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 WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Butler W Office of Nuclear Reactor Regulation
References
GO2-85-255, TAC-57728, NUDOCS 8505220008
Download: ML17277B740 (24)

Text

REGULATORY I< ORMATION DISTRIBUTION "SYST M (RIDS)

CHOATE:

O'CCES$ ION NBR:8505220008 6C 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: 05000397 OL; 12/20/83 REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB2 BC 01 7 7 INTKRNAL; ACRS 16 10 10 ADM/LFMB 0 ELO/HDS2 1 0 NRR/DE/MEB 15 NRR/DE MTFB NRR/DL/TAPMG 1 0Q 1 RGN5 1 EXTERNAL'POR 03 1- 1 NRC PDR 02 NSIC 05>> 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

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Washington Public Power Supply System 30006eorge Washington Way P.O. Box968 Richland, Washington 99352-0968 (509)372-5000 Docket No. 50-397 8505220008 8505i7 PDR ADOCK 05000397 May 17, 1985 8 PDR G02-85-255 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 CPPR-93 PRESERVICE INSPECTION PROGRAM PLAN REQUESTS FOR RELIEF

Reference:

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 )p W.S. Chin, BPA (399)

M.R. Humm, NRC J.B. Martin, -NRC 04' ge

abl 88 ~ Al ternati ve The welds in this request for relief are partially or totally Examinations inaccessible to all examination methods. I Impact on There will be no adverse impact on plant quality and safety by Plant guality doing only a partial code examination of these welds. and Safety

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 SECTION ISO. NO. WELD NUMBER SHEET NO. XI EXAM DESCRIPTION III EXAM REMARKS RRC-104 2RRC(51)-1 XXX-XXX PT Nozzle to Forging 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 ) REQUEST FOR RELIEF NO. PSI-2-002 Component Component support attachment welds. List attached. or System Code 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. Number of ~Cate ory No. of Welds WeldsSection XI Section XI requires 100% of the attachment weld to be examined Requirements by a surface method fov Class 2. Basis for Relief is required from ASME Section XI examination require-Requesting ments on the basis of partial or total inaccessibility of the Relief attachment weld due to plant design. The specific inaccessi-bility problem for each weld is explained under remarks on the attached tables. Al ternate The welds in this request for relief are partially or totally Examinations inaccessible to all examination methods. Impact on There will be no adverse impact on plant quality and safety by Plant guality doing only a partial or no code examination of these welds. and Safety S-A.6 0 i<i, gl CATEGORY C-E-1. DATA SECTION SECTION ISO. NO. WELD NUMBER SHEET NO. XI EXAM DESCRIPTION III EXAM REMARKS RHR-203 RHR-410(W) XXX-XXX SUR Attachment weld Not accessible - within shielding wall.= RHR-207 RHR-475(W) XXX-XXX SUR Attachment weld Not accessible - within shielding wall. lj ~ S RE(UEST FOR RELIEF NO.'SI-2-003 Component Reactor Recir'culation System line 4RRC(8). List attach'ed. or System Code 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. Number of Ca~caory No. of Welds Welds B-J Section XI These welds are subject to an ultrasonic examination using a Requirement calibration block of the same material as the pipe and the same nominal diameter and wall thickness. Basis for The calibration block used for the examinations was 4 inch Requesting schedule 40 where the piping is 4 inch schedule 80. An error Relief 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 None. Examination Impact on There will be no impact on plant quality and safety by using Plant (}uality schedule 40 calibration block instead of the schedule 80 'he and Safety 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. SECTION ISO. NO. MELD NUMBER SHEET NO. XI EXN DESCRIPTION III EXAM RRC-101 4RRC(8)1A-1 'RU-148 VOL SML to Pipe RT/PT RRC-101; 4RRC(8)1A-2 RRU-152 VOL 'Pipe to Flange RT/PT RRC>>101 4RRC(8)2A-1 RRU-146 VOL SML to Pipe RT/PT RRC-101 4RRC(8)2A-2 RRU-147 VOL Pipe to Flange RT/PT RRC-102 4RRC(8)1B-1 RRU-151 VOL SWL to Pipe RT/PT RRC-102 4RRC(8)1B-2 RRU-150 VOL Pipe to Flange RT/PT RRC-102 4RRC(8)2B-1 RRU-149 VOL SML to Pipe RT/PT RRC-102 4RRC(8)2B-2 RRU-153 VOL Pipe to Flange RT/PT 8-A.9 f p C (i$ I RE(}UEST FOR RELIEF NO. PSI-2-004 Component Component supports. List attached. or System Code 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 Cate o No. of Com onents Welds C-E-1 1 N/A (Class 3) 17 Section XI Section XI requires 100>> of the component support structure Requirements from the pressure boundary to the supporting structure to be visually examined. Basis for All of these component supports are in'side bulkhead penetra-Requesting tions and are covered by foam for fire protection which makes Relief them completely inaccessible to visual examination. Al ternate All components supports have been examined during construction Examinations and found to be acceptable. Impact on None; all other components supports on these .lines have been Plant (}uality examined and found acceptable. Ouring inservice inspection the and Safety 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 3 DATA SECTION SECTION ISO. NO. SUPPORT NO. SHEET NO. XI EXAM DESCRIPTION III EXAM REMARKS RCIC-205 RCIC-18 HY-0423 VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-301 SW-60 XX-XXXX YT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SW-301 SW-67 XX-XXXX YT-3 Rigid YT/SUR Inaccessible due to foam filled penetrations; SW-301 SW-69 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations; SW-301 SM-317 XX-,XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-301 SW-72 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-301 SW-75 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SW-301 SW-77 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-303 SM-152 XX-XXXX VT-3 Rigid YT/SUR Inaccessible due to foam filled penetrations. SM-303 SM-431 XX-XXXX YT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-303 SM-142 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-303 SW-203 XX-XXXX VT-3 Ri gid VT/SUR Inaccessible due to foam filled penetrations. SM-303 SW-438 XX-XXXX VT-3 Ri gid VT/SUR Inaccessible due to.foam filled penetrations. = SM-303 SM-137 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled penetrations. SM-305 SM-34 XX-XXXX VT-3 Rigid VT/SUR Inaccessible due to foam filled -penetr ations. g 'T 'pP CATEGORY C-E-1 AND CLASS 3 DATA SECTION SECTION ISO. NO. SUPPORT NO. SHEET NO. XI EXAM DESCRIPTION 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: