ML100770221

Columbia, Revision Requests to the Third Ten-Year Inservice Inspection Program

ML100770221
Person / Time
Site:	Columbia
Issue date:	03/11/2010
From:	Oxenford W S Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-10-039, TAC MB1357
Download: ML100770221 (25)

Text

W. Scott Oxenford P.O. Box 968, PE08 NORTHW ESCT Richland, WA 99352-0968 NORTH W EST Ph: 509.377.43001 F. 509.377.4150 soxenford

@ energy-northwest.com March 11,2010 G02-10-039 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION

References:

1) Letter dated April 9, 2001, Jack Cushing, NRC to J.V. Parrish, Energy Northwest, "Approval of Boiling Water Reactor Vessel and Internals Project BWRVIP-75 Weld Examination Schedule for the Columbia Generating Station (TAC No. MB1357)" 2) Letter dated March 16, 2006, William H. Bateman, NRC to Bill Eaton, BWRVIP Chairman, "NRC Approval Letter for BWRVIP-75-A, 'BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules"'

Dear Sir or Madam:

This letter requests NRC approval of two items that would revise the Columbia Generating Station Third Ten-Year Interval Inservice Inspection (ISI) Program Plan as follows: (1) Pursuant to 10 CFR 50.55a(a)(3)(i), Energy Northwest requests NRC approval of Relief Request 31S1-10 regarding use of an updated method for the inspection of the RPV shell-to-flange weld and head-to-flange weld. The updated method would be implemented through the industry Performance Demonstration Initiative program. This request is described in Attachment 1.(2) Pursuant to 10 CFR 50.55a(a)(3)(i), Energy Northwest requests approval of Relief Request 31S1-11. This request proposes to use the requirements of BWRVIP-75-A in lieu of the ASME Section XI and other augmented requirements for the examination of Category B-F, Item 5.10, nozzle-to-safe end welds, NPS 4 or larger and Category B-J, Item B9.11 dissimilar metal welds NPS 4 or larger.This request is described in Attachment

2.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Page 2 Energy Northwest has concluded in the relief requests of Attachments 1 and 2, that the proposed alternatives provide an acceptable level of quality and safety pursuant to the provisions of 10 CFR 50 55a(a)(3)(i).

When approved, Requests 31S1-1 0 and 31S1-1 1 will apply for the remainder of the Third Ten-Year ISI Inspection Interval for Columbia Generating Station.Energy Northwest is seeking approval of the attached requests by February 18, 2011 to support a spring 2011 refuel outage.There are no new commitments made in this submittal.

If you have any questions or require additional information, please contact MC Humphreys at (509) 377-4025.Respectf ully, Vice Presid 4ntuclear Generation&

Chief Nuclear Officer Attachments:

1) 10 CFR 50.55a Request Number 31S1-10 2) 10 CFR 50.55a Request Number 31S1-11 cc: Regional Administrator

-NRC RIV Project Manager -NRC NRR NRC Senior Resident Inspector/988C RN Sherman -BPA/1 399 WA Horin -Winston & Strawn REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 1 of 8 10 CFR 50.55a Request Number 31S1-10 Proposed Alternative In Accordance With 10 CFR 50.55a(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety--1. ASME Code Component(s)

Affected The components in the following table are affected by this request.Table 1 Identification Code Item Number Description Category Number AE RPV Shell to Flange Weld B-A B13.30 AG Top Head to Flange Weld B-A B13.40 2. Applicable Code Edition and Addenda The applicable Code Edition and Addenda for Columbia Generating Station (Columbia) is ASME Section XI 2001 Edition through the 2003 Addenda as amended by 10 CFR 50.55a. ASME Section Xl 2001 Edition is used for Appendix VIII.3. Applicable Code Requirements The NRC amended the use of the 2001 Edition through the 2003 Addenda in 10 CFR 50.55a(b)(2)(xxiv), which states, "The use of Appendix VIII and the supplements to Appendix VIII and Article 1-3000 of ASME Section Xl of the ASME BPV Code, 2002 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of this section, is prohibited." Therefore, when referencing Appendix VIII, licensees are limited to using the 2001 Code.The RPV shell-to-flange weld and the head-to-flange weld are currently required to be examined per Appendix 1, 1-2110(b) of the 2001 Edition of the ASME Section XI through the 2003 Addenda, which requires that the examination be conducted in accordance with ASME Section V, Article 4, except that alternative beam angles may be used.Additionally, there is a requirement to supplement the ASME Section V examinations with Table 1-2000-1.

