ML17278A939

Forwards Addl Info Re 10-yr Inservice Insp Program,Per NRC 860610 Request for Addl Info.Status of Relief Requests Re Preservice Insp Requested

ML17278A939
Person / Time
Site:	Columbia
Issue date:	07/22/1986
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Adensam E Office of Nuclear Reactor Regulation
References
GO2-86-679, TAC-57728, NUDOCS 8607280126
Download: ML17278A939 (22)

Text

REQULA ORY INFORNATION DISTR IBUTI 'SYBTEN (R IDS)

ACCESSION NBR: 8607280126 DOC. DATE: 86/07/22 NOTARIZED: NO DOCKET I FAC IL: 50-397 MPPSB Nuclear Progecti Unit 2i Mashington,. Public Powe 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN Q. C. Mashington Public Power Supply Sgstem RECIP. NANE RECIPIENT AFFlLIATIGN ADENBAN> E. Q. BMR Prospect Directorate 3

SUBJECT:

Forwards addi info re i0-gr inservice insp program> per NRC 860610 request for addi info. Status of relief requests T e preservice insp. also requested.

DISTRIBUTION CODE: A047D COPIES RECEIVED: LTR ENCL SI ZE:

TITLE: OR. Submittal: Inservice Inspection/Testing NOTES:

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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 ab0728012b Bb0722 I" i PDR ADDCK 05000397 8 PDR July 22, 1986 G02-86-679 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn: Ms. E. G. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 INSERVICE INSPECTIONS AND INSERVICE TESTING PROGRAMS AND RESPONSE TO REQUEST FOR INFORMATION

Reference:

1) Letter, E.G. Adensam (NRC} to G.C. Sorensen (SS),

"WNP-2 Ten Year Internal Inservice Inspection Program Request for Additional Information",

dated June 10, 1986

2) Letter, G.C. Sorensen (SS) to E.G. Adensam (NRC),

"Inquiry as to Status of Request for Relief for Interim Approval of Revision 3 to WNP-2 Pump and Valve Inservice ilest Program Plan",

G02-86-211, dated March 12, 1986

3) Letter G.C. Sorensen (SS) to E. G. Adensam (NRC),

"Preservice Inspection Program Plan Inservice Inspection Program Plan Request for Relief",

G02-86-179, dated February 27, 1986 As requested by Reference 1} enclosed is additional information on the WNP-2 10-year Inservice Inspection Program. Should you have further questions on the Inservice Inspection or Inservice Testing Program Plan please contact Mr. P. L. Powell; Manager, WNP-2 Licensing.

0 E. G. Adensam Page Two July 22, 1986 INSERVICE INSPECTIONS AND INSERVICE TESTING PROGRAMS AND RESPONSE TO RE(VEST FOR INFORMATION Additionally References 2) and 3) requested action on the staff's part which to date has not been forthcoming. A review of our records showi we have two outstanding related open items. Reference 2) requested the status of the interim approval'to use.Revision 3 of the WNP-2 Pump and Valve Test Program submitted December 26, 1985. Reference 3}

requested NRC's review of Preservice Inspection and Inservice Inspec-tion requests for relief submitted 5/17/85 and 5/29/85 respectively.

Reference 1) does contain questions on the Inservice Inspection Program Request for relief however the Preservice Inspection requests for relief are still open. It is our understanding that this item is re-solved however formal confirmation is still required. A status of these two items is .requested.

Very truly yours, W G. C. Sorensen, Manager Regulatory Programs PLP/bk CC JO Bradfute - NRC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCP&R NRC Site Inspector

t RESPONSE TO NRC's REQUEST FOR ADDITIONAL INFORMATION FOR WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PLANT NO. '2 DOCKET iNUMBER 50-397 guestion:

A.. In Section 14.0, "Weld and Component Identification Diagrams," of the ISI Program Plan, the Program Plan and Schedule Tables list the following welds as being inspected to Table IWC-2500-1, Examination Category C-F-2, Item C5.51 of the Code with only surface examination being required:

WELD NUMBERS, 18RHR(20) A-1 18RHR(20)B-1 18RHR(20)A-2 18RHR(20)B-2 18RHR(20)A-3 18RHR(20)B-3 18RHR(20)A-4 18RHR(20)B-4 To satisfy the inspection requirements of, Item C5.51, these welds require both surface and volumetric examinations.. Clarification of this issue is needed.

