ML20064D127

Responds to Items 1 & 4 of IE Bulletin 82-03 Re Stress Corrosion Cracking in Austenitic Stainless Steel Recirculation Sys Piping.Total of 51 Circumferential & Branch Connection Welds & 6 Longitudinal Welds Examined

ML20064D127
Person / Time
Site:	Hatch
Issue date:	12/15/1982
From:	Beckham J GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-82-03, IEB-82-3, TAC-49156, NUDOCS 8301040568
Download: ML20064D127 (17)

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• Georgia Power Cornpany 8 333 Piedmont Awenue At:anta. Geo gia 30308 Telephone 404 526-7020 , ,

MaMng Address ' '

Post Off.ce Box 4545 Attanta. Georg.a 30302 December 15,1.9pgen;7 p,, rgia power J. T. Beckham, Jr. tnd southem electnc system Vee Presrcent and General Vanager Nuclear Generat.on U. S. Nuclear Regulatory Comission

REFERENCE:

Office of Inspection and Enforcement RII: JP0 Region II - Suite 2900 50-321 101 Marietta Street, NW I&E Bulletin Atlanta, Georgia 30303 82-03 ATTENTION: Mr. James P. O'Reilly GENTLEMEN:

Georgia Power Company (GPC) hereby submits the following infonnation concerning inservice inspection activities at Plant Hatch Unit 1 in response to Items 1 and 4 of NRC I&E Bulletin 82-03. The subject bulletin pertains to stress corrosion cracking in austenitic stainless steel Recirculation System piping. A response to Items 2 and 3 of the bulletin will be submitted pursuant to bulletin requirements prior to resuming power operation af ter completion of the maintenance / refueling outage currently in ,

progress.

Response to Item 1 Please refer to the response to Item 4d for discussion on the qualification of ultrasonic test procedures employed during inservice inspection activities at Plant Hatch Unit 1.

l Response to Item 4a (1)

A total of fifty-one (51) circumferential and branch connection welds and six (6) longitudinal welds were examined ultrasonically during the 1982 inservice inspection. Please refer to Attachment 1 for isometric drawings of the Recirculation System piping. Welds which have been examined during the 1982 inservice inspection are denoted by circled weld numbers.

Response to Item 4a (2)

Please refer to Attachment 2 for criteria identification for weld sample selection. Discussed are the original scope of examinations, additional code-required examinations resulting from reportable indications observed in the original scope of examinations, and additional i

examinations in excess of code requirements performed by GPC.

8301040568 821215 DR ADOCK 05000321 PDR bf

Georgia Power d U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement December 15, 1982 Page Two Response to Item 4a (3)

The following piping materials are used in the Recirculation System at Plant Hatch Unit 1:

12" Recirculation - Type 304 austenitic stainless steel, welded pipe (with filler metal) per ASTM A-358 Class 1 with ASTM A-240 base material; .568 inch min. wall (based on nominal 0.D.).  :

22" Recirculation - Type 304 austenitic stainless steel welded pipe (with filler metal) per ASTM A-358 Class 1 with ASTM A-240 base material; .975 inch min. wall.

28" Recirculation - Suction side: Type 304 austenitic stainless steel welded pipe (with filler metal) per ASTM A-358 Class 1 with ASTM A-240 base material; 1.088 inch min, wall.

Discharge side: Type 304 austenitic stainless steel welded pipe (with filler metal) per ASTM A-358 Class 1 with ASTM A-240 base material; 1.263 inch min. wall.

Note: Four inch (4") Recirculation not addressed since piping removed during 1977 maintenance / refueling outage and capped.

Response to Item 4a (4)

Approximately thirty (30) man-rem were incurred in the perfonnance of f the inservice inspection. The exposure incurred does not include l radiation exposure resulting from insulation removal and opening of sacrificial shield doors.

Response to Item 4b l

The following is a summary description of procedures and techniques used during ultrasonic examination of austentic stainless steel piping at the Plant Hatch Unit 1.

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j Georgia Power A 4

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement December 15, 1982

Page Three

, Response to Item 4b (Continued)

! A. Procedures

1. Southern Company Services (SCS) UT-H-400

2. Southwest Research Institute (SwRI) 600-3/59

3. Southwest Research Institute (SwRI) 700-5/8 l These procedures require a 3/8" diameter, 1.5 MHz 450 angle beam i transducer to be used during the ultrasonic examination of l austentic piping.