Section T-472.1 of the 2001 Edition of ASME Section V with the 2003 Addenda defines the ultrasonic scanning criteria for the examination of reactor vessel-to-flange welds and closure head-to-flange welds. These are: (T-472. 1.1) The beam angle shall be appropriate for the configuration being examined and that the beam angle shall be capable of detecting the calibration reflectors, over the required angle beam paths.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 2 of 8* (T-472.1.2)

When scanning for reflectors parallel to the weld seam, the angle beam shall be directed at approximate right angles to the weld axis from both sides of the weld (i.e., from two directions) on the same surface when possible.The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base material." (T-472.1.3)

When scanning for reflectors transverse (perpendicular) to the weld seam, the angle beam shall be directed essentially parallel to the weld axis. The search unit shall be manipulated so that the ultrasonic energy passes through the required volume of weld and adjacent base material.

The search unit shall be rotated 180 degrees and the examination repeated." (T-472.2)

Welds that cannot be fully examined from two directions using the angle beam techniques shall also be examined if possible with a straight beam technique." (T-472.3)

Welds that cannot be examined from at least one side (edge) using the angle beam technique shall be noted in the examination report. For flange welds, the weld may be examined with a straight beam or low angle longitudinal waves from the flange surface provided the examination volume can be covered.4. Reason for Request This proposed alternative represents the best available methodology in qualification of equipment and personnel performing ultrasonic examinations.

It also uses an examination process that provides the highest practical quality and greatest amount of coverage for the performance of the flange weld examinations.

As such, the proposed alternative methodology provides an acceptable level of quality and safety. In addition, the approval of this relief results in savings in the cost of performing the examinations, with not having to incorporate the use of two different sets of examination equipment, and also results in lower personnel radiation exposure from not having to use a different methodology for the flange welds.5. Proposed Alternative and Basis for Use PROPOSED ALTERNATIVE In lieu of the Article 4 of ASME Section V angle beam examination, Columbia proposes to use an angle beam examination that will be performed using examination procedures, personnel, and equipment qualified in accordance with Appendix VIII, Supplements 4 and 6, as amended by the conditions set forth in 10 CFR 50.55a.BASIS FOR USE Appendix VIII requirements were developed to ensure the effectiveness of UT examinations within the nuclear industry by means of a rigorous, item-specific performance demonstration.

The performance demonstration was conducted through industry's Performance Demonstration Initiative (PDI) on RPV mockups containing flaws of various size and allocations.

The demonstration established the capability of REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 3 of 8 equipment, procedures, and personnel to find flaws that could be detrimental to the integrity of the RPV. The performance demonstration showed that for the detection of flaws in RPV welds, the UT techniques were equal to or surpassed the requirements of ASME Section V, Article 4 of the ASME Code. Additionally, the PDI qualified sizing techniques are considered to be more accurate than the techniques used in Article 4 of ASME Section V.Although Appendix VIII is not required for the RPV shell-to-flange weld and RPV head-to-flange weld, the use of Appendix VIII criteria for detection and sizing of flaws in these welds will be equal to or will exceed the requirements established by Article 4 of ASME Section V. Therefore, the use of this proposed alternative will continue to provide an acceptable level of quality and safety, and approval is requested pursuant to 10 CFR 50.55a(a)(3)(i).

ALTERNATIVE EXAMINATION In lieu of Article 4 of ASME Section V angle beam examination, Columbia proposes to use an angle beam examination that will be performed using examination procedures, personnel, and equipment qualified in accordance with ASME Section XI Appendix VIII, Supplements 4 and 6, as amended by the conditions set forth in 10 CFR 50.55a.Examination of each weld is described below (see Figure 1 for weld location).

AE -Vessel-to-Flange Weld The ASME Section XI required examination volume will be scanned for flaws from the outside of the vessel using a 60-degree refracted longitudinal wave. However, the curvature of the flange surface above the weld will limit transducer travel such that examinations can only be performed from the shell side. Additionally, the refueling bellows prevent examinations from being performed from the vertical portion of the flange surface located directly above the curvature.

The projected single-side coverage for flaws located parallel to the weld is shown in Figure 2. Since the examination will be from a single side, the requirements of 10 CFR 50.55a (b)(2)(xvi)(A) apply. Therefore, examinations will be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single-side examinations.

To demonstrate equivalency to two-sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and 10 CFR 50.55a(b)(2)(xv)(B) through (G), on specimens containing flaws with non-optimum sound energy reflecting characteristics or flaws similar to those in the vessel being examined.

Examination of the ASME Section XI required volume will be performed as follows:* Per 10 CFR 50.55a(b)(2)(xv)(G)(I), the clad-to-base metal interface, including a minimum of 15 percent T (measured from the clad-to-base metal interface), shall be examined from four orthogonal directions using procedures and personnel qualified in accordance with Supplement 4 to Appendix VIII.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 4 of 8* Per 10 CFR 50.55a(b)(2)(xv)(G)(2), if the clad-to-base-metal-interface procedure demonstrates detectability of flaws with a tilt angle relative to the weld centerline of at least 45 degrees, the remainder of the examination volume is considered fully examined if coverage is obtained in one parallel and one perpendicular direction.

