ML17277B740

Forwards Request for Relief for Exams Found Impractical During Preservice Insp Program.Written Response Granting Relief from ASME Section XI Requirements Requested

ML17277B740
Person / Time
Site:	Columbia
Issue date:	05/17/1985
From:	SORENSEN G C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	BUTLER W R Office of Nuclear Reactor Regulation
References
GO2-85-255, TAC-57728, NUDOCS 8505220008
Download: ML17277B740 (24)

Text

REGULATORY I<ORMATION DISTRIBUTION"SYST M (RIDS)O'CCES$ION NBR:8505220008 6C CHOATE: 85/05/17 NOTARIZ: NO DOCKET'FACIL:50 397 NPPSS Nuclear Projectp Unit 2r Nashington Public Powe 05000397 AUTH INANE AUTHOR-AFFILIATION

~~~SORENSEN<G+C, Hashington Public Power Supply System RECIP~NAMK>>RECIPIENT AFFILIATION BUTLKRrN~RE Licensing Branch 2 I

SUBJECT:

Forwards request for relief for>>exams found impractical during pr eservice insp program,l'written.response granting.relief from ASME Section XI requirement requested; DISTRIBUTION,CODE.:

A047O COPIES RECEIVED!LTR ENCL.SIZEi TITLE;OR Submittal:

Inser vice Inspection/Testing NOTES: OL;12/20/83 05000397 REC IP IENT ID CODE/NAME NRR LB2 BC 01 INTKRNAL;ACRS 16 ELO/HDS2 NRR/DE MTFB 0Q COPIES LTTR ENCL 7 7 10 10 1 0 1 RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MEB 15 NRR/DL/TAPMG RGN5 COPIES LTTR ENCL 0 1 1 EXTERNAL'POR NSIC 03 05>>1-1 1 NRC PDR 02 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

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Mr.W.R.Butler, Chief Licensing Branch No.2 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Butler:

Washington Public Power Supply System 30006eorge Washington Way P.O.Box968 Richland, Washington 99352-0968 (509)372-5000 Docket No.50-397

Reference:

NUCLEAR PLANT NO.2 CPPR-93 PRESERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF Letter G02-85-110, G.C.Sorensen (SS)to A.Schwencer (NRC),"CPPR-93 Preservice Inspection Program Plan, Amendment No.4, Su+nary Report Supplement No.1, NIS-1 Code Data Report," dated February 28, 1985.Technical Specification

4.0.5 requires

the Supply System to comply with ASME Section XI requirements unless specific written relief has'been granted by the NRC.The WNP-2 Preservice Inspection (PSI)Summary Report, Supplement 1, was submitted to the NRC via the reference.

This supplement contained four requests for relief for examinations the Supply System found impractical during PSI.This letter re-submits those requests for relief (attached) and requests that the NRC staff review and provide a written response granting the requested relief from the Code requirements.

In accordance with 10CFR170.12(f), an application fee of$150.00 is provided.Very truly yours, G.C.Sorensen, Manager Regulatory Programs DPR/kr Attachments:

As stated cc: J.O.Bradfute, NRC W.S.Chin, BPA (399)M.R.Humm, NRC J.B.Martin,-NRC E.Revell, BPA (399)N.S.Reynolds, BLCP&R A.D.Toth, NRC (901A),)p 04'ge

abl 88~Al ternati ve Examinations Impact on Plant guality and Safety The welds in this request for relief are partially or totally inaccessible to all examination methods.I There will be no adverse impact on plant quality and safety by doing only a partial code examination of these welds.1.The Class 1 piping welds have passed radiographic and dye penetrant examinations in accordance with Section III.S-A.3 1 RE(VEST FOR RELIEF NO.PSI-2>>001 (SUPPLEMENT) 2.All of the identified welds will be subject to a system pressure test in accordance with Section XI Class 1 requirements. 3.Leak detection systems identify significant leakage in the areas of the subject piping welds.Appropriate oper-ator action would occur due to leak detection system alarms.4.Alternate systems can bring the reactor to a safe shutdown.5.Other similar welds in the vessel or same, piping run will receive full code examinations. The integrity of the pressure boundary can thus be verified by sampling.8-A.4 9 Q~CATEGORY 8-J DATA SECTION ISO.NO.WELD NUMBER SHEET NO.XI EXAM RRC-104 2RRC(51)-1 XXX-XXX PT DESCRIPTION Nozzle to Forging SECTION III EXAM REMARKS Inaccessible due to CRD housings.'hese welds are located at the centerline of the RPV and they are completely surrounded by.the control rod drive mechanisms. RRC-104 2RRC(51)-2 XXX-XXX PT'Forging to Piping Inaccessible due to CRD housings.-These welds are located at the centerline of the RPV and they are completely surrounded by the control rod drive mechanisms. 0 II) Component or System Code Number of Welds REQUEST FOR RELIEF NO.PSI-2-002 Component support attachment welds.List attached.