ML17291A464

Submits Inservice Insp Summary Rept for Refueling Outage RF94A,Spring 1994.

ML17291A464
Person / Time
Site:	Columbia
Issue date:	10/19/1994
From:	Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17291A465	List: ML17291A464 ML17291A468
References
GO2-94-238, NUDOCS 9411030023
Download: ML17291A464 (15)

Text

PRIG RITY

'ACCELERATED RIDS PROCESSING 1

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9411030023 DOC.DATE: 94/10/19 NOTARIZED: NO DOCKET N FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System r RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

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SUBJECT:

Submits "Inservice Insp Summary Rept For Refueling Outage I RF94A/ Spring 1994 ~

DISTRIBUTION CODE: A047D TITLE: OR COPIES RECEIVED:LTR Submittal: Inservice/Testing/Relief from ENGL 5 sxzE: f+

ASME Code GL-89-04 NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 0 PD4-2 PD 1 1 CLIFFORD,J 2 2

,'NTERNAL: ACRS 6 6 AEOD/SPD/RAB 1 1

~EIX-~ESTER:(QO 1 1 NRR/DE/EMCB 1 1 NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DSIR/EIB 1 1 EXTERNAL LITCO BROWN g B 1 1 LITCO RANSOME,C 1 1 NOAC 1 1 NRC PDR 1 1 YOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVKSTF! CONTACT I'I IE DOCI.'ifEYTCONTROL DESK, ROOhf PI-37 (EXT. 504-~083 I TO ELIAfI%ATE YOUR XA~fL FRO~I DISTRIBUTION LIS'I'S I'OR DOC!. Nf EX'I'S YOI: DOY."I'."HEI D!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 October 19, 1994 G02-94-238 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

WNP-2, OPERATING LICENSE NPF-21 INSERVICE INSPECTION SUMMPLRY REPORT NIS-1 NIS-2, OWNER'S REPORTS

Reference:

1) Letter, GO2-93-234, dated September 16, 1993, JV Parrish (SS) to NRC, same subject

2) Letter, GO2-94-062, dated March 16, 1994, JV Parrish (SS) to NRC, same subject In accordance with the requirements of 10 CFR 50.55a(g) and IWA-6230 of ASME Section XI, as previously agreed, the Supply System hereby submits five (5) copies of the WNP-2 Inservice Inspection (ISI) Summary Report for the Spring 1994 refueling outage. Included in the Summary Report are the NIS-1 Owner's Data Report for inservice inspections performed during the Spring 1994 refueling outage, and NIS-2 Owner's Reports on repair or replacement completed since the filing of the last ISI Summary Report and Supplement No. 1 to the ISI Summary Report (see Reference 2).

Also enclosed are revised Relief Request ISI-2-003 and new Relief Request ISI-2-011 concerning the limited Code examination coverage detailed in Table I of the Spring, 1994, ISI Summary Report. The relief requests are for the first inspection interval and are submitted for your review and approval.

94ii030023 94i019 PDR ADOCK 05000397 PDR

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Page 2 INSERVICE INSPECTION SU1VMARY REPORT NIS-1/NIS-2, OWNER'S REPORTS Should you have any questions or desire additional information regarding this matter, please call me or Mr. P.R. Bemis at (509) 377-4027.

. V. Parrish (Mail Drop 1023)

Assistant Managing Director, Operations JRH/ml Attachments CC: LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Sr. Resident Inspector - 927N

RELIEF REQUEST ISI-2-011 Component or System ASME Section III Class 1 and 2,Section XI Categories B-K-1 and C-C integral attachment welds for piping, pumps, and valves.

Welds C d Cl C RBX . d ill i . ~M B-K-1 B10.10 RRC-HA-l(W) RRC-101-1 B-K-1 B10.10 RRC-HB-1(W) RRC-102-1 C-C C3.40 RHR-77(W) RHR-205-1 C-C C3.40 RHR-410(W) RHR-203-2 Welds RRC-HA-1(W) and RRC-HB-1(W) are SA 240 Type 304 material welded to SA 358 GR 304 CL 1 pipe. Welds RHR-77(W) and RHR-410(W) are SA36 material welded to SA 308 GR B pipe.

Code All of the subject welds were designed and fabricated to ASME Section III Class 1 or 2.

The inservice inspection is to be performed to the 1980 Edition, Winter 1980 Addenda of ASME Section XI.

Section XI requires examination of 100% of each category B-K-1 and C-C weld. All integral attachment welds require examination.

The following examinations are required for examination category B-K-1 and C-C:

Item no Descri tion Exam Method B10.10 Integrally welded attachments Surface C3.40 Integrally welded attachments Surface

Basis for Requesting Relief Relief is required from ASME Section XI examination requirements for the two item B10.10 welds on the basis of partial inaccessibility of the weld due to plant design and high dose required to prepare for and perform the examinations. The welds identified in this relief request require disassembly of a component support collar to gain access to perform a 100%

Code examination.

Relief is required from ASME Section XI examination requirements for the two item C3.40 welds on the basis of inaccessibility of the welds due to their location in a pipe chase where access will place a hardship on the plant to gain access.

