ML20207G193
| ML20207G193 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/24/1986 |
| From: | Foster D GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| GN-962, NUDOCS 8607220718 | |
| Download: ML20207G193 (6) | |
Text
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Georgia Power Company b
Post Office Box 282 Waynesboro. Georgia 30830 Telephone 404 554 9961, Ext. 3360 404 724-8114. Ext. 3360 m
Georgia Power D. O. Foster
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~~
p, ye in n ecclic system June 24, 1986 United States Nuclear Regulatory Commission File: X7BD102 Suite 2900 Log:
GN-962 101 Marietta Street, N.W.
Atlanta, GA 30323
Reference:
Vogtle Electric Generating Plant - Unit 1, 50-424, Readiness Review Module 11, Interim Review Questions Attention:
Mr. J. Nelson Grace We have reviewed the questions regarding Module 11, Pipe Stress and Supports, in the NRC letter dated May 16, 1986,
Subject:
Vogtle Readiness Review - Interim Review Questions - Module Number 11. " Pipe Supports." Our responses are contained in Attachment 2.
The item numbers in Attachment 2 correspond to the item numbers in the enclosure to your May 16, 1986 letter.
i We are hopeful that our responses to your questions satisfies your consnents concerning Module 11 commitments.
This response contains no proprietary information and may be placed in the NRC Public Document Room.
l Very truly-yo rs,
,1 1/
/
D. O. Foster W
RCS/DOF/bjd cc: See Attachments Oll4k/175-6 5
[
cc:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Victor J. Stello, Jr., Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, D.C.
20555 J. W. Thompson U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 28014 Ms. Melanie A. Miller Division of Licensing Licensing Branch #4 Washington, D.C.
20555 Senior Resident Inspector U. S. Nuclear Regulatory Commission Vogtle Electric Generating Plant B. W. Churchill Shaw, Pittman, Potts & Trowbridge 1800 M Street, Northwest l
Washington, D.C.
20036 J. E. Joiner Troutman, Sanders, l.ockerman & Ashriore Candler Building i
127 Peachtree Street, N.W.
Atlanta, GA 30303 D. C. Teper Georgians Against Nuclear Energy 1253 Lenox Circle Atlanta, GA 30306 l
l l
l
C Page Two cc: William M. Hill NRC-IE (EWS-305)
Building East West / South Towers 4340 East-West Hwy.
Bethesda, MD.
20555 W. H. Rankin Suite 2900 101 Marietta Street, N.W.
Atlanta, GA 30323 R. E. Conway J. T. Beckham, Jr.
R. A. Thomas D. E. Dutton D. S. Read W. T. Nickerson D. T. King K. Wiedner P. D. Rice R. H. Pinson C. W. Whitney J. A. Bailey F. B. Marsh J. L. Vota C. W. Hayes S. H. Freid W. C. Ramsey R. T. Oedamer J. S. Hempstead W. M. Wright R. W. McManus M. H. Googe H. Walker J. Starnes (INPO)
- 0. Batum Document Control Project File RR Reading File (Letter Only)
Oll4k/175-6
O a
Page 1 of 3 4
Commitments identified as omitted by NRR:
The item numbers correspond to item numbers of USNRC dated May 16, 1986.
1.
FSAR section 3.6.2.1.2 is addressed in Readiness Review Module 4, Mechanical Equipment and Piping, in commitments 951, 952,and 954 through 961.
Module 4 was submitted to the NRC on June 14, 1985.
I 2.
The question references section 3.6.2.3.2. of the FSAR for dynamic analysis methods for other than RCL piping.
However, section 3.6.2.3.2 specifically addresses " Dynamic Analysis Methods for the RCL".
Section 3.6.2.3.1
. other than RCL".
Commitment No. 4992 of addresses, Module 11 addressed the dynamic analysis of piping other than RCL.
3.
Analysis and design of pipe whip restraints is addressed in Readiness Review Module 11 and in Module 8, Structural Steel, which was submitted to the NRC on November 12, 1985.
FSAR section 3.6.2.3.4 is addressed in commitments 965 of Module 8 and in commitments 965 and 4993 in Module 11.