~Cate ory All of the subject welds weve designed and fabricated to ASME Section III Class 2.The Presevvice Inspection was performed to the 1974 Edition Summer 1975 Addenda of Section XI and Appendix III of the Winter 1975 Addenda.No.of WeldsSection XI Requirements Basis for Requesting Relief Al ternate ExaminationsSection XI requires 100%of the attachment weld to be examined by a surface method fov Class 2.Relief is required from ASME Section XI examination require-ments on the basis of partial or total inaccessibility of the attachment weld due to plant design.The specific inaccessi-bility problem for each weld is explained under remarks on the attached tables.The welds in this request for relief are partially or totally inaccessible to all examination methods.Impact on Plant guality and Safety There will be no adverse impact on plant quality and safety by doing only a partial or no code examination of these welds.S-A.6 0 i<i, gl CATEGORY C-E-1.RHR-207 RHR-475(W) XXX-XXX SUR DATA SECTION ISO.NO.WELD NUMBER SHEET NO.XI EXAM RHR-203 RHR-410(W) XXX-XXX SUR DESCRIPTION Attachment weld Attachment weld SECTION III EXAM REMARKS Not accessible -within shielding wall.=Not accessible -within shielding wall. lj~S RE(UEST FOR RELIEF NO.'SI-2-003 Component or System Code Number of Welds Reactor Recir'culation System line 4RRC(8).List attach'ed. All of the subject welds were designed and fabricated to ASME Section III, Class 1.The Preservice Inspection is to be per-formed to the 1974 Edition Summer 1975 Addenda of ASME Section XI and Appendix III of the Winter 1975 Addenda.Ca~caory No.of Welds B-J Section XI Requirement Basis for Requesting Relief These welds are subject to an ultrasonic examination using a calibration block of the same material as the pipe and the same nominal diameter and wall thickness. The calibration block used for the examinations was 4 inch schedule 40 where the piping is 4 inch schedule 80.An error in the construction specification lead to the use of the wrong schedule calibration block.A review of the examinations using the schedule 40 calibration block instead of the schedule 80 block concluded that the examinations were more sensitive. The weld thickness was approximately 0.3 inches, while the calibration block is 0.24 inches thick.Al ternate Examination Impact on Plant (}uality and Safety None.There will be no impact on plant quality and safety by using'he schedule 40 calibration block instead of the schedule 80 calibration block.The use of the schedule 40 block will result fn z more sens',tiv examination <thinner mate;ia';, therefore, smaller notch for calibration reference). 8-A.8 CATEGORY BM DATA SECTION.ISO.NO.MELD NUMBER SHEET NO.XI EXN DESCRIPTION SECTION III EXAM RRC-101 RRC-101;RRC>>101 RRC-101 RRC-102 RRC-102 RRC-102 RRC-102 4RRC(8)1A-1 4RRC(8)1A-2 4RRC(8)2A-1 'RU-148*RRU-152 RRU-146 4RRC(8)1B-1 RRU-151 4RRC(8)1B-2 RRU-150 4RRC(8)2B-1 RRU-149 4RRC(8)2B-2 RRU-153 4RRC(8)2A-2 RRU-147 VOL VOL VOL VOL VOL VOL VOL VOL SML to Pipe'Pipe to Flange SML to Pipe Pipe to Flange SWL to Pipe Pipe to Flange SML to Pipe Pipe to Flange RT/PT RT/PT RT/PT RT/PT RT/PT RT/PT RT/PT RT/PT 8-A.9 f C p (i$I RE(}UEST FOR RELIEF NO.PSI-2-004 Component or System Code Component supports.List attached.The Preservice Inspection was performed to the 1974 Edition.Summer 1975 Addenda of ASi'IE Section XI with guidance from 1977 Edition Minter 1978 Addenda., Number of Welds Cate o C-E-1 N/A (Class 3)No.of Com onents 1 17 Section XI Requirements Basis for Requesting Relief Al ternate Examinations Impact on Plant (}uality and Safety Section XI requires 100>>of the component support structure from the pressure boundary to the supporting structure to be visually examined.All of these component supports are in'side bulkhead penetra-tions and are covered by foam for fire protection which makes them completely inaccessible to visual examination. All components supports have been examined during construction and found to be acceptable. None;all other components supports on these.lines have been examined and found acceptable. Ouring inservice inspection the adjacent supports will be examined.If the adjacent supports fail, then these supports could be examined by removing the foam fire barrier.This will only be done if there is reason to suspect the subject supports have failed.8-A.10 CATEGORY C-E-1 AND CLASS 3DATA SECTION ISO.NO.SUPPORT NO.SHEET NO.XI EXAM DESCRIPTION SECTION III EXAM REMARKS Rigid SM-301 SW-301 SW-301 SW-301 SM-301 SM-301 SW-301 SM-303 SM-303 SM-303 SM-303 SM-303=SM-303 SM-305 SW-60 SW-67 SW-69 SM-317 SW-72 SW-75 SW-77 SM-152 SM-431 SM-142 SW-203 SW-438 SM-137 SM-34 XX-XXXX XX-XXXX XX-XXXX XX-,XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX XX-XXXX YT-3 Rigid YT-3 Rigid VT-3 Rigid VT-3 Rigid VT-3 Rigid VT-3 Rigid VT-3 Rigid VT-3 Rigid YT-3 Rigid VT-3 Rigid VT-3 Ri gid VT-3 VT-3 Ri gid Rigid VT-3 Rigid RCIC-205 RCIC-18 HY-0423 VT-3 VT/SUR VT/SUR YT/SUR VT/SUR VT/SUR VT/SUR VT/SUR VT/SUR YT/SUR VT/SUR VT/SUR VT/SUR VT/SUR VT/SUR VT/SUR Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations; Inaccessible due to foam filled penetrations; Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to.foam filled penetrations. Inaccessible due to foam filled penetrations. Inaccessible due to foam fill ed-penetr ations. g'T'pP CATEGORY C-E-1 AND CLASS 3 DATA SECTION ISO.NO.SUPPORT NO.SHEET NO.XI EXAM DESCRIPTION SECTION III EXAM REHARKS SW-307 SM-916N HV-1626 VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. 4 SM-314 SM-946N HV-1633 VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-315 SW-951N HV-1639 VT-3 Ri gid'VT/SUR Inaccessible due to foam filled penetrations, CO I M 4 qf b 1: