ML20080F123
| ML20080F123 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/08/1983 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6820 IEB-82-03, IEB-82-3, NUDOCS 8309190172 | |
| Download: ML20080F123 (37) | |
Text
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i GPU Nuclear N
ked Rive, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:
1 September 8, 1983 i
Dr. Thomas E. Murley, Administrator Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Final Response to IE Bulletin No. 82-03 The inspection program for intergranular stress corrosion cracking (IGSCC) in the recirculation system piping at the Oyster Creek Nuclear Generating Station has been completed. The enclosed 'Ibpical Report No. 012, Rev.1,
" Oyster Creek Recirculation System Piping Inspection Program", dated September 5, 1983, summarizes the results of this effort and fulfills the requirements of IE Bulletin No. 82-03.
Mr. T. T. Martin's letter to us concerning Inspection Report 50-219/83-21, dated August 9, 1983, indicated that the adequacy of our inspection results would remain questionable until further examinations or evaluations to characterize the ultrasonic reflectors were made. The enclosed information will provide details of the additional examination performed for that purpose.
In order to assure that satisfactory inspections with correct characterizations were performed, actions were taken to verify the accurate evaluation of all data. These actions are listed as follows:
Independent Reviews - Three organizations external to GPUN (this includes one NRC group) performed independent reviews of examination data. The results from these supplementary reviews were factored into developing the optimum extended inspection program.
Cther types of examinations - Remote visual and penuttant tests were performed on three of the most highly suspect welds. No indications of IGSCC were found. The results of these inspections are on tape and available for viewing by NRC staff.
8309190172 830908 PDR ADOCK 05000219 h
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9 Dr. Thomas E. Murlcy, Administrator r
'Page 2 GPU Nuclear has gone beyond the scope of IE Bulletin No. 82-03 in order to assure ourselves that an edequate assessment of potential recirculation piping problems has been made for Oyster Creek. These efforts have included inspections of attached, smaller bore piping, attendance in the Battelle Northwest /EPRI-sponsored ultrasonic sizing capability exercise, and evaluation of leak rate detection system sensitivity under Systematic Evaluation Program Topic III-5.A "Effect of Pipe Break on Structures, Systems and Conponents Inside Containment". In addition, a nore restrictive unidentified leak rate Technical Specification limit is being developed.
In the event that any additional comments or questions regarding this issue arise, please contact Mr. James Knubel, at 201-299-2264.
Very truly yours,
, i 1J Peter B. Fiedler Vice President and Director Oyster Creek PBF: dam Enclosures Sworn to and Subscribed before me this B" day of Sc4mNr 1983.
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\\d Notary Public of New Jersey phttLE05DFOM cc: Mr. Dennis M. Crutchfield, Chief gp3Y W.UUC U Operating Reactors Branch #5 et er r# #" " ~ ~ '
Division of Licensing U.S Nuclear Regulatory Commission Washington, D.C.
20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N.J.
08731 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
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0YSTER CREEK RECIRCULATION SYSTEM PIPING INSPECTION PROGRAM Final Response to NRC I&E Bulletin No. 82-03, Rev.1 Topical Report No. 012
( Rev. 1)
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1 Tcpical Report No. 012 Page 2 of 7
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i Abstract The augnented inservice inspection program for I&E Bulletin 82-03 for Oyster Creek's Recirculation System has been performed.
Preliminary results of this ultrasonic inspection revealed that two welds contain indications similar to those of IGSCC and several welds possess geomet,ric/ fabrication indications. Follos-up internal examinations were required to provide more complete information. These inspections are now complete. Final analysis of all the dati~ including ^' internal visual'and penetrant examinations snowed not IGSCC indications.
