ML17291B167

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Forwards Second 10-Yr ISI Program Plan Relief Request for Exam Category B-F
ML17291B167
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 12/13/1995
From: Parrish J
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-95-271, NUDOCS 9512210003
Download: ML17291B167 (8)


Text

PR.I&R.I EY ACCELERATED RIDS PROCESSING 1

~ REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9512210003 DOC.DATE: 95/12/13 NOTARIZED: NO DOCKET g 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 Document Control Branch (Document Control Desk)

SUBJECT:

Forwards second 10-Yr ISI program plan relief recpxest for exam category B-F.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-89-04 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 INTERNAL: 6 0 AEOD/SPD/RAB 1 1 ILE CEN~gg 0. 1 1 NRR/DE/ECGB 1 1

/DE7EMCB 1 1 NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EMMEB 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE 4VKSTE! CONTACT'I'IIE DOCL'ifENTCONTROL DISTRIBU I'ION LIS'I'S I'OR DOCL BIEN'I'S YOL'ON"

/

I'l DESk. ROOh,l Pl-37 (CRT. 504-~083 ) TO I'.LI%1INATE YOL'R i'ANILFROil I'.D!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 14

ai WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 December 13, 1995 G02-95-271 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 SECOND 10-YEAR INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST FOR EXAMINATIONCATEGORY B-F

References:

1) Letter GO2-94-286, dated December 27, 1994, JV Parrish (SS) to NRC, "Second 10-Year Inservice Inspection Program Plan"
2) Letter GO2-95-175, dated September 12, 1995, JV Parrish (SS) to NRC, "Inservice Inspection Summary Report for Tenth Refueling Outage" Reference 1 submitted the second 10-year inservice inspection program plan. Reference 2 identified 2 welds where ASME Section XI requirements could not be met. The reference committed to submitting relief requests for these two welds. Per discussion with staff, a determination was made that a relief request was required only for the weld in Examination Category B-F. Therefore, in a'ccordance with 10 CFR 50.55a(g)(6)(i), the Supply System requests approval of relief request 2ISI-17 for relief from 100% examination of Category B-F nozzle-to-safe-end welds. Details are. included in Attachment 1.

Review and approval of this relief request is requested prior to April 1, 1996.

9';I" ~~Q Qr 95122i0003 5000397

,,l PDR AQOCK pDP 9

Page 2 SECOND 10-YEAR INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST FOR EXAMINATIONCATEGORY B-F 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)

Vice President, Nuclear Operations cc: LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, WCFO NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Sr. Resident Inspector - 927N

ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-17 Welds for Which Relief is Requested ASME Section XI, 1989 Edition, no Addenda, Table IWB-2500, Examination Category B-F, Item Number B5.10 welds listed below.

Table I: Examination Category B-F Welds and Examination Volume Coverage

% Code Volume ISI Identification No. ~Descri tion D~iN . PM Examined 10HPCS(1)-4 SE to Nozzle HPCS-101 02 >80 10LPCS(1)-4 SE to Nozzle LPCS-101 02 >75 12LPCI(1)A-6 SE to Nozzle RHR-101 >80 12LPCI(1)B-6 SE to Nozzle RHR-102 >80 12LPCI(1)C-6 SE to Nozzle RHR-103 >80 12RFW(1)AA-11 SE to Nozzle RFW-101 03 >90 12RFW(1)AB-11 SE to Nozzle RFW-101 04 >80 12RFW(1)AC-13 SE to Nozzle RFW-101 05 >80 12RFW(1)BD-11 SE to Nozzle RFW-102 03 >90 12RFW(1)BE-11 SE to Nozzle RFW-102 04 >80 12RFW(1)BF-14 SE to Nozzle RFW-102 05 >80 12RRC(1)-N2A-6 SE to Nozzle RRC-101 08 >80 12RRC(1)-N2B-6 SE to Nozzle RRC-101 07 >80 12RRC(1)-N2C-6 SE to Nozzle RRC-101 06 >80 12RRC(1)-N2D-6 SE to Nozzle RRC-101 05 >80 12RRC(1)-N2E-6 SE to Nozzle RRC-101 04 >80 12RRC(1)-N2F-6 SE to Nozzle RRC-102 08 >80 12RRC(1)-N2G-6 SE to Nozzle RRC-102 07 >80 12RRC(1)-N2H-6 SE to Nozzle RRC-102 06 >80 12RRC(1)-N2J-6 SE to Nozzle RRC-102 05 >80 12RRC(1)-N2K-6 SE to Nozzle RRC-102 04 >80 24RRC(2)A-1 SE to Nozzle RRC-101 01 >80 24RRC(2)B-1 SE to Nozzle RRC-102 01 >80 4JP(NZ) A-1 SE to Nozzle RPV-101 >90 4JP(NZ)B-1 SE to Nozzle RPV-101 >90

