ML20083M966

Forwards Info Re Analyses & Repairs of Recirculation & RHR Sys Piping Welds.Details of Inservice Insp Discussed.Util Intends to Return Unit to Power Operation Upon Completion of Current Outage.Meeting Scheduled for 830201 to Discuss Subj

ML20083M966
Person / Time
Site:	Hatch
Issue date:	01/27/1983
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20083M970	List: ML20083M966 ML20083N032 ML20083N079
References
REF-SSINS-6820, RTR-NUREG-0313, RTR-NUREG-313 IEB-82-03, IEB-82-3, NED-83-062, NED-83-62, TAC-49156, NUDOCS 8302010512
Download: ML20083M966 (4)

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January 27, 1983 Director of Nuclear Reactor Regulatiori Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Ccmission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATItG LICENSE DPR-57 EDNIN I. HA'ICH NUCLEAR PIANT UNIT 1 ANALYSES AND REPAIRS OF RECIRCULATION AND RHR SYSIDI WELDS Gentlenen:

During the inservice inspection conducted during the Plant Hatch Unit 1 1982 maintenance / refueling outage, several unacceptable ultrasonic indications were observed in Recirculation (Recirc) and Residual Heat Renoval (RHR) Systen piping welds. Georgia Power Canpany (GPC) hereby subnits the following infonnation concerning the inservice inspection, analyses and repairs, future inspections, and modification /replacanent plans.

INSERVICE INSPECTION SCOPE OF EXN4INATIONS

7 By letter dated Decenber 15, 1982, GPC provided NRC Region II with a J

p i listing of exaninations that were perfonned during the recent inservice inspection at Plant Hatch Unit 1. The listing was provided as part of g

the response to NRC I&E Bulletin 82-03, " Stress Corrosion Cracking In i

,sT d f,c , Thick-Wall, Large-Dianeter, Stainless Steel, Recirculation Systen Piping

, O tr - At BWR Plants", issued by NRC on October 14, 1982. A copy of the GPC letter is enclosed herein as Attachnent 1 to this subnittal. Please refer to the response to Iten 4a(1) and Attachnent 1 of the subject GPC letter for a discussion on the welds exanined and their location in the Recirc Systen.

The exanination sanpling basis is discussed in our response to Iten 4a(2) and Attachnent 2 of the Decenber 15, 1982 letter to NRC Region II.

In addition, pursuant to the re:Juirenents of NBC NUREG-0313, Rev.1, RHR welch were also exanined. Enclosed as Attachnents 2, 3, and 4 to this subnittal are inservice inspection isonetric drawings of the 20" and 24" dianeter RHR piping exanined chring the recent inservice inspection.

Circunferential welds exanined are denoted by encircled weld numbers.

8302010512 830127 PDR ADOCK 05000321 0 PDR

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Georgia Poner d Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Oparating Reactors Branch No. 4 January 27, 1983 Page Two RESULTS NBC Region II was provided a listing of results of piping inspections in the GPC letter dated December 15, 1982. Please refer to Attachments 2 ard 3 of that letter for a listing of the Recirc welds examined and the results thereof. The listing of reportable indications (Attachment 3 to the December 15, 1982 letter) includes those RHR welds having reportable indications.

EXAMINATION METHODS Please refer to the responses to Items 4b and 4d of (Attachment 1 to this submittal) NBC I&E Bulletin 82-03 in the GPC letter dated December 15, 1982, for a suarnary description of the Ur procedures and calibration standards used in the examination of the subject piping.

Pursuant to the requirements of I&E Bulletin 82-03, the ultrasonic test procedures used by each of the examination agencies involved with the inservice inspection were successfully qualified on cracked pipe samples at Battelle-Columbus. A discussion on procedure qualifications is discussed in the response to Item 4d of the subject bulletin.