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i OYSTER CREEK RECIRCULATION SYSTEM PIPING INSPECTION PROGRAM INTRODUCTION
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In October, 1982, the NRC issued I&E Bulletin No. 32-03 pertaining to
" Stress Corrosion Cracking in Thick-Wall Large-Diameter, Stainless Steel, Recirculation System Piping at BWR Plants". The bulletin concentrated on Nine tiile Point's recirculation system pipe cracking experiences. With Oyster Creek being identified as an addressee of the bulletin and being most similar in design t'o'Nine Mile Point, GP'U'N deve~1oped a'nd implemented an Inspection
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Program for ultrasonic examination of recirc. system piping welds which would satisfy the new requirements. Below is the final response to supplementing Action Items 4, 2 Pnd 3 of the bulletin based on the results of the completed Inspection Program.
METHODS 4.a.(1) & (2)
As part of the Inspection Program, GPUN and its NDE contractor, utilizing GPUN approved procedures and calibration standards, qualified inspection teams on cracked pipe sections from NMP at Battelle Columbus Laboratories in accordance with the Bulletin's requirements.
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Topical Report No. 012 Page 4 of 7 i
j The initial inspection sample size, as shown in Figure 1 and reported in l
GPUN's 82-03 submittal dated December 1,1982, was 16 welds. The selection of the welds to be inspected was not a random sampling. Rather, the welds selected were those which would be more susceptible to IGSCC cracking, based on three conditions (1) high stress rule indices, (2) weld repairs performed during construction and (3) welds being similarly located to those at Nine Mile Point where cracks were initially detected. Prior to the start of f
inspection, further information became available concerning weld repairs during construction. Accordingly, additional welds were included in the inspection plan, increasing the size to 22 welds (Figure 2). After prelimi-nary inspection result's revealed two locations with possible IGSCC, the inspection plan was again increased to include all similarly located welds on the remaining recirculation loops (Figure 3), for a total of 31 welds inspected.
Following the completion of the external examination (UT) of the 31 welds, internal visual and penetrant inspections were performed on 3 welds to further verify the lack of evidence of any IGSCC.
4.a.(3)
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Previously responded to by Ref.1.
4.a.(4) l Previously responsed to by Ref. 1.
4.b. through 4.d Previously responded to by Ref. 1.
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Topical Report No. 012 Page 5 of 7 INSPECTION RESULTS 2.
The original inspection results revealed that only two welds contain indications which were characterized as possible intergranular stress corro-sion cracking (IGSCC) and five welds with indications characterized as fabri-
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cation / geometric-type.
While further evaluation was needed on the two welds with possible IGSCC, inspections were scheduled for nine additional welds. These nine included all welds similar in location to the two above mentioned welds plus those selected under the requirements of ASME Section XI Inservice Inspection.
The 'alditional in'spections' have b~eert completed. The results of the
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additional inspections revealed three welds with indications which were characterized as fabrication or geometric conditions. Seven of the ten welds with indications were then radiographed for further characterization. Appen-
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dix 1 provides a detailed summary of the UT inspection results.
Following fuel off-load, vessel drain and recire. valve (s) disassembly, additional radiography was performed on selected welds.
Internal visual inspections were also performed on the two welds with IGSCC-type indications, NG-B-5 and NG-D-ll. No IGSCC indications were observed.
Although GPUN concluded there was no evidence of IGSCC in any weld inspected, the UT inspection results were then independently reviewed by outside organizations. Additionally, remote visual and liquid penetrant examinations were performed on NG-B-5 and NG-D-11. A third weld, NG-A-14, All highly suspect under the independent review, was also penetrant tested.
three inspection results showed no indications of IGSCC. The details of the r-
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Topical Report No. 012 Page 6 of 7 penetrant, radiography and internal visual inspections and the third party review results are provided in Appendix 2.
PLAN OF ACTION / RECOMMENDATIONS 3.:.
Considering the results reported in Appendices 1 and 2 and the conclu-sions reached, no further inspections are planned during the present outage for Oyster Creek's recire. system piping.
In addition, based on the lack of any evidence of IGSCC in the 31 of 77 welds examined, plus similar result:
from inspections of attached small bore piping (shutdown cooling, clean-up and isolatioW ccndenser-condensate return line), no repair plan or remedial action plan is recommended for the upcoming operating cycle.