4 ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-17 ASME Section XI Requirements ASME Section XI, 1989 Edition, no Addenda, Table IWB-2500-1, Examination Category B-F, item B5.10 requires a volumetric examination of the weld and adjacent base metal as defined in Figure IWB-2500-8.

Appendix III, III-4420 requires examination volume to be covered in two-beam path directions.

Code Requirement from Which Relief is Requested Relief is requested from performing a volumetric examination in two-beam path directions per paragraph III-4420 of 100% of the examination volume defined in Figure IWB-2500-8 for the welds listed in Table I above.

Basis for Relief Design of the nozzle-to-safe-end welds preclude obtaining two-beam path direction for 100% of the examination volume of the welds listed in Table I. Examination of these welds is performed using a 45-degree shear wave for the safe-end portion of the weld and 45 and 60-degree refracted longitudinal (RL) wave transducers for the inconel portion of the weld. Due to the configuration of the nozzle taper 100% coverage of examination volume is not possible in the beam direction looking away from the nozzle for the 45-and 60-degree RL transducers (see Figure 1).

45I60 RL Gaud r t<ozzlo

, ~lal Examlnatlon III

&mmlnatlon Inconel Buttehng Volume Figure 1: Typical Weld Volume Coverage for Nozzle-to-Safe-end Welds

ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-17 Alternative Examinations Perform the examinations required by ASME Section XI, Appendix III, III-4420 to the maximum extent allowed by the nozzle-to-safe-end configuration using 45-degree shear, 45-degree refracted longitudinal (RL), and 60-degree RL wave transducers. The extent of the examination volume coverage is defined in Table I.

Justification for the Granting of Relief There will be no adverse impact on plant quality and safety by doing only a partial Code examination of these welds for the following reasons:

The Code examinations are being supplemented by the technique suggested in Information Notice 90-30', General Electric (GE) Service Information Letters (SIL) 455 Revision 1, and 455 Revision 1 Supplement 1'sing 45 and 60-degree refracted longitudinal wave transducers. The examination of the safe-end side of the weld is accomplished by the 45-degree shear wave technique and 100% coverage of this examination volume is obtained. The inconel portion of the weld is examined with a 45-degree RL wave supplemented by a 60-degree RL wave.

2, No unacceptable indications were found during the first inservice inspection interval examinations4 using the techniques described in GE SIL 455 and NRC IN 90-30.

NRC Information Notice No. 90-30, "Ultrasonic Inspection Techniques for Dissimilar Metal Welds", May 1, 1990 GE SIL No. 455 Revision 1, "ISI of Additional Alloy 182 Weldments", February 22, 1988 GE SIL No. 455 Revision 1 Supplement 1, "ISI of Additional Alloy 182 Weldments", June 23, 1989 ISI Summary Reports for Refueling Outages RF92A and RF94A, pg 6

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ATTACHMENT 1 RELIEF REQUEST NO. 2ISI-17

3. The identified welds will be subject to a system pressure test in accordance with ASME Section XI Examination Category B-P requirements'.
4. Leak detection systems identify significant leakage in the areas of the subject welds'.

Appropriate operator action would occur due to leak detection system alarms7.

5. The percent of achievable examination volume is significant and representative of the item B5.10 welds. Nozzle-to-safe-end weld integrity will be ensured by completing the percent of the welds'xamination volume defined in Table I.

Implementation Schedule This relief request applies to the entire second inspection interval, ISI Program Plan Second Interval pg 5-67 WNP-2 Final Safety Analysis Report, Amendment No. 36, page 5.2-36, dated December, 1985 PPM 4.3.1.2 "High Unidentified Reactor Leakage in Primary Containment"