Alternative Examinations The accessible portion of the item B10.10 welds, without removing the component support, of each weld will be examined per,Section XI requirements.

No alternate examination is proposed for the item C3.40 welds.

Impact on Plant Quality and Safety There will be no adverse impact on plant quality and safety by doing only a partial Code examination of the item B10.10 welds.

1. The attachment welds have passed dye penetrant examination in accordance with Section III.

2. Seventy-five (75) percent of weld RRC-HA-1(W) and fifty (50) percent of weld RRC-HB-1(W) are accessible without removing the component support collar

3. The percent of category B-K-1 welds examined during the first inspection interval exceeds 95% of total welds in this category. During the first inspection interval no unacceptable indications were found in this sample.

4. Other similar welds in this system and in the area of the subject welds have or will receive full Code surface examination coverage. The integrity of the pressure boundary can thus be verified by sampling.

There will be no adverse impact on plant quality and safety by doing only a partial Code examination of the item C3.40 welds.

1. The attachment welds have passed magnetic particle examination in accordance with Section III.

3. The percent of category C-C welds examined in the first inspection interval exceeds 96% of total welds in this category. During the first inspection interval no unacceptable indications were found in this sample,

4. Other similar welds in this system and in the area of the subject welds have or will receive full Code surface examination coverage. The integrity of the pressure boundary can thus be verified by sampling.

The sample sizes in these two categories are reasonably large and representative and assure continued plant quality and safety.

REQUEST FOR RELIEF NO. ISI-2-003 (revised)

Component or Component Supports, ASME Section III Code Class 1, 2, and 3 System Welded Attachments, ASME Section III Code Class 3 Code All of the component supports were designed and fabricated to ASME Section III, NF. All of the welded attachments were designed and fabricated to ASME Section III, ND. The inservice inspection is to be performed to ASME Section XI 1980 Edition, Winter 1980 Addenda.

Number of QategoOr Item No No. of Items Cemyeaett F-B F-l,F-2 k$ 32 ttems F-C F-l, F-2,F-3, F-4 1 D-B D2.20 5 D-C D3.20 1 Supports and welded attachments are listed at the end of this request for relief.

Section XI Section XI requires a visual examination ~F-3) of component supports Requirements and Class 3 welded attachments as follows:

Class 1, 2, 3 category F-B VT-3 Class 1, 2, 3 category F-C VT-3 and VT-4 Class 3 category D-B VT-3 Class 3 category D-C VT-3

~fi Basis for The component supports and welded attachments are completely or Requesting partially inaccessible to examination. The component supports and Relief welded attachments are within y i I &i b i pip chases. A loss of function of the component support is expected to be identified at adjacent supports which are examined. For supports within wall penetrations, it should also be noted that the pipe is completely surrounded by concrete with the metal support embedded in the concrete; the annulus between the pipe and concrete is foam filled. If any failure did occur, the concrete would perform a backup support function.

REQUEST FOR RELIEF NO. ISI-2-003 Alternate The component supports and welded attachments are completely or Examinations partially inaccessible to all examination techniques. No alternate I

I examinations are proposed.

Impact of Plant There will be no adverse impact on plant quality and safety. Failure of Quality and these component supports or welded attachments will not prevent the Safety reactor from being shut down. During the ftrst inspection period the following percent ofitems were examined:

Examination Cate o Percent D-B >97%

D-C >90%

F-B >93%

F-C >99%

No unacceptable indications were found during these examinations.

Later editions of ASME Section XI deftne the sample size for category F-B (category F-A in later Code editions) as 10% of the Class 3 piping supports. The percent of Class 3 component supports examined during the first interval (>93% of rigid type supports for F-B) exceeds the minimum sample size of 10% required in later Code editions.

Later editions ofASME Section XI deftne the sample size for category F-C (category F-A in later Code editions) as 15% of the Class 2 piping supports. The percent of Class 2 component supports examined during the ftrst interval (>93% of spring type supports for F-B) exceeds the minimum sample size of 15% required in later Code editions.

The Class 3 welded attachments in categories D-B and D-C examined during the first inspection interval represent greater than 96% of the total welded attachments in these Avo categories.

The sample sizes in these four categories are reasonably large and representative and assure continued plant quality and safety.

REQUEST FOR RELIEF NO, ISI-2-003 List of Inaccessible Component Supports and Class 3 Welded Attachments Identification Number Drawing Description Category Item No.

