ML20211Q219

Forwards List of Pipe Supports W/Increased Stress Allowables,Per Response to FSAR Question 210.45.Supports W/ Increases of 33.3% or More Will Have No Impact on Structural Integrity

ML20211Q219
Person / Time
Site:	Vogtle
Issue date:	12/12/1986
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
GN-1223, NUDOCS 8612190221
Download: ML20211Q219 (3)

Text

Georgb Pbwer Company Post Offic3 Box 202 Waynesboro, Georgis 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 VOgtle Project December 12, 1986 Director of Nuclear Reactor Regulation File:

X4BP26 Attention:

Mr. B. J. Youngblood Log:

GN-1223 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 PIPE SUPPORTS WITH INCREASED STRESS ALLOWABLES

Dear Mr. Denton:

In response to FSAR Question 210.45 Georgia Power Company committed to notify the NRC where the stress allowables for pipe supports are increased above the normal allowables by more than 33.3 percent when evaluating faulted load conditions. We have reviewed our correspondence files and have identified the attached list of pipe supports As the attached list shows, the number of supports which exceed the 33.3 percent faulted stress increase is extremely limited. No two of the affected supports are on the same pipe in the same vicinity. This confirms that the increase is used sparingly and will have no impact on the structural integrity of the supported piping systems.

Future cases of supports exceeding the stress allowables by more than 33.3 percent are anticipated, primarily in Unit 2.

The attached list will be amended as additional supports are identified.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely,

.h.

J. A. Bailey Project Licensing Manager JAB /sm Attachment Go {

xc: List attached

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P-Director of Nuclear Reactor Regulation

. File: X4BP26

. December 12, 1986 Log:

GN-1223 Page 2 xc:

R. E. Conway R. A. Thomas J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2)

B. Jones, Esquire G. Bockhold, Jr.

NRC Regional Administrator NRC Resident Inspector D. Feig R..W. McManus L. T. Gucwa Vogtle Project File 0928V

PIPE SUPPORTS FOR WHICH FAULTED STRESS ALTAWABLES HAVE BEEN INfMRAMED BY MORE THAN 33.3%

Pipe Ratio of Sample Support Tag Isometric Size Faulted Load to (by N-Stamp Package)

Number Numbe r (in)

Normal Allowable (3)

Safety Injection V1-1204-045-H028 1K4-1204-045-01 1

150%

V1-1204-224-H009 1K4-1204-078-02 1.5 146%

CVCS V1-1208-486-H607 1K4-1203-486-02 1

164%

V1-1208-487-H608 1K4-1208-486-02 1

180%

Main Steam V1-1301-126-H017 1K4-1301-126-04 3

150%

Auxiliary Feedwater V1-1302-014-H012 1K2-1302-032-01 4

188%

V1-1302-018-H016 1K2-1302-033-01 4

194%

V1-1302-019-H011 1K2-1302-034-01 4

200%

V1-1302-057-H005 1K5-1302-057-01 4

156%

V1-1302-086-H001 1K2-1302-003-01 3

196%

Essential Chilled Water V1-1592-044-H053 1K3-1592-044-03 6

147%

N/A(1) Fire Protection V1-2301-332-H001 1K2-2301-330-02 6

138%

Normal Chilled Water V2-1591-030-H006 2K2-1591-030-01 6

166%

N/A(2) CVCS V2-1208-490-H011 2K4-1203-490-01 6

152%

Gaseous Radwsste Processing

• V2-1902-135-H618 2J3-1902-135-02 2

190%

Notes:

(1) Non-ASME support; not included in any N-stamped system.

(2) Unit 2 support; system N-Stamp scope not yet defined.

(3) Ratios between 133.3% and 200% to be reported to the NRC; maximum permitted ratio is 200%.