This must be accomplished using a procedure and personnel qualified for single-side examination in accordance with Supplement

6. Subsequent examinations of this volume may be performed using examination techniques qualified for a tilt angle of at least 10 degrees.0 Per 10 CFR 50.55a(b)(2)(xv)(G)(3), the examination volume not addressed by 10 CFR 50.50a(b)(2)(xv)(G)(1) is considered fully examined if coverage is obtained in one parallel and one perpendicular direction, using a procedure and personnel qualified for single-sided examination when the provisions of 10 CFR 50.55a(b)(2)(xv)(G)(2) are met.AG -Closure Head-to-Flange Weld The ASME Section XI required examination volume will be scanned for flaws using a 60-degree refracted longitudinal wave. Examinations will be performed from both the head and flange side of the weld; however, the short distance from the weld to the flange limits the examination on the flange side weld. The RPV head is not clad;therefore, when applying Appendix VIII, only Supplement 6 would normally be required.However, instead of using Supplement 6 to perform the examination of the entire examination volume, guidance will be taken from Code Case N-664 (which applies to unclad vessel welds, excluding flanges), to perform the examination of the inner 15% of the examination volume per Supplement 4 of Appendix VIII. The outer 85% of the examination volume will be examined using Supplement

6. The application of Code Case N-664 (and thus the use of Supplement 4 for the inner 15% on this flange configuration) is an acceptable practice because the PDI qualification using Supplement 4 clad specimens requires examiners to demonstrate more proficiency than the qualification using Supplement 6 specimens.

By using this approach, weld AG will be examined using the same requirements as specified above for weld AE. The projected coverage for flaws located parallel to the weld is shown in Figure 3.JUSTIFICATION FOR GRANTING RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), approval is requested to use the proposed alternatives described above in lieu of the ASME Code Article 4 of ASME Section V.Compliance with the proposed alternatives will provide an adequate level of quality and safety for examination of the affected welds.6. Duration of Proposed Alternate The alternative program will be applicable to the Third Ten-Year Inservice Inspection Interval for Columbia which ends December 12, 2015.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 5 of 8 7. Precedents This request is similar to one approved for Susquehanna Units 1 and 2 on February 20, 2008 (Accession Number ML 071010140).

In addition to Susquehanna numerous other plants have been authorized to use a similar request. The following are a few of the more recent authorizations:

Watts Bar, September 3, 2009, Accession Number ML092300608 Indian Point, April 20, 2009, Accession Number ML090920046 Browns Ferry, October 3, 2008, Accession Number ML082630051 Millstone Power Station, December 24, 2009, Accession Number ML093240393

8. References None REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 6 of 8 Arý Weld AG Weld (M$A staej Recirc Reactor Pressure Vessel Location of Welds Figure 1 REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 7 of 8""ASI.E E"XAMVOLUM ,E::... .~~~~~~~6

--'.i,.., .SCE W:. VOUE;'ýVO M:i~~~~XA .. .441V i. "i. 8 J ...., .: .I.--: 's 60,T- C CWN .UPI ýA?..v0 M " 44.2",.Figure 2 AE Shell-to-Flange Weld REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 1 Page 8 of 8 ASME Exam Volume = 36.9 Sq. in.60°T-Scan Achieved = 36.5 Sq. in.50"P-Scan Achieved = 34.1 Sq. in.Figure 3 AG Closure Head-to-Flange Weld REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 1 of 15 10 CFR 50.55a Request Number 31S1-1 1 Proposed Alternative In Accordance With 10 CFR 50.55a(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety--1. ASME Code Components Affected Table 1 Code Examination Item Class Category Number Description 1 B-F B5.10 Reactor Vessel Nozzle-to-Safe End Butt Welds, NPS 4 or larger 1 B-J B9.11 Dissimilar metal circumferential welds NPS 4 or I I_ larger not included in Category B-F List of affected welds is contained in Table 2 at the end of Section 8.2. Applicable Code Edition and Addenda The Code of Record for the Third Inservice Inspection Interval is ASME Section Xl Code, 2001 Edition, 2003 Addenda.3. Applicable Code Requirements ASME Section XI Code, Subsection IWB-2412 .requires the percentage of examinations be completed in accordance with Table IWB-2412-1, except for the examinations that may be deferred until the end of the Inspection Interval.

Table IWB-2412-1 defines a minimum and maximum number of examinations to be performed each inspection period.Columbia relief request 31SI-08, authorized by NRC letter dated 12/3/2008 (Reference 9), defines the scope of the risk-informed inservice inspection program for Category B-J welds. This program excludes the dissimilar metal welds of Category B-J. Examination of Category B-J dissimilar metal welds is defined in Table IWB-2500-1.

ASME Section Xl Code, Subsection IWB-2500 requires components to be examined as specified in Table IWB-2500-1.

