ML20234E382
| ML20234E382 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/25/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-2702, NUDOCS 8707070557 | |
| Download: ML20234E382 (11) | |
Text
'
9
'GeorgdP6wer Company tan Ge a 0 08.
f Telephone 404 526-6526 Mailing Address:
l' Post Office Box 4545 Atlanta, Georgia 30302 -
b Georgia Power L T. Gucwa the southern electric system
' Manager Nuclear Safety
- and Licensing SL-2702' 0359m-X7GJ17-V790 June 25, 1987 U. S.LNuclear Regulatory Commission ATTN:
Document Control Desk
'Hashington, D.C.
20555 i
PLANT V0GTLE - UNIT 1 l
NRC DOCKET 50-424 1
OPERATING LICENSE NPF-68 PRESERVICE INSPECTION
SUMMARY
REPORT Gentlemen:
By letter SL-1684 dated December 23, 1986, Georgia Power Company j
(GPC) advised the NRC of its position concerning the submittal' of. a summary report (American Society of ~ Hechanical. Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Form NIS-1. Report) for preservice inspection activities conducted at Plant Vogtle Unit 1 (VEGP-1).
Using a Code interpretation (Code Interpretation XI-1-83-15) as a basis, GPC.
indicated that it would not submi t a summary report to the NRC.
Discussions on June 9,1987 with the NRC staff,. including' the NRC Vogtle Licensing Project Manager (LPM), indicated' that the _NRC will: require GPC to submit a
summary report documenting completion' of. preservice inspection activities at VEGP-1.
GPC previously notified the NRC of the completion of design, construction, and preoperational testing required for fuel loading at VEGP-1 by letter dated January 16, 1987.
. hile not W
specifically addressed, that submittal inferred that' the..preservice inspection activities had been completed.
Pursuant to the June 9, 1987, telephone conversation with the. NRC Vogtle LPM, enclosed herein is a - summary ' report on VEGP-1. preservice inspection activities.
'The report.is believed Lto 'be. consistent in-
-content with that described by the lLPH and therefore. constitutes the
" Summary Report /NIS-1 Form Report" required by Subarticle INA-6200 of the 1980 Edition of the ASME-Code,Section XI, with Addenda through Winter 1980.'
The enclosed report was compiled from excerpts ~of the-Southern
. Company Services - prepared report, "Vogtle Electric. Generating ' Plant
Baseline Preservice Examinations Final. Report - Unit.1,"
which..is available 'at the plant' site for review. Other information, e.g., reactor-pressure vessel examinations, steam generator tubing' examinations, etc.,
is also available for. review.
.The VEGP-1 preservice inspection activities were conducted utilizing an authorized inspection agency, Hartford Steam Boiler Inspection and Insurance Company, to verify the performance of examinations and tests as required by.the Code.
4 PDR, ADOCK 05000424
- f 8707070557 870625 PDR
t k
Georgia Power n U. S. Nuclear Regulatory Commission June 25, 1987 Page Two This submittal should be forwarded to the Office of Nuclear Reactor Regulation for review.
A copy of this submittal has been forwarded to NRC Region II for their review.
Should you require any additional information in this regard, please contact this office at any time.
Sincerely, fr &
_m L. T. Gucwa JAE/im
Enclosure:
Summary Report for Plant Vogtle Unit 1 Preservice Inspection c:
(see next page) 0359m 4
)
i 700775 1
Georgia Power d i
U. S. Nuclear Regulatory Commission June 25, 1987 Page Three j
i c: Georaia Power Comoany Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico Mr. C. H. Hayes G0-NORMS Southern ComDany Servicn Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridge Mr. B. H. Churchill, Attorney-at-Law Troutman. Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law U. S. Nuclear Regulatorv Commission Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle Georaians Against Nuclear Enerav Mr. D. Feig Ms. C. Stangler i
I 0359m 700775
Georgia Power h(-.
ENCLOSURE PLANT.V0GTLE'- UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 PRESERVICE INSPECTION
SUMMARY
REPORT INTRODUCTION Southern Company. Services (SCS) and their contractors performed baseline nondestructive examinations -(NDE) of selected _ Class 1 and 2 components at -
Georgia Power Company'.s Alvin H. Vogtle Electric Generating Plant Unit 1 (VEGP-1).
Preservice inspection activities began.in June 1984 and were completed in January.1987.
.VEGP-1_ is a Westinghouse pressurized.'. Water reactor located in Burke County, Georgia.
Contract personnel which were utilized'. in the performance of nondestructive examinations were:
Combustion Engineering. (C-E).. Lambert, MacGill, and. Thomas, Inc.. (LHT), Nuclear Energy Services (NES), Sonic
' Systems International (SSI), and Zetec.
Combustion Engineering performed the reactor pressure vessel examinations utilizing their own procedures.