A follow-up inspection program shall.be developed for the next refueling outage, taking into consideration the inspection methods of 82-03 and 83-02, the sample inspected this outage, location of welds in the loops, stress levels, and ISI requirements.
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Topical R port No. 012 Page 7 of 7 i
REFERENCES 1)
Letter to Ronald C. Haynes from Peter B.'Fiedler dated December 1, 1982, Re: Oyster Creek Nuclear Generating Station, Docket 50-219, I&E Bulletin 82-03.
2)
Letter to Ronald C. Haynes from Peter B. Fiedler dated February 25, 1983, Re: Oyster Creek Nuclear Generating Station, Docket 50-219, I&E Bulletin 82-03.
3)
Letter to Regional Administrator, Region I from Peter B. Fiedler, dated May 25, 1983, Re: I&E Bulletin 82-03.
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sms Date April 5, 1983 q
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Muolear Subject nectre. Piping 1:.,xamination Results To T.
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Pa t te rson Location Oyutor Creek l
l The following information delineates the current status of examination results obtained from the initial " Quick Look" for 1.GSCC on the recirculation piping system.
The initial " Quick Look" sample was comprised of twenty two (22) welds (Attachment 1).
.The sample size was later expended.during the examination to include four (4) scheduled ISI welds and five (5) welds which closed out the inspection sets for areas where recordable indications were found.
These additions brought the total number of welds examined during the " Quick Look" to thirty one (31).
As a cusult of the examinations the following data was gener.ated:
1.
Twenty one (21) weld heat affected zones (HAZ) were found clear, that is, thare were no recordable indications per the requirements of the Ultrasonic procedure used (6130-QAP-7209.08 Rev. 0).
2.
Ten (10) weld heat affected zones were documented as having rec o rdab le indications per the requirements of the U.T.
procedure.
Locations, evaluations,'and repair status of these 10 welds are shown in Attachments 2, 3, 3A, and 4.
Two (2) weld (HAZ) are considered at this time to have indications characteristic of IGSCC (NG-D-ll and NG-B-5).
Planning for supplemental examinations is as follows.
Remote visuals are to be conducted on the two welds characterized as ICSCC.
If re:;ults of these examinations are not will have to be performed. conclusive a remote surface examination (Dye Penetrant)
In addition, radiography is currently planned for four (4) welds which were evaluated as geometry / fabrication indications and the remaining weld (NG-B-5) characterized as ICSCC.
Plans ace to utilize an ultrasonic signal characterizer (ALN-4060) to be provided thrualso underway the EPRI Institute, as a means to further evaluate the recordable indications referenced in Attachment 3.
April 11.
The use of the 4060 is scheduled for the week of Except for the examinations utilizing the ALN-4060 all other supplemental exams will be scheduled after vessel drain, now scheduled for April 27.
A0000046
v l'ane 7.
T. J.
Pattecson 4
m A further update concerning these examinations will be made as the supplemental examinations are completed and the welds dispositioned.
- d,c a t ~ d R. Outrowski Supervisor, Corporate ISI
- RO/dg Attachments cc:
M.
Allgaier w/ attachments J. Chardos w/ attachments R. DeMuth w/ attachments N. Kazanas w/ attachments R. Pinelli w/ attachments S. Pruitt w/ attachments C. Tracy w/ attachments 0*
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tavun ManttoruJ uc-A-64 "C-N-1 NG-A-t4 h 4,u'h 4.e* h Yes Yuu Yuu NC-C-12 Yes Yue NC-0-11 Yes Yes 60e @ R.T. Video NG-A-5 @
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Op winuun la_:dh 'k 01 I NWL C 110N ILH WLLUS WERE NOTED TO ilAVE t&CORDABLE INDICAl10NS TO DATE PLANNED lELO ADDITIONAL ADDITIONAL FINAL K).
