ML20212F305
| ML20212F305 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/05/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1031, NUDOCS 8608130286 | |
| Download: ML20212F305 (11) | |
Text
Georgia Fbwer Company Fbst Offic] Box 282 Waynesborn Georgia 30830 Telephone 404 554-9961 404 724 8114 Southern Company Services, Inc Post Office Box 2625 b
Birmingham, Alabama 35202 Tennone2058me "
Vogtle Project August 5, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GN-1031 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF: BAILEY TO DENTON, GN-875, S/7/86 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 2: PRESERVICE INSPECTION (PSI) PROGRAM
Dear Mr. Denton:
The referenced letter transmitted the VEGP Unit 1 PSI program. That program identified 38 relief requests. Attached are five additional relief requests, RR-39 through 43. These relief requests are the total number identified to date; additional relief requests are not anticipated. Also included in the attachment is a revision to RR-19 transmitted to your staff by the referenced letter. These relief requests, RR-19, RR-39 through 43, will be included in a revision, scheduled for September 15, 1986, to the PSI Program.
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, J. A. Bailey Project Licensing Manager JAB /sm xc: List attached.
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8608130286 860805 DR ADOCK 05000424 PCd
Director of Nuclear Reactor Regulation File: X7BC35 August 5, 1986 Log:
GN-1031 Page 2 JAB /sm 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. C. Teper W. C. Ramsey L. T. Gucwa Vogtle Project File 0640V i
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VEGP-1 RR-39
_ Component or Relief Area Mechanized volumetric examination of pressure-retaining shell and head welds in Reactor Vessel outside the beltline region.
Weld Identification Numbers: 11201-V6-001-WO3 11201-V6-001-WO4 11201-V6-001-WO6 11201-V6-001-WO7 11201-V6-001-W12 11201-V6-001-W13 11201-V6-001-W14 11201-V6-001-W21 11201-Y6-001-W22 11201-V6-001-W23 11201-V6-001-W24 Requirements from Which Relief is Requested Item No. 81.10, Category B-A, Table IWB-2500-1 of ASME Section XI requires volumetric examination of the Reactor Vessel shell welds. Applicable examination volume is shown in Figure IWB-2500-1 for circumferential welds and IWB-2500-2 for longitudinal welds.
Item No. B1.20, Category B-A, Table IWB-2500-1 requires volumetric examination of Reactor Vessel head welds.
Applicable examination volume is shown in Figure IWB-2500-3 for l
circumferential and meridional welds.
Item No. B1.30, Category B-A, requires volumetric examination of the Shell-to-Flange weld.
Examination requirements are shown in Figure IWB-2500-4.
Basis for Relief For RPV welds outside the beltline region, the nominal 450 and 600 ultrasonic examinations are gated as near as possible to the near surface without caesing nearly continuous spurious signals in the gate.
Typically, t
this gating arrangement causes a slight amount of missed volume for these examinations of approximately 0.35-inch depth for the 450 examination and 0.27-inch depth for the 600 examination.
Alternate Examination The Code required volumetric examination was accomplished to the extent indicated above.
VEGP-1 RR-40 Component or Relief Area Notch length in Basic Ultrasonic Calibration Blocks for examination of vessel welds.
Calibration Block Numbers:
ISI-D-400A ISI-D-401A ISI-D-402A ISI-D-403A Requirement from Which Relief is Requested Figure T-434.1, Article 4,Section V ASME Code requires a notch length of 2-inches in basic ultrasonic calibration blocks for examination of vessel welds.
Basis for Relief The ultrasonic calibration blocks. supplied for the RPV by the ve'ssel manufacturer contain notches ~ that are approximately 13/4-inches in length.
These short notches provide no difficulty in establishing acceptable calibrations.
Alternate Examination A Code examination was accomplished using instruments calibrated on blocks containing notches less than two-inches long.
