REGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR. 8603180223 DOC. DATE: 86/03/13 NOTARIZED: NO DOCKETFACIL: 50-387 susquehanna Steam Electric Station> Unit ii Pennsg lva 05000387

AUTH. NAME AUTHOR AFFILIATIONKEISER> H. W. Pennsylvania Power 5 Light Co.

REC IP. NAME REC IP.IENT AFFILIATIONADENSAMi E. BWR ProJect Directorate 3 gl

SUBJECT: Forwards inservice insp program relief request from AVMECodex'ection XI for fulfilling preservice insp requirementsfor certain longitudinal seam weld during inservice insp pr.

DISTRIBUTION CODE: AOATD COPIES RECEIVED: LTR I ENCL J SIZE:TITLE: OR Submittal: Inservi c e In spec tion/Testing

NOTES: 1 c g NMSS/FCAF/PM. LPDR 2c g s Trans cr i p t s. 05000387

RECIPIENTID CODE/NAME

BWR PD3 PD 01CAMPAGNONE

INTERNAL: ADM/LFMBNRR BWR ADTSNRR PWR-A *DTSNRR PWR-B *DTS

8~SR IBLE 04

COPIESLTTR ENCL

5 51 1

1 01 1

1 1

1 1

1 1

1 1

REC IP IENTID CODE/NAME

BWR EB

ELD/HDS4NRR BWR EBNRR PWR-A EBNRR PWR-B EBNRR/TAMBRQN1

COPIESLTTR ENCL

1 1

1 01 1

1 1

1

1 1

1 1

EXTERNAL: 24XNRC PDR 02

1

1 1

LPDRNSIC

0305

2 21 1

NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

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Pennsylvania Power 8 Light CompanyTwo North Ninth Street ~ Allentown, PA 18101 ~ 215 l 770.5151

Harold W. KeiserVice President-Nuclear Operations21 5/770-7502

NAR 13 1986

Director of Nuclear Reactor RegulationAttention: Ms. E. Adensam, Project DirectorBWR Project Directorate No. 3Division of BWR LicensingU.S. Nuclear Regulatory CommissionWashington, DC 20555

SUSQUEHANNA STEAM ELECTRIC STATIONINSERVICE INSPECTION PROGRAM RELIEF REQUESTER 100450 FILE 841-1PLA-2612

Docket No. 50-387

Dear Ms. Adensam:

Attached is a Inservice Inspection Program Relief Request from fulfillingthePreservice Inspection requirements for certain longitudinal seam weld duringthe Inservice Inspection Program.

If you have any questions, please call us.

Very truly yours,

Vice President — Nuclear Operations

cc: M. J. Campagnone USNRCR. H. Jacobs USNRC

J. R. Wiggins USNRC

8603180223 860313PDR ADOCK 05000387I8 PDRI !

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RELIEF RE UEST

I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE RE UIREMENTS

The Preservice Inspection Program for Susquehanna SES Unit 81 wasprepared/implemented/completed in accordance with ASME Section XI 1974Summer 1975 Adde'nda, "Rules for Inservice Inspection of Nuclear PowerPlant

Components.'-'ode

Category B-J, pressure-retaining welds in piping, required acomplete volumetric examination of 100% of the longitudinal seam welds inpiping.

Code Categories CF/CG, pressure-retaining welds in piping, pumps, andvalves in systems which do/do not circulate reactor coolant, required acomplete volumetric examination of 100%/50% of the longitudinal weldjoints in fittings.Contrary to the above, preservice examinations of certain longitudinalseam welds were inadvertently missed during the PSI; therefore, baselineultrasonic examination data is unavailable to support the ISI Program.

Relief is requested from fulfilling the reservice ins ectionrequirements for the subject components during the ISI ten year interval.Inspection of longitudinal welds will be performed in accordance with thecurrent routine Section XI program over the ISI ten-year interval, i.e.longitudinal welds will be examined concurrent with examination ofselected intersecting circumferential welds. Performance of the PSI oran increased ISI scope at this time poses an undue hardship with nocompensating increase in plant safety.

II. SCOPE

A total of forty-nine (49) longitudinal seam welds, distributed by Classamong the following systems, have no PSI data:

~tstetsNumber

of WeldsLineal Ftof Weld

Class 1 RHRRRCS

1428

3

133'5

7'I

Class 2

TOTAL 49 14'39'll

of the above welds are in stainless steel piping/fittings and are ofone (1) of the following material specifications:

1) SA358 TP304 CL1, "Electric-Fusion-Welded AusteniticChromium-Nickel Alloy Steel Pipe for High-Temperature Service."

2) SA312 TP304 Welded, "Seamless and Welded Austenitic StainlessSteel Pipe", and

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3) SA403 WP304W, "Wrought Austenitic Stainless Steel PipingFittings."

The forty-nine (49) longitudinal seam welds are identified as follows:

~set emWeld

Identification Descri tion

RHRClass 1

RHRClass 2

1)2)3)4)5)6)7)8)9)

10)11)12)13)14)

1)2)3)4)

DCA-111-1-1-HDCA-111-1-1-JDCA-111-1-1-KDCA-111-1-1-LDCA-111-1-2-BDCA-111-1-3-CDCA-111-1-4-GDCA-111-1-4-FDCA-111-1-5-CDCA-111-1-5-DDCA-111-2-1-CDCA-111-2-2-CDCA-111-2-3-BDCA-111-2-9-A

DBB-107-2-'1-EDBB-107-2-1-FHBB-ill-1-1-HHBB-ill-1-1-J

Pipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe Seam

'Elbow SeamElbov SeamElbow SeamElbow Seam

RRClass 1 2)

3)4)5)6) DCA-142-1-1-D7) DCA-142-1-3-E8)9)

10)11)12)13)14)15)16)17)18)19)20)21)22)23)24)

DCA-142-1-3-FVRR-B31-1-4-CVRR-B31-1-4-DVRR-B31-1-5-CVRR-B31-1-5-DVRR-B31-1-6-CVRR-B31-1-6-DVRR-B31-1-7-CVRR-B31-1-7-DVRR-B31-1-8-CVRR-B31-1-8-DVRR-B31-2-4-CVRR-B31-2-4-DVRR-B31-2-5-CVRR-B31-2-5-DVRR-B31-2-6-CVRR-B31-2-6-D

DCA-141-1-1-CDCA-141-1-1-DDCA-141-1-3-EDCA-141-1-3-FDCA-142-1-1-C

Pipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamPipe SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbow SeamElbov SeamElbow SeamElbov SeamElbow SeamElbow SeamElbow Seam

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~SstemWeld

Identification Descri tion

25) VRR-B31-2-7-C26) VRR-B31-2-7-D27) VRR-B31-2-8-C28) VRR-B31-2-8-D

Elbow SeamElbow SeamElbow SeamElbow Seam

CS

Class 1

1) DCA-107-1-1-E2) DCA-107-1-1-F3) DCA-107-1-1-G

Pipe SeamPipe SeamPipe Seam

III. BASIS FOR RELIEF

Performance of a preservice/augmented inservice inspection program on thesubject welds poses an undue hardship on PP&L with no negative impact onplant safety, or compensating increase in future plant safety.

A. Ins ection Hardshi

SSES Ul/1 is currently into the second refueling outage sincecommercial operation in June, 1983. Examination of the longitudinalwelds during this outage represents an undue hardship due to theexpected radiation exposures to perform these exams.

~Sstem

Man RemExposure

To Perform PSI,,'an RemExposure

2 3To Perform ISI

RHRRRCS

9.521.00.57

2.2 (22 fts)7.6 (25 ft.)0.9 (6 ft.)

TOTAL 31 10.7

1 PSI exposure is based on complete volumetric examination of 100% ofthe welds.2 ISI exposure is based on a volumetric/surface examination of allsubject welds:

a) ISI Classof twelveweld, or

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1-for at least one (1) pipe diameter up to a maximum(12) inches from the intersecting circumferential

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b)rISI Class 2 — for two and one-half (2.5) times the nominal wall

thickness (t) from the intersecting circumferential weld.3Exposures indicated are based on:

a) actual, recent SSES II1 H.P. surveys

b) NDE inspection time equal to 45 minutes per foot of weld foreach inspection technique. (i.e. U.T., P.T.)

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c) Field support resources (e.g. insulation removal, scaffoldingerection, etc.) estimated as six (6) times NDE inspection times.

In addition to the above overall hardship to SSES Util in personnelexposure, an additional hardship exists in that the inspectionpersonnel required to perform exams on stainless steel welds areIGSCC trained and qualified. Due to the rigorous training/testinginvolved in this qualification, a limited number of qualifiedinspection personnel are available at this time. Increasing theexposure histories of these personnel, to the point of possiblymaking them unavailable, would be an inefficient use of limitedresources and may impact other operating facilities.

B. Plant Safet Im act

Unavailability of preservice inspection data for the subject weldsposes no impact on the safe operation of SSES 81.

Construction Code NDE:

The subject piping was purchased from ITT Grinnell in accordancewith Bechtel Specification M-201, 'Technical Specification For

, Shop Fabricated Piping For Nuclear Service" and the followingASME Section II material specifications,'s required bysubsection NB of ASME Section III:a) SA-652, Specification For Special Requirements for Wrought

Steel Welding Fittings For Nuclear and Other SpecialApplications.

b) SA-655, Specification For Special Requirements For Pipe andTubing For Nuclear and Special Applications.

These specifications required the following NDE of shopfabricated piping:

a) Nuclear Class 1 longitudinal and girth welds inwelded-with-filler-metal tubular products and fittings were100% radiographed and accessible surfaces of welds and heataffected zones in base materials were examined by magneticparticle or liquid penetrant methods. Also, ultrasonicexamination was required, either prior to forming orfollowing heat treatment.

b) Nuclear Class 2 longitudinal and girth welds inwelded-with-filler-metal tubular products and fittingsreceived 100% radiography.

All Construction Code NDE was satisfactorily performed prior toplant start-up; therefore, the preservice piping pressureboundary integrity was verified prior to service. In addition,the subject piping systems were also hydrotested.

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2. Materials:

The stainless steel materials involved are not susceptible tocracking due to IGSCC:

1) Materials in the subject rolled and welded piping are 0.030max. carbon and the long seams are in the solution annealedcondition, and, therefore; are conforming to NUREG 0313.

2) The fittings contain long seams also in the solutionannealed condition and, therefore, are conforming toNUREG 0313.

3. Piping Pressure Stresses:

Based on a review of the piping design for the affected piping,the actual piping wall. Thicknesses have, as a minimum, amargin of thirty-two (32) percent over the required wallthicknesses as dictated by ASME Class 1 straight pipe pressuredesign requirements based on code allowable stresses.

Historically, no problems have been reported on stainless steelwelded piping/fittings. Recently, ten (10) utilities werepolled and all reported no problems with stainless steel weldedpipe ~

IV. ALTERNATE PROVISIONS

A. ISI Re uirements

Inspection of the subject longitudinal welds will be performed inaccordance with the current routine Section XI program over the ISI10 year interval, i.e., longitudinal welds will be examinedconcurrent with the examination of selected intersectingcircumferential welds. This program provides adequate sampling, on asystem basis, of weld integrity, as illustrated below:

~Sssem

Total No. ofLongitudinal Welds

Per S stem

No. of WeldsRequiring

ISI% ofTotal

RHRRRCS

5871

3

1842

1

315933

TOTAL 132 61 46

Weld sampling on a syst: em basis exceeds the 25% sample prescribed forClass 1 circumferential welds.

In addition, due to the recent advances in ultrasonic techniques toimprove detection of IGSCC, ISI examinations will provide better,more reliable data than that previously obtained during PSI. Sincethe recording levels and sensitivi'ty levels utilized during PSI wereless conservative than that currently prescribed, use of the baselinedata to resolve ISI indications is limited.

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Bi Construction NDE

ASME Section XI (74575) IWB-2100(b) allows the use of shop and fieldexaminations in lieu of on-site preservice examinations provided suchexaminations are conducted utilizing techniques equivalent to thoseemployed for subsequent inservice examinations. Since the currentISI Program for SSES $/1 requires only portions of the longitudinalweld be examined, (i.e. a pipe-diameter up to twelve inches or 2.5t),shop radiography satisfies the volumetric examination requirementsfor balance of the weld not subject to ISI.

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''DISTRIBUTION w/o enc1osure<Occket Fi1eg

Bl<R¹3- r/f--EHy1ton (2)MCampagnone

DOCKET NO(Si. 50-387/388Nr. Harold l<. KeiserYice PresidentNuc1ear OperationsPennsylvania Power IIt Light Company2 North Ninth StreetA11entown, Pennsy1vania 18101SUBJECT:

SUSQUEHANNA, UNITS 1 AND 2

The following documents concerning our review of the subject facility are transmitted for your information.

CI Notice of Receipt of Application, dated

D Draft/Final Environmental Statment, dated

C3 Notice of Availabilityof Draft/Final Environmental Statement, dated

C3 Safety Evaluation Report, or Supplement No. , dated

D Notice of Hearing on Application for Construction Permit, dated

C3 Notice of Consideration of Issuance of Facility Operating License, dated

Q Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant HazardsConsiderations, dated ary 26, 1986.

D Application and Safety Analysis Report, Volume

C3 Amendment No. to Application/SAR dated

C3 Construction Permit No. CPPR-

D Facility Operating License No.

, Amendment No.

, Amendment No.

dated

, dated

C3 Order Extending Construction Completion Date, dated

C3 Other fSpecify)

Enclosures:As stated

Office of Nuclear Reactor Regulation

cc: See next page

OFriCe~

SURNAME+

DATE+ 3/gi /86

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NRC FORM 318 t1/84) NRCM 0240

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