern Re:. Reactor Buil'dino Cooler Support Braces' This report evaluates a concern that support braces for the cooling water supply header used for the reactor building coolers at the Bellefonte Units 1 and 2 were fabricated from steel angle whereas the seismic analysis 'by the vendor was.done assuming box shape steel tubing.
It is concluded that this condition constitutes a defec-t reportable under 10 CFR 21.
J e
Description of Concern Each of the Bellefonte plant units has three sets of reactor building coolers that are cooled by raw cooling water.
These coolers are part of the reactor building cooling system and are engineered safeguards features since their function is to provide emergency reactor building dtmosphere cooling in the event of a design loss-of-coolant accident (LOCA).
Each_of the three coolers consists of three sets of cooler banks and each bank of coolers is provided with cooling water by means of cooling water heade rs.
Support braces, as-fabricated, for te cooling water headers for all the coolers in both Bellefonte units, are of.cngle s teel.
- However, American Air Filter (AAF), the cooler manufacturer, psrformed the seismic analysis of the coolers and supports based on the support braces being fabricated from box cross-section tubing, and has determined that the as-fabricated brace is non-conservative with respect to the brace design used in the seismic analysis.
i l
The safety concern is that in the event of a seismic occurrence, the braces ~
could possibly be overstressed, causing the cooling water headers to become detached from the coolers, thereby losing cooling water supply to the coolers; the coolers would therefore be unable, to perform their cooling function if a-1.0CA accompanied the seismi'c event, and the reactor building temperature and' pressure'would exceed the values used in the plant' safety analysis.
l The discrepancy between the as-fabricated braces and the brace design used in the seismic analysis was discovered by AAF when they were perfonning a general review of their seismic analysis methods used for all customers, q
including the Bellefonte units.
This discovery was made ' subsequent to the I
U 10 j
- .-= -
_2-
\\
shipment of the coolers to Bellefonte and is not considered as part of the QA process for the design of the Bellefonte units; it is therefore considered to be an inadvertent discovery.
The Bellefonte units are the only B&W plants for which B&W Company contracted to s' pply the AAF reactor building coolers.
u
/
Analysis The reactor buildings for the Bellefonte Units are provided with two types of systems that are designed to function in the event of a LOCA to adequately ' cool the reactor buiiding atmosphere.
One system is the three building coolers described above.
The other system is t'he reactor building spray system, which consists of two separate trains.
Adequate building cooling following a LOCA can be achieved by any one of the following combinations of these two systems:
(a) -Either the full capacity (both trains) of the reac, tor building spray system, or (b) Two of the three reactor building coolers, or
( c,' One train of the spray system and one of the reactor building coolers.
4 If, in the event of a seismic event concurrent with a LOCA, the three reactor building coolers fail to function due to the deficient support braces, then only'the spray system would be available to perform the required cooling.
Thus, options (b) and (c) above would be unavailable and only option (a) would be viable.
However, a single failure must also be assumed,, and in this case, that could be the failure of one train of the spray system, leaving only one train available.
One train is insufficient and the accident analysis in the FSAR is therefore invali~ dated.
Reportability A seismic stress analysis on the as-fabricated support braces has no.t been performed, tand one is not intended to be performed, to determine if these braces would be overstressed in a seismic event and,would, in turn, result
' n failure of the coolers.
i s-
However, the manufacturer, AAF compared the angle brace design with the box tube brace design used in the seismic analysis and concluded that the angle brace was non-conservative with respect to the box tube brace and, further, estimated that the angle brace may not provide the required ' support strength in a seismic event.
It is therefore ' concluded that this condition is a c'efect reportable under 10CFR21.
8.
Corrective Action The defective support braces (18 in number) have been returned to the vendor for mcdification to conform to the design used in the seismic analysis.
There appears to have been a lack of design control 'at AAF in that the detail fabrication drawings showed the braces as angle steel, and that was the way it was actually fabricated, whereas the AAF seismic analysis was performed assuming braces made of; square tubing.
B&W h'as no present orders with AAF to procure additional coofers and no orders are presently con-templated; however, prior 20 the-placement of any future orders, B&W will perform an in-depth audit of the AAF design control system to ensure that this type of problem does not recur.
O 2
~
,. Y.;.. _ - i...-
.. _.. -.--....).--.y.~.
.. : q _. -_:.. n--(. r.:
..:y _ _ _ _ e.
ATTACWD IS A PART 21 REPORT FPG lE l%1L UNIT - ROOM 359Eh?
PART 21 IDSiTIFICATION 10, 8o - 4o6-o o o COMPANY llAE B 4 03 DATE CF LETTER
%Y/Po DDCET 10.
So - V 3 r, n -43 P 2h/,/Fa ORIGllML RER)RT ZSUPPLB'BITARY E IATE DISTRIBHED DISTRIBRIO4:
REACTOR (R)(
REL CYCE &
SAFEGUARDS (St l%TERIALS(M)
IPMDR, DIRECTOR 10/FFMSI -
AD/SG-lE RRR/DRi DIRECTOR NES/ Fos AD/ROI AD/FOI ( 2 )
EGlWS REGIONS AD/RCI IE FIES I!PMOR, DIRECTOR REGIO"S PJR lies /SG SS-881 IE FILES (2)
LoDR PDR CB:TPfLFILES C5fiPAL FlES-SS-396 LPDR CBfi?AL FIES (CHPJO CBiiFAL FILES (CHRO:0 TEPA alB h
- IE FILES (2)
LPDR CBffRAL FILES 016 TEPA LT3/1PA liG 5715 CBffRAL FILES (CHR0:0 g.p; gg 73 CBffPAL FILES
.SS-396 ACT10th L0EBAFA MiB 5715 PRELIMIIMRY EVUAL4 TION OF THE ATTACHED REPORT INDICATES LEAD RES FOLLO+LP AS SHMi BELOW:
JEO LO1E WGS LJ DIEE FRGI a
EEV. 2/26/80
.,