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VEGP-1 RR-41 Component or Relief Area Use of a centrifugally-cast stainless steel (SA-351 CF8A) piping calibration block in conjunction with a flat composite (SA-508 CL 2 and SA-240 Type 316) calibration block for the mechanized examination of the Reactor Vessel nozzle to safe-end welds.
Calibration Block Numbers: ISI-D-331A (Centrifugally-cast stainless steel piping block)
ISI-D-405A (Flat composite block)
Weld Identification Numbers:
11201-V6-001-W33 11201-V6-001-W34 11201-V6-001-W35 11201 -V6-001-W36 11201-V6-001-W37 11201-V6-001-W38 11201-V6-001-W39 11201-V6-001-W40 Requirement from Which Relief is Requested Article III-3411 requires that basic calibration blocks shall be fabricated from one of the materials being joined by the weld.
Relief is requested to use a cast-stainless steel piping calibration block in conjunction with a composite calibration block for the mechanized examination of the RPV nozzle to safe-end welds.
Basis for Relief The RPV manufacturer supplied a flat block fabricated from SA-508 CL 2 and SA-240 Type-316 welded together to fonn a composite block to be used for the examination of the nozzle to safe-end welds. Due to the special near-surface examination technique being applied from inside the vessel during the mechanized examination, the flat contour of the composite calibration block could not be used alone to establish a calibration which was representative of the examination to be performed. An attenuation (dB) comparison performed between the cen.trifugally-cast calibration block (ISI-D-331A) and the flat composite calibration block (ISI-D-405A) revealed that calibration using ISI-D-331A would provide a more sensitive examination for 3 of the 4 channels used for the examination. Based on this information, calibration block ISI-D-331A was used to establish both the sweep position and calibration sensitivity for 3 channels. The sweep position for the other channel was established from ISI-D-331A, but the sensitivity was established from ISI-D-405A because of the required additional dB.
RR-41 (Cont'd)
The use of the. curved surface of the centrifugally cast calibration block, as well as adding the increased sensitivity, provided a superior calibration for the special near-surface examination technique applied to these welds.
Alternate Examination The Code required surface examination was accomplished from the outside of the wel d.
A mechanized ultrasonic examination was completed from the inside using the composite calibration block in conjunction with the curved, surface cast piping calibration block as discussed above.
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VEGP-1 RR-42 Component or Relief Area Volumetric examination of nozzle inner radius section for Steam Generator inlet and outlet nozzles.
Examination Identification Numbers: 11201-B6-001-IR-01 11201-86-001-IR-02 11201-86-002-IR-01 11201-86-002-IR-02 11201-86-003-IR-01 11201-86-003-IR-02 11201-86-004-IR-01 11201-B6-004-IR-02 Requirement from which Relief is Requested ASME Code Item No. 83.140 Category B-D, requires volumetric examination of the.,
nozzle inside-radius section' for steam generator nozzles.
Figure IWB-2500-7 shows the applicable examination volume. Relief is requested from.
accomplishing this examination for the inlet and outlet nozzles on all steam -
generators.
Basis for Relief The VEGP steam generator nozzles are integrally cast as part of the channel head. The configuration of the nozzles does not provide the necessary contact surface for examination.
In addition, the metallurgical structure of the casting in this area does not allow for adequate transmission of ultrasound for the required sound path distance.
Alternate Examination None c.,._
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VEGP-1 RR-43 Component or Relief Area Volumetric examination of steam generator channel head to tube-sheet weld.
Weld Numbers:
ll201-B6-001 -WO8 11201-86-002-WO8 11201-B6-003-WO8 ll201 -B6-004-WO8 Requirement from which Relief is Requested ASME Code Item No. 82.40, Category B-8, requires volumetric examination of the tubesheet-to-head weld on the primary side of steam generators. Figure IWP-2500-6 shows the applicable examination volume and includes essentially 100 percent of the weld volume. Relief is requested from examining 100% of tha volume of these welds.
Basis for Relief Four vessel sup' ports and an identification tag prevent access Eto 100% of the weld length by the transducer.