~Res onse:

The Supply System revised the WNP-2'SI Program Plan and has included in it a surface and volumetric examination requirement for each of the above 1 isted wel ds. Attached markups ref 1 ect this change.

question:

I B. Isometric Drawing No. HPCS-202-4 is missing from the ISI Program Plan.

Provide the staff with a copy of this drawing.

~Res onse Enclosed is a copy of ISI weld and identification diagram HPCS-202-4, Rev. 2.

This drawing was being revised and inadvertently omitted.

Question:

C. In Relief Request ISI-2-001, relief from performing a 100K volumetric examination of 13 Class 1, ASME Section XI, Category B-A, pressure re-taining welds in the reactor pressure vessel was requested on the basis of partial inaccessibility of the welds due to plant design. for the proposed partial volumetric examination of these welds, the Licensee should define the percentage of each weld to be examined.

~Res onse:

Request for Relief No. ISI-2-001 has been revised and is hereby submitted for your review. It now contains a tabulation of each RPV weld and the percent which is accessible.

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iluestion:

D. Relief Request= ISI-2-002 requests use of a schedule 40 calibration block instead of a Schedule 80 calibration block for inspection of Reactor Recirculation 4-inch decontamination connections (8 welds, Examination '

Category B-J, Item B9. 11). The staff requests a copy of the procedure that will be used for calibration of the inspection equipment using the substitute calibration block. Specifically, what adjustments are made for the difference in wall thickness between the Schedule 40 calibration block and the Schedule 80 connections, and how is the Code required examination volume coverage verified? Justify the determination of impracticality for the use of the Schedule 80 calibration block.

~Res onse: I The Supply System hereby withdraws Relief Request ISI-2-002. The examina-tion of these welds will utilize WNP-2 UT calibration standard UT-29. A comparison of this standard to the piping for which it will be used is as follows:

Piping RRC(8)-4S 4" Sch 80 SA-376 Tp 304 Cal. Block UT-29 4" Sch 80 SA-312 Tp 304 Section XI, Appendix III, III-3411, "Material Specification" requires the calibration blocks be made from material as specified for the piping being joined by the weld. UT-29, although of a different specification, meets this requirement because the physical and chemical properties are identical.

These materials have different specifications because SA-312 allows the pipe to be either seamless or welded, whereas SA-376 allows seamless pipe only. Since the segment of pipe used for the calibration standard does not contain a weld, the materials are identical. Therefore, relief is not

,required. In addition, a review of the baseline examination performed with UT-31, which is more sensitive due to the smaller notch size of the Schedule 40 pipe, showed no indications; therefore, there are no indica-tions to compare the inservice examination to.

All of the changes addressed in these responses have been incorporated into the WNP-2 ISI Program Plan and will be submitted to the NRC when the plan is formally updated.

Date 04/16/85 Revision 0 RE(VEST FOR RELIEF HO. ISI-2-00]

r'*

Component ASME Class 1,Section XI Category B-A pressure retaining welds or System in reactor pressure vessel. List attached.

Code All of the subject welds were designed and fabricated to ASME Section III Class 1 1968 Edition, Summer 1970 Addenda.. The Inservice Inspection is'o be performed to the 1980 Edition Minter 1980 Addenda of ASME Section XI.

Number ~Cate or Ho.

of Melds B-A =. +3- I6 Section XI Section XI requires examination of 100% of the pressure retaining Requirements welds in Category B-A be performed completely. The following

'examinations are requireed:

B-A All pressure retaining welds in Reactor vessel. Yolumetric Basis for Relief is required from ASME Section XI examination requirements Requesting on the basis of partial inaccessibility of the weld due to plant Relief design. The design and access provisions complied with earlier codes which did not require 100K examination. Per 10CFR50.55a'g}

(4} access is not required to be upgraded to the Inservice Inspection Code.

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Date 04/16/85 Revision 0 RE(VEST FOR RELIEF HO. ISI-2-001 Alternative ~~e The accessible portion of each weld will be examined Examinations per Section XI requirements.

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 RPY welds have passed radiographic, magnetic particle and ultrasonic examinations in accordance with Section III.

2. All of the. identified welds will be subject to a system pressure test in accordance with Section XI Class 1 er requi rements.

'. Leak detection systems identify significant leakage in the areas of the subject welds. Appropriate operator action would occur due to leak detection system alarms.