ANALYSES AND REPAIRS By letter dated January 26, 1983, GPC provided NRC Region II with the listing of welds requiring analysis and repair. That submittal was made to provide a response to Items 2 and 3 of I&E Bulletin 82-03, thus cmpleting the reporting requirements for that bulletin. A copy of that GIC letter is enclosed herein as Attachment 5 to this subnittal.

Analyses performed by NUrIDI have demonstrated the need to repair six welds at this time in the form of a weld overlay. The welds requiring repair are as follows:

System Weld No.

Recirculation 1B31-lIC-22AM-1 Recirculation 1B31-lRC-22AM-4 Recirculation 1B31-1BC-22BM-1 Recirculation 1B31-lRC-22BM-4 j RHR lEll-lRHR-20B-D-3 RHR lEll-lRHP,-24B-R-13 70077S t

f Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operatirg Reactors Branch No. 4 January 27, 1983 Page Three Al% LYSES AND REPAIRS (Continued)

In addition, the indications on Recirc Systen weld 1B31-lRC-22AM-1BC-1 were analyzed and were determined not to require repairs at this time.

A leakage detection systen for that particular weld is being considered.

As stated in our January 26, 1983 letter, GPC will subnit to NBC NRR details of the analyses and repairs. Enclosed for your review as Attachnent 6 to this subnittal is the NUfEDI design report for the Recirc and RHR Systen weld overlay repairs and flaw evaluations.

EUIURE INSPECTIONS The following welds discussed in the section above will be exanined during the next three successive schechled refueling outages:

Systen Weld No.

Recirculation 1B31-1BC-22AM-1 Recirculation 1B31-lRC-22AM-1BC-1 Recirculation IB31-lRC-22AM-4 Recirculation 1931-1RC-221N-1 Recirculation 1B31-1BC-22BM-4 RHR lEll-lRHR-20B-D l RHR lEll-lRHR-24B-R-13 In the event that no unacceptable indications are observed, 'the exauination frequency will be extended to three thirty-six month + 12 l In addition, if no unacceptable indications- are

month exaninations.

observed after the aforenentioned exanination frsluencies, the affected welds will be exanined once per eighty months. Future exanination frsluency is contingent upon the design life of the affected welds (Please refer to Section 1.0 of the attached NUfECH design report) .

In addition, fifty percent (50%) of the Recirc manifold sweepolet welds (includes weld 1B31-lRC-22AM-1BC-1) will be exanined in a similar manner as discussed above.

All other stainless steel welds will be exanined in accordance with the guidance of NUREG-0313, Rev.1 as stated in our letter to NBC dated June 29, 1981. For your convenience, a copy of that letter is enclosed herein as Attachnent 7 to this subnittal.

700775

Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 January 27, 1983 Page Four MWIFICATIONS/REPIACEMEffrS Modifications ancyor replacanents are under consideration. There are, however, no firm plans at this time. Because nonconfonning material (as I

defined in NUREG-0313, Rev. 1) is utilized at Plant Hatch Unit 1, GPC has ccmnitted to NRC by letter dated June 29, 1981 (please see Attachnent 7 to this subnittet), to perform augmented inservice inspection in accordance with the guidance of NURBG-0313, Rev. 1. In addition, it was further ccmnitted that in the event that replacanent of nonconforming material is required, at such time the affected component will be replaced with conforming material and processed in accordance with Section III of NUREG-0313, Rev.1.

Asstuning acceptable results fran the nondestructive exaninations and I

hydrostatic test, it is our intention to return Plant Hatch Unit 1 to power operation upon the canpletion of the current outage. We believe that the results of the inspection and the repair progran provide an adequate basis ~

for safe operation of the unit.

During a telephone conversation on January 24, 1983, with Messrs.

G. Rivenbark (NRR Hatch Project Manager) and W. Hazelton (NRR-MPEB), a meeting was schechled by GPC tentatively for February 1,1983, at 10:00 a.m.

in Bethesda for a presentation of the information contained herein to_ the appropriate NRC staff personnel. Assisting in the GPC presentation to the staff will be NUPECH and Southern Canpany Services personnel, as appropriate.