VARIABLE EVALUATION NDE NDE DISPOSITION 0-0-12 SIDE-1 Ind.#200-tack of thru-wall dimension discounts IGSCC SIDE-1 Ind.#201-Location, Lack of length (spot) and lack of thru-wall dimension discounts IGSCC SIDE-1 Ind.#202-Location and CRT pattern amplitude preclude possibility of IGSCC SIDE-1 Ind.#203-Loca tion discounts IGSCC 3-C-12 SIDE-1 Ind. #200-Fabrica tion /geome try condition SIDE-1 Ind.#201-Fabrication / geometry condition 3-D-11 SIDE-1 Ind.#200-Characteristic of IGSCC 0
60, R.T.
Video Ind.#201-Characteristic of IGSCC 60, R.T.
Video 0
3-E-4 SIDE-1 Ind.#200-Fabrication, gemietry condition Ind.#201-Fabrication, geometry condition i-C-22 SIDE-2 Ind.#200-Fabrication, geometry condition i-C-23 SIDE-2 Ind.#200-Fabrication, geometry R.T.
condi tion SIDE-1 Ind.#201-Fabrication, geometry R.T.
condition SIDE-1 Ind.#202-Fabrication, geometry R.T.
condition
-B-5 SIDE-2 Ind. #200-Fabrication, geometry R.T., Video condition SIDE-2 Ind.#201-Fabrication, geometry R.T., Video condition SIDE-2 Ind.#202-Fabrication, geometry R.T., Video condition SIDF-2 Ind.#203-Characteristic of IGSCC R.T., Video SIDE-2 Ind.#204-Characteristic of IGSCC-R.T. Video C-4 SIDE-2 Ind.#200-Fabrication, geometry condition D-4 SIDE-2 Ind.#200-Fabrication, geometry R.T.
condition Ind.#201-Fabrication, geometry R.T.
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TEN WELDS WERE NOTED T0 llAVE RECORDADLE INDICAi(ONS i
WELD' TO DATE PLANNED NO.
VARIABLE EVALUATION AL N
I '10 NG-A-14 SIDE-1 Ind.#200-Fabrication condition 600 R.T.
Ind.#201-Fabrication condition R.T.
9
r WELD llISTORY (WELDS WITl! RECORDA13LE U.T. INDICATIONS)
LD ' '
- DATE OF LOCATION NATURE NO.
FAllRT. CAT EON OF IMPAIR OV REPALR NG-A-14 Pre-1969 3:00 1.F. (3 spots) - repaired NG-B-12 6:00-12:00 I.P. - repaired 6:00-10:00 Gas Pockets / Porosity - repaired NG-C-12 6:00 to 9:00 I.P. - repaired NG-D-ll 5 of 6 on film I.P. and Slag Incluulons-repulced NG-E-4 None NG-C-22 None - Elbow was removed during construction and reweldt-NG-C-23 11one - Elbow was removed,during construccion.and rowelde NG-B-5 2-3 on film I.P'.
- repaired NG-C-4 None NG-D-4 None l
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EXAMINATION TEAMS TEMI NO.
EXAMINERS / LEVEL U.T.
1 McCaully, II/Liebold, II 2
Reichert, II/ Trotter, I 3
McCaully, II/D. Rosa, I 4
Deskiewicz, II/Valden, I 5
Radlbeck, II/D. Rosa, I 6
Deskiewicz, II/Floyd, I 7
Deakiewicz, II/C. Rosa, I 8
Collins, II/Butkiewicz, I 9
Rad 1 beck, II/Floyd, I 10 Minyon, III/Valden, I 11 Liebold, II/Valden, I 12 Reichert, II/Liebold, II 13 Collins, II/Minyon, III 14 Reichert, II/C. Rosa, t 15 Radlbeck, II/Valden, I 16 Minyon, III/McCaully, II 17 Reichere, II/Minyon, III t
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1 Appendix 2 OYSTER CREEK RECIRCULATION SYSTEM PIPING INSPECTION fR0 GRAM REl0RT j
Prepared IIyi R. Ostr'owski Corporate ISI Supervisor b
de 4 9-2.-B.3 Approved:
N. -C. Kazartal, lity Assurance Director - VJa t
I I
c..--
REFERENCE:
1.