B. Calibration Standards i

Stainless steel curved calibration blocks incorporating 1/8" i diameter side drilled holes at 1/4T, 1/2T, and 3/4T depths were utilized.

C. Scanning Sensitivity For manual UT examinations, scanning was performed at 14 dB above

the Primary Reference Level. However, upon concurrence of an NDE Level III, this level could be reduced if baseline screen noise hindered the interpretation of the ultrasonic scope C RT. This scanning level was always at least 6 dB above the Primary Reference

. Level. For mechanized examinations, scanning was performed at 6 dB above the Primary Reference Level.

D. Recording Criteria All indications which produced a response greater than 20% of the Distance Amplitude Curve (Primary Reference Level) which were not i

determined to be caused by outside diameter geometry were recorded. In addition, the examiners were instructed that any

indication interpreted to be significant should be recorded.

Response to Item 4c Examinations conducted since 1977 in the Recirculation System have been performed using 1.5 MHz transducers. Reportable indications were 1

identified using such equipment on the 4" RWCU Return piping during the 1981 inservice inspection at Plant Hatch Unit 1. The subject piping is 1 scheduled for replacement during the maintenance / refueling outage j currently in progress pursuant to a commitment made to NRC. No other 1 reportable indications due to intergranular stress corrosion cracking

! (IGSCC) have been observed using 1.5 MHz transducers at Plant Hatch Unit 1.

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Georgia Power b U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement December 15, 1982 Page Four Response to Item 4d In cooperation with Electric Power Research Institute (EPRI) and Battelle Laboratories, an evaluation of the crack detection capabilities of ultrasonic procedures and techniques was developed at the Battelle-Columbus Laboratories in Columbus, Ohio. Portions of five 28" stainless steel recirculation system piping welds which contained liquid penetrant-identified IGSCC indications from the Nine Mile Point Nuclear Plant were prepared for ultrasonic examination. SCS and SwRI examined the 5 specimens using procedures and techniques mentioned in the response to Item 4b (excluding the mechanized procedure) and demonstrated to the satisfaction of NRC Inspectors, Mr. Bill Crowley and Mr. James Coley, the ability to adequately detect and evaluate IGSCC.

These specimens and the UT procedures and techniques were representative i of examinations that were performed at the Plant Hatch Unit 1. However, the SwRI remotely operated mechanized ultrasonic equipment procedures and techniques were not demonstrated at Battelle Laboratories. Upon review of the SwRI procedures and techniques, the ultrasonic examinations conducted with the remotely operated mechanized equipment were determined to be adequate in the detection of IGSCC.

Enclosed as Attachment 3 is a summary of reportable indications observed during the inservice inspection just completed on Plant Hatch Unit 1.

Should you have any questions in this regard, please contact this office.

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company i

and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY

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/ J. T. Beckham, Jr'.

Sworn to and subscribed before me this 15th day of December, 1982

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,/ ' g,hotarpPublic JAE/mb Enclosure

! xc: H. C. Nix, Jr.

Senior Resident Inspector USNRC, Document Control Desk (Washington) wm

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• 12 AR-F-3 1.534 .075 l 12 AR-H-4 1.382 .075 l 12 AR-J-2 1.476 .075 12 BR-A-2 1.409 .075 12 BR-C-4 1.346 .075 12 BR-E-3 1.566 .075 22 AM-1BC-2 1.025 .060 22 AM-2 0.921 .056 ,

22 AM-3 1.041 .059 22 AM-3BC-1 1.041 .060 22 AM-3BC-2 1.063 .060 22 BM-1BC-1 0.99 .060 22 BM-1BC-2 0.988 .060 22 BM-2 1.037 .059 22 BM-3BC-2 1.016 .060 28 B-3 1.484 .059 28 B-7 1.415 .059 28 B-10 1.524 .069 28 B-15 1.496 .059

• Note: % Carbon Content unavailable at time of second sample determination; provided later by GE.

e ADDITIONAL EXAMINATIONS PERFORMED FOR GPC Eleven additional examinations were performed and were chosen on the basis of revised high SRI and carbon content. The following circumferential welds were examined: Weld # SRI #  % Carbon Content

• 12 AR-G-2 1.474 .075 12 AR-G-3 1.557 .075 12 AR-H-2 1.537 .075 12 AR-H-3 1.519 .075 12 AR-J-3 1.473 .075 12 BR-A-3 1.508 .075 12 BR-A-4 1.255 .075 12 BR-B-2 1.441 .075 12 BR-B-3 1.447 .075 12 BR-C-2 1.527 .075 12 BR-D-3 1.577 .047

i ATTACHMENT 3

SUMMARY

OF REPORTABLE INDICATIONS

The following is a summary of reportable indications found during the inservice inspection just completed on Plant Hatch Unit 1:

Weld No. IB31-lRC-22AM-1 Pipe to Cap Reference Location: 00 is top dead center of manifold looking toward cap.

