ML20207D265
| ML20207D265 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/11/1988 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | Hairston W GEORGIA POWER CO. |
| References | |
| TAC-66675, NUDOCS 8808150305 | |
| Download: ML20207D265 (6) | |
Text
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August 11, 1988
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.Docke't No. :
50-425
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Mr.
W. G. Hairston, III Sen!or Vice President -
Nuclear Operations Georgia Power Company
.P. O. Box 4545 Atlanta, Georgia 3030*i i
Dear Mr. Hcirston:
L
SUBJECT:
'/0GTLE UNIT.2 REQUEST FOR ADDITIONAL INFORMATION PRESERVICE INSPECTION PROGRAM (TAC 66675)
The NRC staff with assistance from its contractor EG8G Idaho, Inc., is reviewing the Preservice Inspection Program for Vogtle Unit 2.
We find that we need additional information (see enclosure) in order to complete our evaluation. We request a response within 45 days of receipt of this letter. Contact me if you have any questions.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P. L.96-511.
Sincerely, Jon B. Hopkins, Project Mcnager Project Directorate II-3 Division of Reactor Projects - I/II
Enclosure:
As stated CC:
See next page DISTRIBUTION Docket #1HI Lo'al PDR" "
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4 Mr'. W. G. Hairston, III Georgia Power Company Vogtle Electric Generating Plant cc:
Mr. L. T. Gucwa Resident Inspector Manager of Safety and Licensing Nuclear Regulatory Comission Georgia Power Company P.O. Box 572 P.O. Box 4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Deppish Kirkland, III, Coursel Mr. Ruble A. Thomas Office of the Consumers' Ut'11ty Executive Consultant Council i
Southern Company Services, Inc.
Suite 225 P.O. Box 2625 32 Peachtree Street, N.E.
Birmingham, Alabama 35202 Atlanta, Georgia 30302 Mr. Paul D. Rice James E. Joiner Vice President & Project Director Troutman, Sanders, Lockerman, Georgia Power Company
& Ashmore Post Office Box 282 1400 Candler Building Waynesboro, Georgia 30830 127 Peachtree Street, N.E.
Atlanta, Georgia 30303 Mr. J. A. Bailey l
Project Licensing Manager Danny Feig l
Southern Company Services, Inc.
1130 Alta Avenue l
P.O. Box 2625 Atlanta, Georgia 30307 Birmingham, Alabama 35202 Carol Stangler Ernest L. Bl:ke, Jr.
Georgians Against Nuclear Energy Bruce W. Churchill, Esq.
425 Euclid Terrace Shaw, Pittman, Potts and Trowbridge Atlanta, Georgia 30307 l
2200 N Street, N. W.
l Wasnington, D. C.
20037 Mr. R. D. Mcdonald Executive Vice President -
Mr. G. Bockhold, Jr.
Nuclear Operations l
General Manager Nuclear Operations Georgia Power Company Georgin Power Compar.j P.O. Box 4545 P.O. Box 1600 Atlanta, Georgia 30302
{
Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 3032?
c ENCLOSURE GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 DOCKET NUME~R 50-425 MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING AND SYSTEMS TECHNOLOGY Reauest for Additional Information - Preservice Insoection Procram Plan 1.
Scoce/ Status of Review General Design Criteria 32, 36, 30, 42, and 45, in Appendix A of 10 CFR Part 50 require, in part, that Code Class 1, 2, and 3 components be designed to permit periodic examination and testing of important areas and features to assess their structural and leak-tight integrity.
The design of these components must incorporate provisions for access for inservice examinations, as required by Subarticle IWA-1500 of Section XI of the ASME Code.
10 CFR 50.55a(g) defines the detailed require;ents for the preservice and inservice programs for light water-cooled nuclear power facility cc nponents. Based upon the construction permit date of June 28,197a, comoonents (including supports) which are classified as ASME Code Class 1 and 2 snall meet the preservice examination requirements set forth in editions of Section XI of the ASME Code and Addenda in effect 6 months prior to the date of i
issuance of the construction permit. The components (including I
supports) may meet the requirements set forth in subsequent editions of l
this Code and Addenda which are incorporated by reference in l
paragraph (b) of 10 CFR 50.55a, subject to the limitations and modifications listed therein. The Preservice Inspection (PSI) Program l
Plan has been prepared to meet the requirements of the 1983 Edition, Summer 1983 Addenda (83S83) of the ASME Code Section XI except that tha reactor pressure vessel automated examinations are to be performed to the requirements of the 1980 Edition through the Winter 1981 Addenda i
(80W81) and the extent of examination for Code Class 2 pipina welds in l
Residual Heat Removal (RHR) Systems, Emergency Core Cooling (ECC)
Systems, and Containment Heat Removal (CHR) Systens has been determined by he 1974 Edition through Summer 1975 Addenda (74S75).