The tube sheet interferes with transducer placement for the upstream scans and the curvature of the channel head interferes with the downstream scans.
Alternate Examination Ultrasonic examinations were accomplished on the percentage of weld volume indicated in Attachment 1.
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VEGP-1, RR-43
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Percentage of Weld Volume Examined Weld No.
Weld No.
Weld No.
Weld No.
Examination 11201-B6-001 -WO8 11201 -B6-002-WO8 11201-B6-003-WO8 11201 -B6-004-WO8 1
Upstream 450 Scan 71 %
51 %
51 %
Sl%
i Downstream 450 Scan 80%
60%
67%
60%
l Upstream 600 Scan 49%
36%
36%
36%
Downstream 600 Scan 80%
42%
47%
42%
Upstream Laminar Scan 49%
36%
36%
36%
Downstream Laminar Scan 80%
42%
47%
42%
Upstream 00 Planar Scan 80%
80%
80%
80%
Downstream 00 Planar Scan 80%
80%
80%
80%
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VEGP-1, RR-19 Revision 1 Identification No.
Code Cat./ Item No.
Scan Description 11201-058-1 B-J/B9.11 600 6" Safe-end to elbow 11201-058-3 B-J/89.11 600 6" Pipe to pipe 11201-058-5 B-J/89.11 600 6" Elbow to pipe 11201-059-8 B-J/89.11 600 6" Elbow to pipe 11201-059-9 B-J/89.11 600 6" Pipe to elbow 11201-059-11 B-J/89.11 600 6" Pipe to tee 11201-059-12 B-J/89.11 600 6" Tee to pipe 11204-024-12 B-J/89.11 600 6" Elbow to pipe 11204-024-15 B-J/89.11 600.
6" Pipe to elbow 11204-024-16 B-J/89.11 600 6" Elbow to pipe 11204-024-17 B-J/89.11 60d 6" Pipe to elbow 11204-024-18 B-J/89.11 600 6" Elbow to pipe 11204-044-4 B-J/89.11 600 6" Pipe to elbow 11204-044-7 B-J/B9.11 600 6" Elbow to pipe 11204-044-8 B-J/89.11 600 6" Pipe to elbow 11204-044-9 B-J/89.11 600 6" Elbow to pipe 11204-044-10 B-J/B9.11 600 6" Pipe to elbow 11204-044-12 B-J/89.11 600 6" Pipe to elbow 11202 ',96-7 Supplemental UT 600 8" Valve to pipe 11202-196-17 Supplemental UT 600 8" Pipe to elbow 11202-196-27 Supplemental UT 600 8" Pipe to elbow 11202-196-32 Supplemental UT 600 8" Elbow to pipe 11202-196-48 Supplemental UT 600 6" Tee to pipe 7-31 a
VEGP-1, RR-19 (Cont'd)
Revision 1 Identification No.
Code Cat./ Item No.
S_can Description 11202-196-49 Supplemental UT 600 6" Pipe to elbow 11302-107-44 C-F/C5.21 600 6" Pipe to elbow 11302-108-42 C-F/CS.21 600 6" Pipe to elbow 11302-108-43 C-F/C5.21 600 6" Elbow to transition piece 11302-109-13 C-F/C5.21 600 Penetration to 6" pipe 11302-109-16 C-F/C 5.21 600 6" Pipe to valve 11302-109-18 C-F/C5.21 600 6" Pipe to elbow
,11302-109-19 C-F/C5.21 600 6" Elbow to pipe 11302-109-29 C-F/C5.21 600 6" Valve to pipe 11302-109-40 C-F/C5.21 600 6" Pipe to elbow 11302-109-41 C-F/C5.21 600 6" Elbow to transition piece 11205-E6-002-W01 C-A/C1.10 600 Shell to flange weld 11205-E6-002-W02 C-A/C1.20 600 Shell to head weld 11205-E6-002-WO4 C-B/C2.21 450 Nozzle to shell weld 600 11205-E6-002-W05
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