Table IWB-2500-1 column headed "Extent and Frequency of Examination" requires that all Category B-F welds and all dissimilar metal B-J welds be examined over the ten-year ISI interval as described in items B5.10 and B9.11 below: B5.10 Examine the reactor vessel nozzle-to-safe end butt welds, NPS 4 or larger, by volumetric and surface examination method.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 2 of 15 B9.11 Examine piping circumferential welds NPS 4 or larger by volumetric and surface examination method. Per Note (1)(c) examinations shall include all dissimilar metal welds not covered under Category B-F.These welds are also covered by the augmented examination requirements of NUREG-0313 (Reference

1) and GL 88-01, including Supplement 1 (References 2 and 3).Energy Northwest implemented the inspection schedules of BWRVIP-75 for this augmented program in References 4 and 5.4. Reason for Request Energy Northwest proposes to use the schedules and frequencies specified in BWRVIP-75-A (Reference

6) in lieu of the Code requirements listed in Section 3 above.BWRVIP-75-A provides the technical basis for revisions to GL 88-01 inspection schedules, which supports a reduction in the number of welds to be examined in some categories or an increase in the time between inspections in other categories.

This proposed alternative inspection schedule will result in significant dose reduction over the existing schedule and frequency.

5. Proposed Alternative and Basis for Use In lieu of the requirements of ASME Section XI, 2001 Edition, 2003 Addenda, the proposed alternative described below shall be used.Proposed Alternative Energy Northwest will examine the affected Category B-F and B-J welds (Table 2) in accordance with the BWRVIP-75-A schedule and frequency for normal water chemistry, as defined by the NRC Final Safety Evaluation (Reference 8). The examination methods listed in Table IWB-2500-1 are not affected by this request.Basis for Use By letter dated May 14, 2002 (Reference

7) the NRC issued their Final Safety Evaluation (SE) on BWRVIP-75.

In that Safety Evaluation, the NRC staff concluded that, "licensee implementation of the guidelines of BWRVIP-75 report, as modified, will provide an acceptable level of quality for inspection of the safety-related components addressed".

Additionally, the NRC concluded that, "the revised BWRVIP-75 guidance is acceptable for licensee referencing as the technical basis for relief from, or as an alternative to, the ASME Code and 10 CFR 55.55a, in order to use the sample schedules and frequencies specified in the revised BWRVIP-75 report that are less than those required by the ASME Code." BWRVIP-75-A is the updated version of the report which incorporated changes by BWRVIP in response to recommendations in the NRC SE and other necessary revisions identified since the previous publication of the report.BWRVIP-75-A was approved by the NRC March 16, 2006 (Reference 8).

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 3 of 15 Energy Northwest concludes that the use of BWRVIP-75-A, as defined by the NRC Final SE, in lieu of the above specified Code requirements, will provide an acceptable level of quality and safety. Therefore, approval is requested pursuant to 10 CFR 50.55a(a)(3)(i).

6. Duration of Proposed Alternative Energy Northwest proposes to use this alternative for the remaining term of the Third Inservice Inspection Interval for Columbia which began 12/13/2005-and ends 12/12/2015.

7. Precedents A similar relief request was approved for Edwin I. Hatch Nuclear Plant -Units 1 and 2 for their third Inservice Inspection Interval as RR-39 (Reference 10).8. References

1. W.S. Hazelton and W.H. Koo, 'Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping," NUREG-0313, Rev. 2, USNRC, January 1988.2. USNRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel," January 25, 1988.3. USNRC Generic Letter 88-01, Supplement 1, "NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel," February 4, 1992.4. Letter from RL Webring, Energy Northwest to NRC, "Columbia Generating Station, Operating License NPF-21; Request for Adoption of BWRVIP-75 Weld Examination Schedule," dated 2/9/2001, ML010510129.

5. Letter from Jack Cushing, NRC to Energy Northwest Mr. J.V. Parrish, "Approval of Boiling Water Reactor Vessel and Internals Project BWRVIP-75 Weld Examination Schedule for the Columbia Generating Station (TAC NO. MB1 357)", dated 4/9/2001, ML010990083.

6. BWRVIP-75-A:

BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules, Final Report, October 2005. Report submitted to NRC by ERPI letter dated October 31, 2005, ML053070149.

7. Letter from William H. Bateman, NRC to Carl Terry, BWRVIP Chairman, "Final Safety Evaluation of the BWRVIP Vessel and Internals Project, BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75)," EPRI Report TR-1 13932, October 1999 (TAC NO.MA5012) dated May 14, 2002, ML021350645.

8. Letter from William H. Bateman, NRC to Bill Eaton, BWRVIP Chairman, NRC Approval Letter for BWRVIP-75-A, "BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules," dated March 16, 2006, ML060760028.

9. Letter from Michael T. Markley, NRC to Mr. J.V. Parrish (EN), "Columbia Generating Station -Request for Relief No. 31SI-08 for the Third 10-Year Inservice Inspection Program Interval (TAC NO. MD7507)," dated December 3, 2008, ML0832202.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 4 of 15 10. Letter from Evangelos Marinos, NRC to Mr. H.L. Sumner, Jr, "Edwin I. Hatch Nuclear Plant, Units 1 And 2 Re: Request for Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) (TAC NOS. MC6532 and MC6533)," dated December 22, 2005, ML053330339.

REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 5 of 15 Table 2 Code Item BWRVIP-75-A Material See Identification Number Description Category Number Category Note Number Mitigation Drawing 10HPCS(1)-4 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-109 1OLPCS(1)-4 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-109 12RFW(1)AC-13 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-108 12RFW(1 )AB-1 1 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-108 12RFW(1)AA-11 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-108 12RFW(1)BF-14 Safe-end to Nozzle B-F B5.10 C 4 MSI P RPV-108 12RFW(1)BE-11 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-108 12RFW(1)BD-11 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-108 12LPCI(1)A-6 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-110 12LPCI(1)B-6 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-110 12LPCI(1)C-6 Safe-end to Nozzle B-F B5.10 C 4 MSIP RPV-110 4JP(NZ)A-1 Safe-end to Nozzle B-F B5.10 C I MSIP RPV-115 4JP(NZ)B-1 Safe-end to Nozzle B-F B5.10 C 1 MSIP RPV-115 24RRC(2)A-1 Safe-end to Nozzle B-F B5.10 C 2 MSIP RPV-105 12RRC(1)-N2A-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2B-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2C-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2D-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2E-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 24RRC(2)B-1 Safe-end to Nozzle B-F B5.10 C 2 MSIP RPV-105 12RRC(1)-N2F-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2G-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2H-6 Safe-end to Nozzle B-F B5.10 C 3 MSIP RPV-106 12RRC(1)-N2J-6 Safe-end to Nozzle B-F B5;10 C 3 MSIP RPV-106 12RRC(1)-N2K-6 Safe-end to Nozzle B-F B5.10 C -3 MSIP RPV-106 10HPCS(1)-3 Safe-end Extension to Safe-end B-J B9.11 A 6 MSIP RPV-109 1OLPCS(1)-3 Safe-end Extension to Safe-end B-J B9.11 A 6 MSIP RPV-109 12RFW(1 )AC-1 1 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12RFW(1 )AB-9 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12RFW(1)AA-9 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12RFW(1)BF-12 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12RFW(1)BE-9 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12RFW(1)BD-9 Safe-end Extension to Safe-end Stub B-J B9.11 A 7 MSIP RPV-108 12LPCI(1)A-5 Safe-end Extension to Safe-end B-J B9.11 A 6 MSIP RPV-110 12LPCI(1)B-5 Safe-end Extension to Safe-end B-J B9.11 A 6 MSIP RPV-110 12LPCI(1)C-5 Safe-end Extension to Safe-end B-J B9.11 A 6 MSIP RPV-110 20RHR(2)-2 Safe-end to Valve B-J B9.11 B 8 IHSI Figure 1 12RHR(1)A-14 Valve to Safe-end B-J B9.11 B 9 IHSI Figure 2 12RHR(1)B-10 Valve to Safe-end B-J B9.11 B 9 IHSI Figure 2 REVISION REQUESTS TO THE THIRD TEN-YEAR INSERVICE INSPECTION PROGRAM FOR COLUMBIA GENERATING STATION Attachment 2 Page 6 of 15 Table 2 Code Item BWRVIP-75-A Material See Identification Number Description Category Number Category Note Number Mitigation Drawing 4JP(NZ)A-2 Safe-end to Fitting B-J B9.11 A 5 MSIP RPV-115 4JP(NZ)B-2 Safe-end to Fitting B-J 1B9.11 A 5 MSIP RPV-115 4RRC(4)A-1 1 Safe-end to Valve B-J 1B9.11 B 10 IHSI Figure 3 4RRC(4)B-12 Safe-end to Valve B-J 1B9.11 B 10 IHSI Figure 3 Abbreviations HPCS -High Pressure Core Spray IHSI -Induction Heating Stress Improvement JP -Jet Pump LPCI -Low Pressure Core Injection LPCS -Low Pressure Core Spray MSIP -Mechanical Stress Improvement Process NZ -Nozzle RFW -Reactor Feed water RHR -Residual Heat Removal RRC -Reactor Recirculation Notes 1) SA 508 Cl 2 nozzle, buttered with Inconel 182 weld metal, welded to 336 F8 (0.025 C) Safe end with Inconel 82 weld metal 2) SA 508 Cl 2 nozzle, buttered with Inconel 182 weld metal. Post weld heat treated. Welded to SA 336 F8 Safe end (with 0.020 carbon content) with Inconel 82 weld metal for root/hot pass and Inconel 182 for balance.3) SA 508 Cl 2 nozzle, buttered with Inconel 182. Original Inconel 600 safe-end removed. New 316L safe end with Inconel 182 butter on the nozzle side of the safe end welded to original Inconel 182 buttering with Inconel 82 weld metal for the butt weld. Original Inconel 182 buttering with Inconel 82 weld metal for the butt weld.4) Inconel 182 buttering on safe end welded to Inconel 600 SE with Inconel 182 weld metal root/hot pass and Inconel 182 for balance.5) SA 336 F8 Safe end with 0.025 % carbon 6) Inconel 600 safe end welded to carbon steel safe end extension with Inconel 82 weld material exposed to the fluid media.7) Inconel,600 safe end, stub, and carbon steel safe end extension welded with Inconel 82 weld material exposed to the fluid media.8) Valve body SA-352 welded to SA-182 F316 transition pipe (safe end) with SFA 5.4 filler material.9) Valve body SA-350 welded to SA-182 F304 transition pipe (safe end) with SFA 5.4 filler material.10) Valve body SA-350 welded to SA-182 F316 transition pipe (safe end) with SFA 5.1 and SFA 5.4 filler material.

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--p--- 0 o ~0 5/4-,9 PVn 0 )(i')R#2 P (?#-, -"n to-I m%m4 CD 0<OD z,'0(1M m zm 0 j ma 0m 0 c 0>z-I VALVE DIMENSION TA IS12f -tm i C D E i z .ý44 1.26 .94 3-5 m I WELD EN.4D D, ý'M VALVE END AA INLET iI1"34 oUrLET- 1-507 c 0 0 CD~CD 0 r, m z m-Iýz 0 z-n CA)m 0 m 0 Cl Clo--I 0-4 m m 2<Cl)m Cl)0 z I 2 3 4 5 6 7 B 9 10 CD 0 01-4.C, CD 15" WELDS5 INCONEL 182 BLITTERI 24RRC(2)B,-2 LOOP A LOOP B 150: LOOP A O LOOP B 180" O" LOOP A LOOP B 7115" SAFE-END WELD DETAIL NOZZLE WELD DETAIL NOTES CAL BLCK EXAMINATIN 3/16'0 0 0 0 0 UT-11g UT-101 UT-?UT-101 UT-119 NOZZLE 7D SHELL WELD NOZZLE 7D SAFE-END WELD SAFE-END TO PIPE WELD SAFE-END FORGING (IF EXAIINED)NOZZLE INNER RADIUS 0 <m)Om>0(1_rn 0m zma 0-mr 0 m m-I 02 z 1.140 J '_S CLI PIPE/2 1/8'S 11l/16" REFERENCES, CBI NUCLEAR Co. 205 AE 023 SHT 45 REV 4 NI NOZZLE FORGINO SHT 4? REV 3 NI SAFE-END FOREINO SHT 48 REV 4 Ni NOZZLE ASSEMBLY ISI I50IETRICS RRC-101-i REV 4 RRC-102-1 REV 3 o 1 2 3 4 5 B ? N S i0 I I S£ALE, 1/4" : 1°'TH]S DRAMIN6 15 FOA USE IN PR'ESERVICE AND INSPeCTIOnS OM.T.DUALITY CLASS, 1 I ASKS CODE CLASS. 1_______ _________

NOZZLE SCALE, 1/4'='-____________ -THIS DRAWING IS INTENDED5 FOR LSE IN PRESERVICE AND INSERVICE INSPEC71OKS PROGRAMSA MYL.ENMB, 7 HOYLE I DRAWN. C-RA I DATE, S-TO-R SENERGY COLUMBIA NORTHWEST GENERATING Pepla.Vbon.-Sokaundm STATION PIPING SYSTEM il IA H I MALL NIA*ERIAL P iwT CAL INCH THICKNESS TYPEJ eBER WMELD 9 COMPONENT 24"1RC02)-4S 24 XXX 1.140 1SA 3W8 ER 3D4 CL 1 SS SEE NOTES IENTIFICA7ION DIAGRAII SAFE-END_ _ I --ISA 3l3 CL F8 S:E NOTES TITLE, 2 5 REVISED LDrC JL DPR TIC MIi NOZZLE ,*. SAO 50CL2 CS ISEENOTES RECIRC SUCTION UPDA in 70 Q R PI t pc;r, FF IdriT a I-31-7 SSUED FOR LSE K-__A _ LF_ ONG No, R V-_1_05 REV 2 No DATE REVISION BY CID on I[