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As required by 10 CFR 50.55a(a)(3), if the applicant determines tnat c9rtain Code examination < equirements are impractical and relief is requested, the applicant shall submit information to the Nuclear Regulatory Commission (NRC) to support that determination.
The staff has reviewed the available information in the Vogtle Electric Generating Plant, Unit 2, PSI Program, Revision 2, submitted November 4, 1987.
2.
Additional Information Reauired Based on the above review, the staff has concluded that the following informatien and/or clarification is required in order to complete the review of the PSI Program Plan:
A.
The "Line Designation List" (Section 7.0) lists the lines within the scope of the ASME Code Section XI. The Tables identify the lines by system, line number, size, Code class, temperature, pressure, examination method (s) required, and basis for exemption (if applicable). Will all of the welds on the lines identified for ex aation, both Class 1 and Class 2, receive PSI examinations?
If not, provide the staff with an itemized listing of the components, by system, which will be subject to examination during PSI. The requested listing is necessary to permit the staff to determine if the extent of PSI examinations performed during PSI will meet the applicable regulations and Code requirements.
l B.
Provide isometric and/or component drawings showing the welds, components, and supports which are required to be examined by Section XI of the ASME Code.
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C.
In May and June of 1985, Georgia Power Company successfully demonstrated the ultrasonic procedures and equipment used for examination of the centrifugally cast stainless steel (CCSS) in the l
2
p i
main coolant loop piping at Vogtle Unit 1.
For further information see NRC Region II report numbers 50-424/85-18 end 50-424.35-23.
Provide a discussion of the PSI ultrasonic examinations af the main coolant loop piping at Vogtle Lait 2.
Confirm that the materials in the main coolant loops at Vogtle Unit 2 possess basically the came acoustical properties as those at Unit 1, that the equip?.ent and procedurtes being used for PSI examination at Unit 2 meet the methodology requirements of Section XI of the ASME Code, ar.d that the detection of significant defects, if present, is pessible.
D.
Calibration standards meeting the Code requirements were not obtained and used during the PSI examin.ttons of the Pressurizer nozzle-to-safe end welds at Vogtle Vait 1.
Section XI, Article III, Paragraph III-3410 requires that basic calibration blocks shall be made from material of the same nominal diameter and nominal wall thickness or pipe schedule as the pipe to be examined. Verify that appropriate calibration biccks will be obtained and utilized during PSI examinations at Vogtle Unit 2.
l E.
Calibration standards meeting the Code requirements of Section XI, l
Article III, were also not obtained and used during the augmented volumetric examination of thin-walled (less than 0.5 inch wall thickness) and small diameter Class 2 piping welds in the Engineered Safety Systems during PSI examinations at Vogtle Unit 1.
Verify that appropriate calibration blocks will be obtained and utilized for examinations of these welds during PSI at Vogtle Unit 2 l
l F.
Provide a list of the ultrasonic calibration standards being used l
during the PSI examinations at Vogtle Unit 2.
This list should include the calibration standard identifications, material l
specifications, and sizes.
G.
The examination category tables for Class 2 systems in Section 3 of the PSI Program, with regard to the volumetric examination of longitudinal piping welds (Code Item Nos. C5.12 and C5.22),
3
P.
o reference Note 6.
Note 8 states; "Some of the longitudinal welds may be made with the addition of filler metal and 2thers aay be made without the addition of filler metal. A Code examinttion will be accomplished to the extent practical." Provide clarification with regard to why presence or absence of filler metal, for the longitudinal searr welded piping, will affect the Code-required volumetric and/or surface examinations.
H.
Paragraph 1.13 of the Program states: "The relief, requests will address the area of relief, ASME Code examination requirements, Code item no. and category, if applicable, basis for relief, and alternate examination, if any."
If requesting a partial relief from a Code requirement, also include an estimate of.the percentage of the Code required examination that is being completed. The relief requests are not included in Revision 2 of the Unit 2 PSI Program, as the Applicant states that the examinations art: presently being performed.
Estimate when the requests for relief for Vogtle Unit 2 PSI will be received for staff evaluation.
The schedule for timely completion of Ris review requires that the Licensee provide, by the requested date, the above requested information and/or clarifications with regard to the Vogtle Electric Generating Station, Unit 2, Preservice Inspection Program Plan, Revision 2.
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