4. Other similar welds in the vessel er-same-piping-run will receive full code examinations. The integrity of the pressure boundary can thus be verified by sampling.

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Date RE(}UEST FOR RELIEF NO. ISI-2-001 Revision Cate or B-A 5 of Weld ISO No. Weld Number Descri tion Examinable Remarks RP V-101 AA BTM HD-SC ¹1 WD 53K See Note 1 RPV-101 AB ¹l-¹2 SC CRC WD 52$ See Note 1 RPV-101 AC ¹2-¹3 SC CRC WO 395 See Note 1 I

RP V-101 ¹3-¹4 SC CRC WD Seven weld two-foot long stabi'lizer 'lugs obstruct at 45 intervals. See Note 1

~

'"'PV-101 AE Vessel to flange 95K Thermocouples at 135 , 270 and 360 RPV-101 BJ ¹3 SC VRT WD at 50 90K Stabilizer lug at weld AD intersection RPV-101 BK ¹3 SC VRT WD at 170 90K Stabilizer lug at weld AO intersection RPV-102 DA BTM HD MRD at 272 67K Thermocouples at weld AA intersection. See Note 2 RPV-102 DB BTM HD MRD at 332 67Ã See Note 2 RPV-102 DC BTM HD MRO at 32 67K See Note 2 RPV-102 OO BTM HD MRD at 92 67K See Note 2 RPV-102 DE BTM HD MRD at 152 67K See Note 2 RPV-102 DF BTM HD MRD at 212 67K See Note 2 RPV-102 DG BOT HO DOL at 270 17$ See Note 3 RPV-102 DR BOT HD DOL at 90 =

17K See Note 3 RPV-102 AJ BOT HD DOL WD 93K See Note 1 4-7

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ISI-2-001 Date RE(VEST FOR RELIEF NO.

Revision Cate or B-A Continued Notes:

Design of RPV shield wall and external inservice inspection system was completed prior to promulgation of amendments to 10CFR50.55a. Their design limits access to less than 100K of this weld.

2. Only 21" starting from the intersection of weld AA and 14" starting from the intersection of weld AJ can e examined due to the vessel k t (A l e foot ss not besn examined on eac weld.

3. Only 12" to 23" on each end of the weld, starting from the intersection of weld AJ, can be examined due'o CRD penetrations and housings.

1 4-8

WASHINGTON PUBLIC POWER SUPPLY SYSTEM WNP-02 IS I PROGRAM PLAN AND PAGE 001 IKTERV<L: 01 OR COMPONENT: 18PHR (20) 2 DATE 04/25/86.:

SCHEDULE'YSTEM DRAWING NO ~ RHR 204 DESCR IPTION: RC IC STf'l-RHR HX-1 A SECT ~

XI EXAM CAL ~ SCHEDULED I DENT ~ t" 0 ~ DES CR TP T I ON EXAM ~ I T EM l'lO MTH ~ BLOCK PER ~ OUTAGE REGS NOTES RHR 590 SPRING N/A N IA N/A OT RHR-612 SPR! NG N/A N/A N/A OT RHR"588 l PSA-3 S (2) N/A

'l/A N/A OT S/N T2792/B2347 1l'HR-589 c'/N PSA"3 SNUBBER N/A N/A N/A OT 4493 RHR-587 SPRING N/A N/A N/A OT R HR-592 P. SA -1/2 SNU BBE R N/A N/A N/A OT S/N 2782 RHR-593 STRUT l'l/A N/A N/A OT R l'.-R -591 SPR INC N/A N/A N/A OT RHR-595 PSA-1 SNUBBER N/A N/A N/A OT S/N 3888 RhR-594 STRUT N/A N/A N/A OT aHR-596 SPR ING N/A N/A N/A OT 18RHR (20) A-1 VALVE TO PIPE C-F-,2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8 RHR-984N SPR ING IWF F X VT3H F RHR-597 ( k )

8 WELDED LUGS C-C C3 ~ 40 SUR F RHR-597 STRUT IWF F-X VT3H

It' "SHINGTON PUBLIC POMLP SUPPLY SYSTr'8

'Jt" P ~ 2 IS I PROGR 'i. Phf~'tl ANO,SCf'EDULE l SVSTEW OR CO~tPC<l=i!'1 ~

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P IPE C-F-2 C5 ~ 51 SUR F8 C5+51 VOL FR 18n~"~, 3 "")A 3