The remaining portions of section 3.6.2.3.4 are l
considered descriptive and not a commitment for the Readiness Review definition of a commitment.
1 I
4.
Seismic Analysis methods for piping systems is addressed in commitment 1615 of Module 11.
Seismic analysis of Category I subsystems and components addressed is in l
commitment 1011 of Readiness Review Module 8 and l
Appendix J.
Equipment Qualification, which was submitted to l
the NRC on March 26, 1986.
5.
.The subject of FSAR section 3.9.B.2 is preoperational testing which is addressed in commitments 3323 through 3228 and 3230 through 3332 of Module 3A, Preoperational Testing, which was submitted to the NRC on March 29, 1985.
l 6.
As stated in section 1.0 of Module 11, the scope of Module 11 included safety related piping and supports and l
non-safety related seismic Category I piping.
Therefore, I
the non-safety related valve discharge piping is not included in Module 11.
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Page 2 of 3 7.
FSAR Section 3.9.B.3.2 was not considered a commitment for Readiness Review.
The section is considered descriptive; it does not invoke a code, standard, or other regulatory requirement and does not describe an unique method of designing closed system discharges.
8.
FSAR Section 3.9.B.3.4.2.lc was not included in Module 11 as a commitment.because it is descriptive of the methods used to ensure that design complies with the commitments to ASME Section III. Subsections NA and NF.
9.
FSAR Section 3.9.B.3.4.2.lF is descriptive of the generic temperatures used for environmental qualification of equipment inside containment.
Environmental qualification of mechanical equipment, including snubbers, is addressed in Appendix J of Module 21, General Appendices.
FSAR Section 3.9.B.3.4.2.lG is descriptive of a feature of snubbers which allows adjustment of the snubber overall i
length without affecting snubber operating position.
This feature was considered a design detail, not a Readiness Review commitment.
10.
Commitments related to the ESF materia'ls were addressed in Module 4, Mechanical Equipment and Piping in commitments 322, 324 through 331, 256, 259 and 2170.
11.
As stated in section 3.4 of Module 11, general commitments related to the quality program for the design and construction of pipe supports were recognized and verified during the verification described in section 6 of Module i
11.
The specific commitments were not included in the commitment matrix because they were general and implementation is broad and applicable to many modules.
12.
The commitment in response to NRC FSAR question Q210.30 was to provide a later submittal to the NRC.
Readiness Review did not include this type of commitment in their modules because they are schedular in nature and do not represent a design or construction basis commitment.
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e Page 3 of 3 13.
The response to NRC FSAR question Q210.35 was not included as a commitment in Module 11 because it is a discussion of design features of the main steam and feedwater systems and did not represent a Readiness Review commitment.
14.
The response to NRC FSAR question Q210.36 was not included as a ccmmitment in Module 11 because it was descriptive of the design methods and details of the main steam and feedwater piping and did not represent a Readiness Review Commitment.
15.
The response to NRC FSAR question Q210.39 was not included as a commitment in Module 11 because it was descriptive of the design process followed to comply with commitments to NRC Regulatory Guide 1.29 and ASME III requirements for pipe anchors.
Compliance-to RG 1.29 and ASME III are included as specific commitments in Module 11.
16.
The vibration monitoring program is addressed in Readiness Review Module 3A, Preoperational Testing, as commitment 4378.
17.
Table 210.45-1 included in response to NRC FSAR question Q210.45-1 is the same as table 3.9.B.3-1 of the FSAR which is included as commitment 1660 in Module 11.
f 18.
The response to NRC FSAR question Q210.45C provided tables 210.45-1 and 210.45-2 which lists design details of the loads, load combinations, and allowable stresses used in i
the design of piping and components supports.
These tables are included in FSAR as 3.9.B.3-1, 3.9.B.3-6 and 3.9.B.3-7.
Module 11 addressed these tables in commitments 1651, 1655 and 1660.
19.
Module 11 includes consideration of compressive buckling as commitment 4258.
The Q210-45-3 description in the commitment section of the matrix indicates Table 210-45-3 of question Q210.45, 20.
Response to this item is identical to item 3.
i Oll3k/167-6 3
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