I 2 3 4 5 6 7 B g 10.0.060,-7 5. 0 7 5 " \NOTES CAL BLOCK EXAMINATION UT-119 NOZZLE TO SHELL HELD LIT-iIl NOZZLE TO SAFE-END WELD LrT-19 SAFE-END TO PIPE HELD ULT-1II SAFE-END FORGING (IF EXAI]NEDD UT-119 NOZZLE INNER RADIUL CD (0 SAFE-END kWELDTALL C)CD 1/4, WELDS G N2A 3D LOOP A G 2B 60" LOOP A NOC 90" LOOP A N2D 120" LOOP A N2E 150' LOOP A N2F 210D LOOP B N2G 240: LOOP B N2H 270D LOOP B N2J 300" LOOP B N2K 330' LOOP B I2RRC Il)-N2A- LOOP A T2RRC (1)-N28-E LOOP A T2RRC )-N2C-6 LOOP A T2RRC r)-N20-E LOOP A 12RRCEI)-N2E-6 LOOP A 12RRC(l)-N2F-R LOOP B 12RRC 'I)-N2(-6 LOOP B 12RRC 1)-N211-6 LOOP B 12RRC r1)-N2J-5 LOOP B 12RRC I1)-N2K-E LOOP B 12RR p[1)-N2A-4 LOOP A 12RRC I )-N28-4 LOOP A 12R9C 1)-N2C-4 LOOP A 121RCE1)-N20-4 LOOP A 12RRC[1)-N2E-4 LOOP A 12RRC [1)-N2F-4 LOOP B 12R9C[1)-N2G-4 LOOP B 12P9C1l)-N2H-4 LOOP B 12ERC(1)-N2J-4 LOOP B 12RAC(I)-N2K-4 LOOP B REFERENCES, CBI NUCLEAR CO. 205 AE 023 SHT 49 REV 5 N2 NOZZLE FORGING SHT 52 REV 10 N2 NOZZLE ASSEMBLY GE / NED 112 D 2704 REV 1 SAFE-END RECIRC INLET NOZZLE 112 D 2593 REV OTHERMAL SLEEVE EXTENSION I51 ISOMETRICS RRC-1D1-4 REV 2 RRC-101-5 REV 2 RRC-101-6 REV 2 RRC-IO1-l REV 2 RRC-IDl-B REV 2 RRC-102-4 REV 2 RRC-102-S REV 2 RRC-I02-6 REV 2 RRC-102-lT REV 2 RRC-102-8 REV 2 QUALITY CLASS, I ASME CODE CLASS. I ENGR, I HOYLE I ,RA,,. K-.c, I DATE, 5-11-9 0<0(/o M 0zm 0zcn 0 m Z -I m 0 rz NOZZLE WELD DETAIL/0. 604'01 234 5 8 9 10 SCALE, 1/4" 1*THIS DRAWING IS INTENDED FR USE IN PRESERVICE AND INSERV]CE INSPECTIONS ON4LY.ENERGY COLUMBIA NORTHWEST GENERATING Pmm.opVklwm'SokMfiu STATION PIPING SYSTEM ff. DIA MC D ALL MAIL CAL"H MAERIALSPECBLOCK SCCINCH THICKNESS I TYPE NU.5ER HELD E COMPONENT QI2'BCE1)-45 12 XXX 0.09 HSA 358 E 4 CL 1 S EE NOTES IDENTIFICATION DIAGRAM r, JIl: I:.1: kJrl 2 s-2s-OH REVSED LO0 JL I5 OR I TV 1 IO2LIZZLE -t SA_ 1 508 _CB 2 CS ISEE NOTES TITLE, RECIRC RETURN W2 NOZZLE AT 30'. 60'. 90'. 120'. 150'.210'. 240o. 300' 2 300" ED To amftrs Df q 7tR 533 £L 10 ?-31-49 ISSUED FOR L K-USEcA H LF8 DGNO, RPV-106I_

_ _V_ _NO DATE REVISION BY CHKO AI ID 1 2 3 5 6 8 9 10 0 0 0 0 0 0 0 NOTES CAL BLOCK EXAMINAT&ION UT-120 NOZZLE TO SHELL MELD UT-1O2 NOZZLE TO SAFE-END MELD UT-1O5 SAFE-END TO SAFE-END STUB MELD UT-106 SAFE-END STUIB ED SAFE-END EXTENSION MELD UT-15 SAFE-END EXTENOION TO PIPE WELD UT-06 SAFE-END FORGING (IF EXAMINED)UT-12D NOZZLE INNER RADIUS WELDS.15, It INCONEL BACKING RING "/\71, / _TFIELD I L UNKNOWN-A55UME INCONEL 182 UiFT n nFTAII u N4 A 150: N4B g90 NIC 30'NED 210 N4E 270°N4F 130" O 12RFMI1)AA-1 12BE WM )AB-1 12RFW IT)AC-I 12RFM I() RD-I 12RFW MI)BE-I 12RFw (1)BP-i.12RFW [1)A -11 12RFW (1) AC-I 12RFM (I1)BO-1I 12RFM N1) BE-11 12RFu (1)P-1: G 12RFu(i)AA-g 12RFM W1 ) AR-9 12RFW (I )AC-1 12RFW I1)BD-9 12RFW(l)BE-9 12RFM WI)BF-1: 12RFNEI1)AA_8 12RFM I)AC-11 12RFP(1)BD-R I 21PM I1) RE-8 12RPM I1) F -I'REFERENCES, CBI NUCLEAR CO.SHT 56 REV 4 SHT 57 REV 4 SIT 58 BEV 2 SHT 59 REV 9 151 ISOMETRICS RFW-101-3 REV RFM-10T-4 REV RFW-101-S REV 1 wM-102-3 REV RfW-102-4 REV RFW-t02-5 REV LINE AA LINE AR LINE AC LINE RD LINE BE LINE BF I LINE AA I LINE AR 3 LINE AC 1 LINE RD I LINE 4 LINE BF 5 LINE AA) LINE AM 2 LINE AC) LINE RO LINE RE 3 LINE BF LINE AA LINE AR I LINE AC LINE RO LINE BE? LINE BF LINE AA LINE AR) LINE AC LINE RD LINE BE I LINE BF 205 AE 023 N4 NOZZLE N4 SAFE-END 2 SAFE-END FORGING N4 THERMAL SLEEVE FORGING N4 NOZZLE ASSEMBLY JmO 0 CD 0 m oz ft =_L 0 z OIMALITY CLASS., 1 I ASME CODE CLASS. 1 NOZZLE INCONEL 182 BALANCE 4" 3 ' 9 7/16' PIPINE SYSTEM INOM DIA I CHM DIT MALL ENS,1 T HEY1.E I DRAWN. K-fEA I DATE. S-18-nB O ENERGY COLUMBIA NORTHWEST GENERATING