<t EL TO P'IP.= C- -2 C5o 51 SUR C5i51 QhL i9 Ipr TO; =-E C-F-2 C5 ~ 51 SUR C5>>51 VO t >A-i VUBf) R N/A tV/A OT S/N 9929 RHR-586 P SA-3 SNUBB ER N/A F.-X N/A OT S/N 3894 RHR-584 SPR ING N/A N/A N/A OT RHR"583 STRUT N/A N/A N/A OT RHR-582 STRUT N/A N/A N/A OT RHR-975N ANCHOR N/A N/A OT RHR 949N BOX N/A N/A N/A OT RHR-950N BOX N/A N/A N/A OT RHR-951N BOX N/A N/A N/A OT RHR-953N PSA-3 SNUPBER N/A N/A N/A OT S /N 3879 R HR -955N BOX N/A N/A N/A OT

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)'A'SHIN 6 TON PUBL IC P OMER SUPPLY SYSTEM Mt'P-02 ISI PROGRAM PLAN AND SCHEOULE PAGE 001 INTERVAL: 01 SYSTEH OR COHP ONENT'. R FR (20 ) -2 OATE 04/25/86 DRAMING NO ~ RHR-208 OES CR IPTION: LOOP R SPLY- RHR HX1R SECT ~

XI EXAM", CAL ~ SCHEOULEO IDENT-~ NO ~ OES CR IPTI ON EXAM'TFH VO HTH BLOCK PER OUTAGE REQ ~ NOTES RHR-58C SPRING N/A N/A N/A OT RHR "574 P SA -3,S tI:UBB ER Nl A NID N/A OT S/N RHR-573 I PSA -3 SNUBB ER N/A N/A N/A OT S/N RKR-572 SPRING N/A N/A N/A OT RHR-607 SPRING N/A N/A N/A OT RHR-571 SPRING. t! /A N/A N/A OT RHR-575

-PSA-3 SNUBBER N/A . N/A N/A OT S/N RKR-576 STRUT N/A N/A N/A OT RHR-577 SPRING N/A N/A N/A RHR-578 PSA'"3 SNUBBER N/A N/A N/A OT S/N R HR -9 85l".

STRUT t'ai/A N/A N/A 18RHR(20)B-1 VAL VE TO PI PE C "F "2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8 RHR-6 SPR ING IWF F-X VT3H F 18RHti (2C ) 0-2 PIPE TO EL C-F-2 C5 ~ 51 SUR C5 ~ 51 . VOL 16RHR (2C ) 0-3 EL TO PIPE C-F 2 C5 ~ 51 SUR FB C5 ~ 51 VOL F8

MASHINGTON PUBLIC POMER SUPPLY SYSTEh(

MNP-02 ISI PROGRAH PLAN AlUD SCHEDULE PAGE 002 INTERVAL: 01 SYSTEN OR COMPONENT: RHR (20' DATE'4/25/86 DRAMING NO ~ RHR-208 DESCRIPTION: LOOP R SPLY-RHR HXlB SECT ~

XI EXA V; CALe SCHEDULED IDENT ~ NG ~ DESCRIPTION fgAN ~ TTF'H NO HTH ~ PiL()CK PER~ OUTAGE REQ ~ NOTES R HR-581 18RHR (20) 8-4 STRUT PIPE TO, TEE IMF C" F-2 F-X C5 ~ 51 VT3H SUR F8 e

C5 ~ 51 VOL F8 RHR-a PSA-3 SNUBBER N/A N/A N/A OT S/N RHR-570 PSA-3 SNUBB ER N/A N/A N/A OT S/N RHR-568 SPRING N/A N/A N/A OT RHR-567 STRUT N/A N/A N/A OT RHR-566 STRUT N/A "l /A N/A OT RHR-969N ANCHOR N/A N/A N/A OT RHR-960N R HR-961N PSA-1 SNUBBER Sf>(2) N/A. N/A N/A OT S/9 ~,

PSA"3 SNUBBER h!/A N/A N/A OT, S/N RHR-1003N STRUT N/A N/A N/A DT RHR<<938N RHR-930M PSA-1 '/A N/A OT S/N STRUT N/A N/A N/A OT RHR-939N PSA-3 SNUBBER N/A N/A N/A OT S/N R HR-957M PSA-3 SNUBBER N/A hl/A N/a OT S/N

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