Topical Report No. 012 Response to NRC I&E Bulletin No. 82-03, Rev.1, Project No. 32 8025, dated May 10, 1983, authored by R. A. Pinelli and R. Ostrowski.,
INTRODUCTION:
Reference 1 stated the Plan of Action to satisfy I&E Bulletin No. 82-03 would be to pursue possible IGSCC indica-tions by performing further characterization examinations of seven welds by visual, radiography or liquid penetrant, or a combination of these examination techniques.
SUMMARY
The following data summation reflects the analysis of the initial ultrasonic examinations of the recirculation piping welds with further clarifications provided by supplemental, ultrasonic, radiographic, penetrant and visual inspections (see Attachment 1). As a result of the examination data review and logic pattern followed for the examination sequencing and characterization of recordable indications it is concluded that no indications of IGSCC have been con-firmed by this in's~ ection program.
~ ' '
p The examination and data provided are summarized as follows:
1.
As a result of the initial ultrasonic examinations, ten (10) weld heat affected zones were documented as having
- ~ recordable indications per the requirements of the ultrasonic procedure.
Welds #NG-A-14 NG-C-22 See Attachment 3 for NG-B-5 NG-C-23 locations NG-B-12 NG-D-4 NG-C-4 NG-0-11 NG-C-12 NG-E -4 2.
Two (2) of the welds NG-B-5 and NG-D-11 were considered to have indications characteristic of IGSCC and were scheduled for further supplemental examinations - radio-graphy, remote internal visual and remote internal pene-trant examinations.
This required the f abrication of special inspection fixtures which would provide the capabilities for performance and video taping of the penetrant examinations.
3.
Eight (8) of the welds were charac.
ized by GPUN as having reflectors caused by geomet, or fabrication pro-cesses and were processed as follows:
- Velds NG-A-14, NG-C-12, NG-C-22, NG-C-23, and NG-D-4 were radiographed to further characterize the root
_ ~ _.
_ =
conditions. The data provided by the radiography was utilized to further locate the weld root with respect l
.to the ultrasonic signal.
No change was made with respect to initial calls of geometry, fabrication indications.
- Welds NG-B-12, NG-C-4 and NG-E-4 did not require further examinations.
Data from ultrasonic examina-tion was sufficient to resolve characterizations.
l Status of these welds remain the same in that ultra-I sonic indications are the result of geometry fabrica-tion indications.
4 4.
Based on the analysis of an outside third party evalua-tion, weld NG-A-14 was also scheduled for penetrant testing (see Attachment 2).
On completion of the pene-trant examination on welds NG-B-5, NG-D-ll and NG-A-14, it was concluded that IGSCC was not present and there appeared suitable causes for ultrasonic reflectors to be present in the identified areas.
INSPECT'IOTPLAN Procedure 61Y0-dAP-7209.08', "UT Detection of IGSCC in
~
2 APFR0ACH:
Stainless Steel Recirculation System Piping". Rev. O, dated February 16, 1983, was utilized to perform the ultrasonic examinations.
This procedure was qualified as per NRC I&E Bulletin 82-03.
This conservative recording criteria of the ultrasonic procedure is such that ary! reflector greater than
~ normal screen noise (5%) is recorded and required charac-terization and disposition.
I Using the conservative criteria of considering any ultra-sonic reflector with an amplitude greater than 55 full screen height, a total of 10 welds were identified with recondable indications which required characterization of the indic,tions for final disposition.
The ten welds were further analyzed and all were eliminated as having been i
caused by IGSCC.
l l
The process of selecting which welds were to receive further t
examination (s) was as follows:
The ultrasonic, radiographic and visual results eliminated welds requiring further examinations until all ten were dispositioned as not having apparent IGSCC.
The matrix of results are found in Attachment 1.
The process of elimination was as follows:
i 1
1.