They performed mechanized ultrasonic -
examinations from the vessel interior and: some manual ultrasonic examinations from the exterior.
In addition, C-E performed visual and surface examinations.
The results of these. examinations are included in a separate report entitled "Vogtle Electric Generating Plant '-- Unit 1 Reactor Pressure Vessel and Closure Head Preservice. Examination."
The C-E report is available at the plant. site for review.
Zetec, Inc. performed 100 percent eddy current examination of the steam generator tubing.
The results of the steam generator-tubing examinations performed ' by Zetec are. included in a separate report entitled."Vogtle Electric Generating Plant Unit 1 Eddy Current Inspection Report" which is-available at the plant site for review.
Results of the examinations on the Class - 3 welded attachments ~ and the -
component supports are.available at~the plant site for review.
An. authorized inspection agency, Hartford Steam Boiler.. Inspection and Insurance
- Company, was utilized during the course of preservice inspection activities to verify the performance of examinations and tests.
0359m E-1 06/25/87 SL-2702
- 700775
l k
G' orgia Power h c
ENCLOSURE (Continued)
PRESERVICE INSPECTION
SUMMARY
REPORT COMPONENTS SUBJECT TO EXAMINATION Plant ' components subject to examination were selected. and classified for examination in accordance with: Section XI of the America'n-Society-of Mechanical Engineers (ASME)- Boiler and Pressure Vessel Code,. " Rules for Inservice Inspection of Nuclear Power Plant. Components", 1980. Edition with Addenda through Winter 1980 except that the reactor pressure vessel was examined with Addenda.through Hinter 1981.. The extent of the examinations for Residual H_ eat Removal (RHR),. Emergency Core Cooling System '(ECCS)', and Containment Heat Removal (CHR). systems was determined-by the 1974 edition of ASME Section XI with Addenda through Summer 1975 as required by 10 CFR 50.55a.
The classification of a J component as 'ISI Class 1,
2, or 3 for Inservice Inspection does not imply that.each component was designed or constructed to that same ASME Code.
classification requirement.
The safety design. codes remain as. stated in the Vogtle Electric Generating Plant Final Safety Analysis Report (FSAR).
In addition to the above Code requirements, the Nuclear Regulatory Commission (NRC) has imposed certain augmented examinations as added assurance of structural reliability.
Those components and the examinations performed are as follows:
o The results of the manufacturer's testing and examination were used to satisfy the requirements of plant technical specification 4.4.10.2 and FSAR paragraph 1.9.14.2 for the reactor coolant pump flywheels.
o The steam gerierator tubing was examined in accordance with Standard Technical Specifications (NUREG-0452 Rev. 4) and Regulatory Guide 1.83, Rev. 1.
This examination consisted of the full length of 'all steam generator tubes.
The examination of the steam generator tubes and the results thereof were discussed in Georgia Power : Company.-
letter GN-946 dated June 13, 1986 to the NRC.
o Certain portions of the ISI Class 2
- piping, which penetrate containment, are designated as high energy lines.
The augmented examinations consisted of a 100% volumetric examination of the large-diameter Main Steam and Feedwater System welds ~between the containment penetration and the first rigid' restraint outside-containment.
0359m E-2 06/25/87 SL-2702
' 700775:
..)
k Georgia Power n
, ENCLOSURE (Continued)
PRESERVICE INSPECTION
SUMMARY
REPORT
' COMPONENTS SUBJECT TO EXAMINATION (Continued) o A minimum of 81. of the' total number of welds in the engineered safety systems (Nuclear Service Cooling Water, Safety Injection, Residual Heat Removal, Containment Spray, and Chemical and Volume Control) were subject to an ultrasonic examination in accordance with the requirements.of the VEGP Safety Evaluation Report, Paragraph 6.6.3.
These added welds were mostly in thin-walled and small diameter piping that had - not -previously been. selected for. volumetric ' weld examination due.to. size, pressure,.and ' temperature. exemptions.
The subject' welds. were addressed in Georgia Power Company letter GN-875 dated.May 7, 1986 to the'NRC.
EXAMINATION DOCUMENTATION Selected. Class 1 and 2 components were examined in accordance with.the following documents:
o Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of' Nuclear Power Plant Components",1980 Edition with Addenda through j
Hinter 1980.
)
o "Vogtle Electric Generating Plant Unit 1
Preservice_ Inspection Program ISI-P-002."
o "Vogtle Electric Generating Plant Unit 1 Preservice Inspection Plan ISI-P-001."
The Reactor Pressure Vessel examinations complied. with above documents except that the Hinter 1981 Addenda to the 1980 Edition of - the ASME Section XI Code was used.