Pursuant to the request of Mr. J. Blake of NBC Region II, a copy of this

~

subnittal will be provided concurrently to the NBC regional office so they may assist in the review of the analyses and repairs at Plant Hatch Unit 1.

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

Sincerely yours,

} f~ 4_m l L. T. Gucwa-Chief Nuclear Engineer JAE/mb Attachnents xc: J. T. Beckhan, Jr. .

l H. C. Nix, Jr.

J. P. O'Reilly (NBC- Region II) l Senior Resident Inspector l

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, twoncre 404 5N te2C ATTACHMENT 1 Ma ing Ana:. n Post O*cc Bos 4545 Atia*.ta Georg a J0302 December 15, 1982 Georgia Power J. T. Deckham, Jr.

Ven Pre".: cent anc G.wral ihnager f.T mutten t=actnc svstem fJuc; ear Genera!en U. S. Nuclear ReguTatory Commission

REFERENCE:

Office of Inspection and Enforcement RII: JP0 Region II - Suite 2900 101 Marietta Street, NW 50-321 Atlanta, G2orgia 30303 I&E Bulletin 82-03 ATTENTION: Mr. James P. O'Reilly GENTLEMEN:

Georgia Power Company (GPC) hereby submits the following infomation 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 Syst corrosion cracking in austenitic stainless steel Recirculation m piping.

submitted A response to Items 2 and 3 of the bulletin will be pursuant to bulletin requirements prior to resuming power operation after completion of the maintenance / refueling outage currently in ,

progress.

Response to Item 1 l

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.

Response to Item 4a (1)

A total of fifty-one (51) circumferential and branch connection welds and 1982six (6) longitudinal inservice welds were examined ultrasonically during the inspection.

drawings of the Recirculation Please Systemrefer to Attachment 1 for isometric piping. Welds which have been examined weld numbers.

during the 1982 inservice inspection are denoted by circled

_ Response to Item 4a (2)

Please selecticn. refer to Attachment 2 for criteria identification for weld sample code-requiredDiscussed are the original scope of exaninations, additional examinations resulting from reportable observed in the original scope of examinations, indications and additional examinations in excess of code requirements perfomed by GPC.

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A Georgia Power m.:a U. S. Nuclear Regulatory Comission Office of Inspection ar.d Enforcement December 15, 1982 Page Two Response to Itsn 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 I with ASTM A-240 base material; .568 inch min. wall (based oa 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 204 austenitic stainless steel welded pipe (wti.h 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 i during 1977 maintenance / refueling outage and capped.

Response to Item 4a (4)

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

Response to Item 4b 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.

NOT75

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Georgia Powerkn U. S. Nuclear Regulatory Comission Office of Inspection and Enforcement December 15, 1932 Page Three Response to Item 4h (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 These procedures require a 3/8" diameter, 1.5 MHz 450 angle beam transducer to be used during the ultrasonic examination of j austentic piping.

B. Calibration Standards Stainless steel curved calibration blocks incorporating' 1/8"

, diameter side drilled holes at 1/4T, 1/2T, and 3/4T depths were l utilized.

l 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 CRT. 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.

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

l Response to Item 4c l

l Examinations conducted since 1977 in the Recirculation System have been performed using 1.5 MHz transducers. Reportable indications were l

identified using such equipment on the 4" RWCU Return piping during the 1981 Inservice inspection at Plant Hatch Unit 1. The subject piping is scheduled for replacement during the maintenance / refueling outage currently in progress pursuant to a comitment made to NRC. No other 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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GeorgiaPbwer d U. S. Nuclear Regulatory Comission Office of Inspection and Enforcement Decembe, 15, 1982

, Page Four l

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 IG5CC indications from the Nine Mile Point flucicar Plant were prepared for ultrasonic examination. SCS and SwRI enmined l the 5 specimens using and techniques mentioned in the i response to Item 4b p(rocedures 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 dperated mechanized equipment were determined to be adequate in the detection of IGSCC.