SW-69 see note 1 SW-301 Rigid F-l, F-2 SW-67 see note 1 SW-301 Rigid F-l, F-2 SW-72 see note 1 SW-301 Rigid F-B F-l, F-2 SW-317 see note 1 SW-301 Rigid F-B F-l, F-2 SW-152 see note 1 SW-303 Rigid F-B F-l, F-2 SW-431 see note 1 SW-303 Rigid F-1 F-2 SW-137 see note 1 SW-303 Rigid F-B F-l, F-2 SW-438 see note 1 SW-303 Rigid F-B F-l, F-2 SW-203 see note 1 SW-303 Rigid F-B F-l, F-2 SW-77 see note 1 SW-301 Rigid F-B F-l, F-2 SW-34 see note 1 SW-305 Rigid F-B F-l, F-2 SW-142 see note 1 SW-303 Rigid F-l, F-2 SW-60 see note 1 SW-301 Rigid F-B F-l, F-2 SW-916N see note 1 SW-307 Rigid F-B F-l, F-2 SW-75 see note 1 SW-301 Rigid F-B F-l, F-2 RCIC-18 see note 1 RCIC-205 Rigid F-B F-l, F-2 FPC-64 see note 1 FPC-301 Box F-B F-l, F-2 FPC-64(WJ see note 1 FPC-301 Welded Attach D-C D3.20 FPC-98 see note 1 FPC-304 Rigid F-B F-l, F-2 FPC-114 see note 2 FPC-304 Rigid F-B F-l, F-2 FPC-203 see note 1 FPC-304 Box F-B F-l, F-2 LPCS-19 see note 1 LPCS-202 Anchor F-B F-l, F-2 RHR-53 see note 3 RHR-207 Spring F-C F-l, F-2, F-3, F-4

Identification Number Drawing Description Category Item No.

RHR-99 see note 1 RHR-210 Anchor F-B F-l, F-2 RHR-1 74 see note 2 RHR-201 Box F-B F-l, F-2 RHR-6'05 see note 2 RHR-201 Strut F-B F-l, F-2 RHR-606 see note 2 RHR-201 Strut F-B F-l, F-2 SLC-4453-57 see note 1 SLC-101 Rigid F-B F-l, F-2 SW-90 see note 1 SW-307 Rigid F-l, F-2 SW-90(W) see note 1 SW-307 Welded Attach D-B D2.20 SW-123 see note 1 SW-301 Rigid F-B F-l, F-2 SW-123(W) see note I SW-301 Welded Attach D-B D2.20 SW-439 see note 1 SW-303 Rigid F-B F-l, F-2 SW-439(W) see note I SW-303 Welded Attach D-B D2.20 SW-946N see note 1 SW-314 Rigid F-B F-l, F-2 SW-946N(WJ see note 1 SW-314 Welded Attach D-B D2.20 SW-951N see note 1 SW-315 Rigid F-B F-l, F-2 SW-951N(W) see note 1 SW-315 Welded Attach D-B D2.20 SW-950N see note 1 SW-315 Rigid F-B F-l, F-2 Notes 1 Covered or contained within glare barrier 2 In enclosed cubicle or pipe chase 3 Limited examination due to surrounding interferences

V &IC3R.I"EY (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9410280125 DOC.DATE: 94/10/21 NOTARIZED: NO DOCKET N FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION m~nr ~

SUBJECT:

"Primary Reactor Containment 1994 Integrated Leakage Rate Test Final Rept." W/941021 ltr.

DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR I ENCL TITLE: OR Submittal: Append J Containment Leak Rate Testing L SIZE: /

0 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 0 PD4-2 PD 1 1 CLIFFORD,J 2 2 INTERNAL: ACRS 6 6 EILE-.CENTER 0 1 . 1 OGC/HDS3 1 1 RES/DE/SEB 1 1" RES/DSIR/SAIB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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RECIPIENT'S:

i4'OTE TO ALL"RIDS" PLEASE HELP US TO REDUCE iV'iSTE! CONTACT TI IE DOC! 'ifEYTCONTROL

• DESK, ROO!if Pl-37 (EXT. 504-7083 ) TO ELI nfl.'PATE YOUR NAifL Pl<Oif DISTRIBUTION LIS'I'S I'OR DOCUA I Lzi'I'S YOU DOY."I'L'I'.D!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 15

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 993S2-0968 ~ (S09) 372-$ 000 Docket No. 50-397 October 21, 1994 G02-94-244 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject; WNP-2, OPERATING LICENSE NPF-21 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST

References:

1) WNP-2 Final Safety Analysis Report, Washington Public Power Supply System

2) Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Code of Federal Regulations, Title 10, Part 50, Appendix J

3) Leakage Rate Testing Containment Structures for Nuclear Reactors, American National Standards Institute, Inc., New York, NY; ANSI N45.4-1972

4) Letter, dated April 29, 1987, DM Crutchfield (NRC) to GC Sorensen (SS), "Issuance of Exemption to a Provision of Appendix J and Amend-ment No. 41 to Facility Operating License No. NPF-21, WPPSS Nuclear Project No. 2 (TAC No. 60740)"

In accordance with the reporting requirements stipulated in Reference 2, and in compliance with the testing commitments, regulations and guidelines specified in References 1, 2, 3, and 4, the Reactor Containment Building Integrated Leak Rate Test, 1994 is submitted.

Should you have any questions or desire additional information regarding this matter, please call me or D. A. Swank at (509) 377-4563.

Sincerely

. V. Parrish (Mail Drop 1023)

Assistant Managing Director, Operations Attachment CC: LJ Callan - NRC RIV DL Williams - BPA/399 NS Reynolds - Winston & Strawn NRC Sr. Resident Inspector - 927N JW Clifford - NRC KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office 94i0280125 94i02i '

PDR ADOCK 05000397 PDR V M~