0359m E-3 06/25/87 SL-2702 700775
g l
Georgia Power n j
ENCLOSURE (Continued)
PRESERVICE INSPECTION
SUMMARY
REPORT EXAMINATION DOCUMENTATION (Continued _).
j The Class 1 and 2 systems which were examined using nondestructive j
techniques are listed below with their applicable system number:
l lyliftnj Svstem Nwnbar i
Reactor Coolant 1201 4
Nuclear Service Cooling Water 1202 Safety Injection 1204 Residual Heat Removal 1205 i
j Containment Spray 1206 Chemical and Volume Control 1208 Main Steam 1301 Auxiliary Feedwater 1302 i
Condensate and Feedwater 1305 EXAMINATION METHODS The nondestructive examinations were performed utilizing approved procedures which met the requirements of the applicable section of the ASME Boiler and Pressure Vessel Code.
The C-E and Zetec NDE procedures as well as the visual procedures for component supports are included in t
their respective final reports which are available for review at the i
plant site.
SCS auxiliary procedures were used to measure search unit i
location, record results, and document details on the applicable forms when referenced by an NDE procedure.
The SCS NDE and auxiliary procedures are included in their report, "Vogtl e Electric Generating Plant Baseline Preservice Examinations Final Report - Unit 1," which is available at the plant site.
NONDESTRUCTIVE EXAMINATION PERSONNEL All SCS personnel were certified to SCS written practice AUX-H/F/V-300 which meets the applicable codes and standards.
All contractors were certified to their own written practice and were audited by SCS Quality Assurance.
Personnel certifications for C-E, Zetec, and those personnel 0359m E-4 06/25/87 SL-2702 700775
i j
k Georgia Power L.
1 i
ENCLOSURE (Continued)
PRESERVICE INSPECTION
SUMMARY
REPORT i
NONDESTRUCTIVE EXAMINATION PERSONNEL (Continued)
')
l who performed the visual examination of component supports are: included 1
in their respective final reports.
The
. remaining NDE personnel certifications are included in. the. aforementioned SCS-prepared repcrt.
Personnel certifications for SCS and its contractors are available at the' plant site for review.
SPECIAL EXAMINATIONS During the examination of some types of materials, it was discovered that new methods and equipment would have to be developed in order to provide the best possible examination.
The -following describes those developmental activities:
(1) Selected 10-Inch Safety Injection Piping When using conventional shear wave transducers during the initial ultrasonic calibration using calibration block ISI-D-306 (which is fabricated from 10-inch Schedule 140 piping, SA-376, TP316), the ultrasonic beam angle would vary or shif t at different locations within the material.
This is undesirable since--the beam angle would not permit sufficient Code coverage to locate discontinuities.
Since the calibration block was fabricated from the.same material as used in the plant, the characteristics were the same.
A piece of this material was subjected to metallurgical analysis'.
The results from the analysis showed that this material has an abnormal banded-microstructure rather than a uniform equiaxed microstructure which results from incomplete annealing.
This condition does. not effect the structural integrity of the component.
The calibration block was then sent to a leading manufacturer of.
ultrasonic equipment, KB Aerotech, so.that a transducer could be developed.that would - effectively examine-this type of piping material.
The transducer that gave the best results was a 3/8" x 3/4" dual element transducer utilizing a longitudinal wave mode.
Curved. shoes were also utilized to reduce coupling noise.
The NDE--
examiners were trained in this technique prior to the examinations.
0359m E-5 06/25/87 SL-2702
1 I
4 Georgia Power m.
ENCLOSURE (Continued)
PRESERVICE INSPECTION
SUMMARY
REPORT 1
t f
SPECIAL EXAMINATIONS (Continued) l (2) Ultrasonic Examination of Cast Stainless Steel Reactor Coolant Loop Piping SCS developed an acceptable examination method for the ultrasonic examination of centrifuga11y cast stainless steel piping.
The reactor coolant loop piping is fabricated from SA-351, CF8A material.
The piping is centrifugally cast and the elbows are static cast.
The material has an extremely coarse and.somewhat irregular grain structure which causes significant attenuation and some angular differences during typical ultrasonic examination.
The basic calibration block (which is a dropout of the same material utilized for the reactor coolant piping) was sent to KB Aerotech so that a transducer could be developed to enhance the inspectability of this material.
They designed a 1.0 inch dual-element transducer i
focused at a depth of 2.5 to 3.0 inches, utilizing a 45 degree refracted longitudinal wave with a frequency of 1.0 megahertz (MHZ).
The transducer was mounted on Lucite shoes curved for axial and j
circumferential scanning which greatly reduced the signal-to-noise i
ratio on the ultrasonic examination instrument display.
j SCS, using this new transducer design, coupled with a Krautkramer i
USL-38 ultrasonic instrument and a procedure (UT-V-406) developed by i
SCS, successfully demonstrated this technique to NRC Region II, who determined this to be a conservative method of detecting ID reflectors.