• twm STATION THIS DMAWINS 15 INTENDED FOD UIE IN PRIESERVICE AND INSERVICE INSPECTIONS PROGRAMS ONLY.F_ _ I-I 12"RM (l)-4 12 12D LOW0 SAFE-EEC EXTENl10li 12 0.E71 MATERIAL SPEC ] AiL CAL BLOCK SA INO ER R CS SEE NDTES MELD E COMPONENT SA 508 CL 1 CE SEE NOTES IrENTIFICATION DIAGRAM SAFE-END STUS 0.EMI 591,e (600)]N L SEE NDTES 2 5-5-l06 REVIEW L0 A JL OM TIC ISAFE-END 12 1.125 IMS IEA INEL SEE NOTES TITLE, FEEDUATER N4 NOZZLE AT 30'. 90'. 150". 210', 270" E 330'T1 702-E I MMW 7K'1V W E-11 lAND L INFOM6T)IR -AI si Int__I- IShA C E2 STE hATE 2-20-79 15.0 PER S AM I-e Hj LPR MIPV HDt- A luTEM [I 532C MI C I WS 1UEATE NOZZLE_______________

0 ?-31-49 1 II-FCUSFIE jg-fiflA LFII _ _11#1_ SA s CL I O G No, RPV-1O8 l0A NO DATE RVISIOM BYI CICD APVD I SLEEVE SA U TP ES4 I I SEE NATES I

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.... .. ............

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2 3 5 6 7 8 10"0 CD 01 0 016 0 WELDS S4JP(NZ)A-I S4JP(NZ)A-2

0. or"-IT"P)0 0 0 0 0 CAL BLOCK UT-119 NOZZLE TO SHELL WELD UT-1Og NOZZLE TO SAFE-END WELD UT-29 SAFE-END TO FITTING WELD UT-109 SAFE-END FORGING'IF EXAT1INEDI UT-119 NOZZLE INNER RADIUS 0<Om 0(1 m 0zm-1i m z REFERENCES, CRT NULLEAR CD. 2D5 AE 023 SIT 72 REV 2 NE NDZZLE FORGING S,.T ?3 REV 2 NE SAFE-END FORGING SHT 74 REV 2 Ng NOZZLE ASSEMELY DUALITY CLASS, 1 ASE CODE CLASS, I SAFE-END-(0.025X ACTUAL CARBON CONTENT 0 12 3 15R R 6 0 SCALE, 1/4' = I'THIS DRAWINE 15 INTENDED FOR USE IN PRE, RV]CE AND INSERV]CE INSPECTION6 PROGRAMS ONLY.END, T HNYLE I DRAEN. K-VMA I DATE, 10-4-49 O ENERGY COLUMBIA NORTHWEST GENERATING PeapIle*V lia* Sokitawo STATION TC MOM WALL MAEI A IPE MA L CAL PIPING SYSTEM [MO~ DIsA 5 MAL S PE ATL BCAL INCH THICKNESS TiPE NAMRER MELD & COMPONENT SAFE-END !/4 51A TIS CL FE SS SEE NOTES IDENTIFICATION DIAGRAM M NO7ZZLE-I -I IsA SE L 2 SEE NOTES H 2 5-25-09 REVISED LDGO JL G1R TC fpv 9 ?711 SA 533 SR B CS !SEE NOTES TITLE, JET PUMP INSTRUENiETATION L IW TION.....

WCIIIO. OJ ICIAA .N9 .... .AT 105 ... .. .. .?-31-T- ISSLED FOR USE I K-MeA I LFB [ _ _ NO, RPV- 1 15 REV 2 No DATE REVISION BY CA'gD APED I