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

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

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company 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 b ore me this 15th day of December,1982 l W -

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VfJ g1totag Public JAE/mb Enclosure l

l xc: H. C. Nix, Jr.

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

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l e ORIGINAL SCOPE OF EXAMINATIONS Welds from the Recirc System were picked on the basis of ASME Section XI Code, NUREG-0313, Rev. 1 guidance (high stress welds with Sm 2 2.4), and comitments to NRC resulting from the Spring 1982 chloride intrusion. A total of nineteen circumferential welds were examined in the 4",12", 22" and 28" Recirc System piping. In addition, six longitudinal welds were examined. The following welds were ex4 mined:

Weld #

Circumferential and Branch Connections 4A-1A 4A-10A 48-1A 4B-10A 12 AR-K-1 12 AR-G-4 12 AR-G-5 ~

12 BR-B-1 12 BR-D-4 12 BR-D-5 22 AM-1 22 AM-1BC-1 -

22 BM-3

. 22 BM-3BC-1 22 BM-4 28 A-1 P 28 A-2 28 A-14 28 A-15 Longitudinal 12 AR-G-4LU 12 BR-D-4LU 22 SM-3LD 28 A-2LD 28 A-14LU-0 28 A-14LU-I e ADDITIONAL CODE REQUIRED EXAMINATIONS "s a result of reportable indications observed in the original

- ope of examinations for Recirc, nineteen additional examinations otre perfonned. Welds were chosen on the basis of high preliminary stress rule index (SRI) numbers provided by GE. The following circumferential welds were examined:

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,- Weld # SRI #  % Carbon Content *

'! 12 AR-F-3 1.534 .075 12 AR-H-4 1.382 .075 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 0.92i .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 'l.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. -

s ADDITIONAL EXAMINATIONS PERFORMED FOR GPC Eleven additional examinations were pdrformed and were chosen on the basis of revised high SRI and carbon content. The following circumferential welds were examined:

Weld # SRI i  % 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 .073 12 BR-B-2 1.441 .075 l 12 BR-B-3 1.447 .075 1

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ATTACHMENT 3

SUMMARY

OF REPORTAB!.E INDICMIONS I

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

Weld No. 1831 1RC-22AM-1 Pipe to Cap g Referec.::e 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 unifonnly 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-lRC-22AM-1BC-1 Branch Connection Reference Location: 00 is at the top dead center of the manifold on the i

upstream side (toward cross). Clockwise is measured from Oo looking up the riser (90o 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 ere located from 63" to 77" CW frem 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 conter of manifold looking toward cap.

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

30-140% DAC, located unifonnly around cap with clusters at top and bottom of rap. Maximum depth is 72% through wall located 56" CW from 00 Note: Weld 1831-lRC-22AM-4 added after reportable indications observed in pipe to cap welds in original scope of examinations.

Weld No.1831-1RC-?T.BM-1 Pipe to Cap Reference Location: 00 is top dead center of manifold looking toward cap.

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

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

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t Weld No. 1831-lRC-22BM-4 Pipe to Cap Reference Location: Oo is top dead center of manifold looking toward 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 j cluster at the top.

Weld No. lEll-lRHR-20B-D-3 Elbow to Pipe Reference Location: Looking toward pipe side with Oo 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 0o, depth less than above. .

One 1 1/2" long circumferential indication on pipe size, 200% DAC, lo::ated 27" CW from 0o, 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-1RHR-248-R-13 Pipe to Pipe Reference Location: Oo is at the top dead center of the pipe looking toward the reactor recirculatica system.

Indications: Six 1/4" to 3/8" long axial indications located on the upstream side of the weld. Three . indications are located approximat aly 1" to 3" CW from Oo (top of pipe) and three indications are located approximately 14" to 17" CW from Oo. 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. 1B31-1RC-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 extensive investigation, which included a complete Fonn. However, 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 PC reviewed the radiographs and ultrasonic data and concurred with the investigation and the weld was accepted for service.

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