Ten welds were selected (see next paragraphs); three of which showed ultrasonic indications outside of the area 2
where IGSCC is found and/or the sizing data showed that the indication fell below the expected amplitude of an IGSCC reflector.
2.
The seven remaining whlds showed five welds whose ultra-sonic data was not characteristic of IGSCC and that had radiographic data indicating geometry as the possible cause of ultrasonic reflectors.
Two of the seven welds (NG-B-5 and NG-D-ll)flectors and were still 3.
in doubt as to possible causes of the UT re were visually examined by the Internal Pipe Inspection Device.
The two welds showed no visual data indicative of IGSCC and had geometric conditions indicating a possible cause of the ultrasonic reflectors.
In order to assure ourselves that satisfactory inspec-tions with correct characterizations were performed, a program was developed to penetrant test areas of the internal surface of the two remaining welds (NG-8-5 and NG-D-11) and provide an independent evaluation of the ultrasonic data..Th,e penetrant test was conducted utilizing a florescent watbr washable penetrant without the use of a developing agent.
This process not only precluded the use of a cleaning agent Other than demineralized water but also precluded the further mechanical complication of applying a developer.
Samples utilizing known IGSCC indications were used during development and qualification of this fixturing, process, and personnel. Results of the penetrant testing on NG-B-5 and NG-D-ll revealed no relevant indi-cations.
The independent review of ultrasonic data is summarized in Attachment 2.
The summary interpretation provided identifies an independent third party review of the data.
At the request of one consultant, additional ultrasonic data was obtained and used for a characteri-zation of the indications. An additional weld, NG-A-14, was identified from the independent review process and subjected to both visual and internal penetrant examina-tion utilizing the same inspection techniques as were used in NG-B-5 and NG-D-ll.
This penetrant examination did not reveal any relevant indications.
This examina-tion concluded the inspection process for the recircula-tion piping welds.
BRANCH PIPING In addition to the thirty-one 26" recirculation welds, a WELDS:
sample of associated branch piping welds was inspected.
O
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This inspection is sunnarized below:
Snutdown Cooling System NU-1-2 indication NU-1-32 Located on longitudinal seam 81/2" to 9" from circum-ferential seam. Radiography perfonned.
Indication identified as concave condition at root.
Isolation Condenser System NE-2-48 NE-2-51 Clean-Up Demin. System ND-1-3 ND-1-8 ND-1-9 Only one weld with recordable indications. Remaining welds clear.
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, ATTACINENT 1 ULTRASONIC INSPECTIONS PERFORMED ON WELDS WITH REFLECTORS IDENTIFICATION 45' ULTRAS 0NICS 60* ULTRASONICS PLOTTED PLOTTED LOCATION MAX TIRU LOCATION MA'X THRU WELD REPORT IDENTIFICATION I.D. HAZ, AMPLITUDE LENGTH WALL I.D. HAZ, AMPLITUDE LENGTH WALL NIMBER NtNBER NUMBER ROOT, WELO INCHES INEHES ROOT, WELD INCHES INCHES i
NG-A-14 1108 200 - RT I.D. HAZ 30%
1"
.180" 400 100%
2"
.180" 1148/l136 200 - RT WELD 25%
1.25"
.120 1148/1136 201 - RT WELD 40%
,. 5 0"
.140 4 01 60%
NA
.140" NG-B-5 159 200 - etT WELD 15%
3.5"
.25"
2.0"
2.25"
.150 NA DUE TO PT PERFORMED 204 - RT HAZ 10%
. 5 0"
.180 NG-B-12 197 200 BSE MTL 10%
3.00" 2 01 BSE MTL 10% - O'-
202 BSE MTL 10%
4.00"
.210 203 BSE MTL 15%
3.00"
.1,00 NG-C-4 1135 200 WELD 40%
.375"
.062 NG-C-12 163 200 - RT WELD 10%
.50&'
.500"
.120 l NG-C-22 165 200 - RT WELD 30%
.500"
.010 NG-C-23 1004' 200 - RT WELD 30%
1.200"
.100 400 OPP HAZ 80%
.280"
.500"
.110 401 OPP HAZ 70%
2.00"
.280 402 OPP WELD 75%
.270" NG-D-4 1139 200 - RT WELD 50%
l.00"
.130 400 WELD 60%
1.50"
.130 401 WELD 50%
NG-D-11 168/195 200 - RT HAZ 45%
1.75"
.060 400 HAZ 25%
1.50"
.200" 50%
12.50"
12.50"
.180 401 HAZ NG-E-4 172 200 WELD 25%
.750"
.120 201 WELD 25%
.250"
.120 400 series numbers reflect 60* data on same indication.