Indications: Thirty-one 1/4" to 3/8" long axial indications on cap, 55-100% DAC, located uniformly around cap with a cluster at the bottom of the cap. Maximum depth is 63% through wall located 49" CW from 00 Weld No. IB31-1RC-22AM-1BC-1 Branch Connection Reference Location: 00 is at the top dead center of the manifold on the upstream side (toward cross). Clockwise is measured from 00 looking up the riser (900 is toward the reactor).

Indications: Seven 1/4" to 1/2" long indications on the weldolet oriented perpendicular to the weld, 20-50% DAC. Five are located from 63" to 77" CW from 00 and have no appreciable depth.

Two are located at approximately 200 CW from 00 with one having a maximum depth of 12% and the other having no appreciable depth.

Weld No. IB31-lRC-22AM-4 Pipe to Cap Reference Location: 00 is top dead center of manifold looking toward cap.

Indications: Thirty-two 1/4" to 1/2" long axial indications on cap ,

30-140% DAC, located uniformly around cap with clusters at top and bottom of cap. Maximum depth is 72% through wall located 56" CW from 00 Note: Weld IB31-lRC-22AM-4 added after reportable indications observed l in pipe to cap welds in original scope of examinations.

j Weld No. 1831-lRC-22BM-1 j Pipe to Cap l

Reference Location: Oo is top dead center of manifold looking toward cap.

Indications: Five 1/4" long axial indications on cap, 40-105% DAC. Two are located approximately 23" CW from 00 and three 60" CW f rom 00 (near top of cap). Maximum depth is 64% through wall located in the cluster of three near the top of the cap.

Note: Weld IB31-lRC-228M-1 added af ter reportable indications observed in pipe to cap welds in original scope of examinations.

Weld No.1831-lRC-22BM-4 Pipe to Cap Reference Location: 0o is top dead center of manifold looking tow 6rd cap.

Indications: Seventeen 1/4" to 1/2" long axial indications on cap, 30-130% DAC. Twelve of the seventeen indications are clustered near bottom of cap. The others are randomly distributed around the circumference of the weld. Maximum depth is 67% through wall located 66 1/2" CW from Oo in a cluster at the top.

Weld No. lEll-1RHR-208-D-3 Elbow to Pipe Reference Location: Looking toward pipe side with 00 on outside of elbow.

Indications: One 1/4" long axial indication on pipe side, 170% DAC, located 23" CW from 00, 94% through wall depth.

Four 1/4" to 3/8" long axial indications on pipe size, 40-140% DAC, located 34" to 37" CW from 00, depth less than above.

One 1 1/2" long circumferential indication on pipe size, 200% DAC, located 27" CW from 00, less than 10% through wall depth.

One 1 1/2" long circumferential indication on elbow side, 100% DAC, located 47" CW from 00, 33% through wall depth.

Weld No. lEll-lRHR-24B-R-13 Pipe to Pipe Reference Location: Oo is at the top dead center of the pipe looking toward the reactor recirculation system.

Indications: Six 1/4" to 3/8" long axial indications located on the upstream side of the weld. Three indications are located approximately 1" to 3" CW from 00 (top of pipe) and three indications are located approximately 14" to 17" CW from 0o. The maximum through wall depth is 47% for an indication located at the top of the pipe (5" CW on I.D.

surface).

Weld No. 1B31 -l RC-28A-14 was ultrasonically examined by SwRI and preliminary evaluations revealed the possibility of a 5 1/2" linear indication. This was reported to GPC by SwRI on a Customer Notification Form. However, extensive investigation, which included a complete reexamination by another inspection contractor (also NDE Level III review),

review of the construction (preservice) radiographs, and a reexamination and evaluation by another SwRI NDE Level III, concluded this indication to be inside surface geometry, i.e., counterbore. In addition, a SCS NDE Level III representating GPC reviewed the radiographs and ultrasonic data and concurred with the investigation and the weld was accapted for service.

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