Prior to examination, ID contours were taken at several points around each weld to identify counterbore locations and aid in the evaluation of any indications.
In addition to the ultrasonic examinations, radiographs were also reviewed.
0359m E-6 06/25/87 SL-2702
'0077L
y y
s k; t *
)r f
,u L
( [,, i t %' (
f
-6 l
},;'"
8 "y
3 f
.k i
Georgia Power h(
i I,
.v 4
w 4
J
,'4 s
c sQ ;!.
p t,'
t t
i
.I 4
~
4 ENCLOSURE (Continued) 9 n\\
n PRESERV1%fINdPECTION
SUMMARY
REPORl y
, i j
SPECIA'. FFJJIl0NS (Continued)
I t,
+
(3) Ultrasonics Examination of Thin-Wall Piping. (less than nomigal
.5 inches) q-N>
g W.
o Thin-wall, piping was fxamined due to the imposion of 4certain
%e augmented programs by IIe NRC. -SCS developed a procedure (UT '/ 4971h4 3-for the examination of t?ese welds using a 1/2-node examination,.
By'b5,f utilizing ;small diameter (1/4 inch) transducgWd%T fe'didsd tion' b
's,
wedge to-udex poirt,1SCS was able tdgrovide the maximum coveragi; s
rotsible dud 7to the. thin wall aersus wide weldT crown. b Thost i i 2.25 MHz,. 600*tecad.T examinations were perfdrnd usine a f/4 inch,
.rN,~
t wave trar;cchcer with a modifM wedge.g ' 4 i
^
y y
The,0circumferential scans (clodelse L and' counterciockwiseM_'were ]
omined from this procedure, because in mosticates',,the sour f b9am ^
o did not hit fl.C inside oiametei' and the wide, bwelded cer,#tbryof f
f the weld crowns did not permit favorable coveraieA Thr nct be ground fluth due to the posdbility o? mt91wa 'wakt welds cotildviolations **
i
. from root, concavity and close tolerances.
L' W
(
)
The ultrdsenic equipment was cllibraiedt on a flat bicck instead of M, the ASME tisic calibration blo"ck. 'The flat block (ISI-D-347A)]D,75; d Inches thi<.k anh Contains 1/ltth.. inch ' side-drilled holes steppidfat~
1/10th-inch incrpents through the thickness.
A comparison of thi
+
q flat calibrulon tiock versus.the ASHE basic calibration block showed s i
l the response obtain'qd from tn'a side-drilled holes was more sensitivO'
^
' " than the response from ' theJCode-required, notc%'b t dThe 50% DAC
\\
necarding level ruing the reiponse from 1/1Ginrd 61js-drille6 holer io, the.75-inch ~ flat pinte 'it(mori conservattde by 6dB than~thd recording l evel.
tsing the response.frorn not;nes.
Since thd circumferentiql scais were omitted,' the. curvaturv of the p)is did not effect the) exam;inations.
\\'
p i.
r s
{
,y I
'}
9, q
n-
{
s
- [
k ft
\\>
(
's 3
~,:
f
~
i
}\\
\\
5 7
3' j
i s
e 4
0359m c
E-7 06/25/87
\\ s g (,i J Sm'-2702 ilh a
s-4-
(.
(
,y
% (
s f
Jp V.
h' t
ML xb r( ~f..
}
"~
Georgia Power b ENCLOSURE (Continued)
ERESERVICE INSPECTION
SUMMARY
REPORT REPORTABLE INDICATIONS All reportable indications were evaluated per the requirements of the 1980 Edition of the ASME Section XI Code with Addenda through Hinter 1980 (except the reactor pressure vessel which utilized the Winter 1981 Addenda).
Relief Request No. 45, which has been submitted.to and approved by the NRC, addresses the use of acceptance criteria of Subparagraph IHB-3410.1 of the Code for other specific component examinations, e.g.,
pressurizer, steam generators, etc..
Components containing reportable indications were either found to be acceptable or -
were appropriately repaired or replaced and reexamined with acceptable.
results.
The details of which components and reportable indications and
[
how each was resolved to the satisfaction of the representative (s) of the authorized inspection agency are contained in the detailed reports at the plant site and are available for review by'the NRC at any time.
REPORT INFORMATION This summary report briefly describes the preservice. inspection activities conducted at Georgia Power Company's Plant Vogtle Unit I and as agreed to by the NRC constitutes the " Summary Report /NIS-1 Form 1
Report" required by Subarticle IHA-6200 of the 1980 Edition of the ASME Section XI Code with Addenda through Winter 1980.
As noted.herein, the final reports generated by Southern Company Services and its contractors are available at the plant site for review and should be referred to should additional information be desired by the NRC.
These and other documents pertinent to the preservice inspection at the subject facility will be made available to the NRC upon request at the plant site.
0359m E-8 06/25/87 i
SL-2702 s.,.