ATTACHMENT 2 RESULTS OF ULTRASONIC DATA INTERPRETATION I.D.
'UT I'NTERPRETATION**
GPUN
SUMMARY
OF IGSCC INTERPRETATIONS
[
WELD IDENTIFICATION NOT NUMBER NUMBER GPUN LMT EBASCO PRESENT PRESENT INCONCLUSIVE
- NG-A-14 200*
NO (Poss.
11 2
0 200 NO IGSCC)
YES/HIGH i
201 N0 NO-GE0M j
i
- NG-B-5 200 NO NO-GE0M NO-P. GEOM 3
0 0
201 NO NO-GE0M NO-P. GE0M 3
0 0
202 NO NO-GE0M NO-P. GE0M 3 1 0
0 1
203*
POSSIBLE INDETER YES/MED 0'
2 1
4 204*
POSSIBLE INDETER YES/MED 0'
2 1
NG-B-I?,
200 NO NO-INCLU N0 3;
O O
j 201 N0 NO-INCLU
-YES/HIGH 2-1 0
J 202 NO NO-INCLU NO 3.
0 0
203 NO NO-INCLU YES/HIGH.
2 1
0 4
NG-C-4 200 NO NO-GE0M N0 3.
0 0
l l
NG-C-12 200 NO NO-GE0M YES/MED 2,
1 0
201 NO NO-GE0M YES 2
1 0
s i
,i NG-C-22 200 N0 NO-GEOM YES/MED 2
1 0
i l
NG-C-23 200 NO NO-GE0M N0 3
0 0
201 NO POSSIBLE NO 2
1 0
202 NO NO-GE0M N0 3
0 0
)!
NG-D-4 200 NO NO-GE0M NO-P. GEOM 3
0 0
201 NO NO-P. GE0M 3
0 0
4 i
- NG-D-ll 200*
POSSIBLE POSSIBLE YES/HIGH 0
3 0
POSSIBLE POSSIBLE YES/MED 0
3 0
j NG-E-4 200 NO POSSIBLE NO 2
1 0
j 201 NO POSSIBLE NO 2
1 0
i
- Penetrant examination completed on internal surface areas. No relevant indications.
- NRC Interpretation presented in NRC Inspection Report No. 50-219/83-21.
ATTACHMENT 3 2
' ~' '.
REACTOR REC 1xCULATION PIPING
,a
- e TYPICAL LOOP to NG-B-24A g
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t k i #p 6
~
NG-B-1A NG-E-1A
[
7
-B-24 NG NG-C-23*
('
/
NG-A-25 l'
NG-B-2
/
NG-C-2 NG-A-24 NG-D-2
'/
NG-B-23 l
NG-E-2 NG-C-22*
NG-A-5 NG-E-24 NG-B-4 NG-1-4*
o NG-E-22 i
REC lRC. PuM P NG-A-6 NG-B-5 j
NG-C-4*
NG-A-18 NG-D-4 NG-E-6 N
V
)
NG-D-5 NG-C-93 NG-A-14*-
NG-B-12* -
NG-C-12* -
NG-D-ll* -
NG-E-13 Nuclear lH3 INSERVICE INSPECTION REACTOR RECIRCULATION SYSTEM U.T. (IGSCC). EXAMINATION
- Recordable Ultrasonic Indications ggy,gg,gg, gEV.
SMT.Nt SMETCH No.
TC989999 E
..