RNP-RA/04-0086, Results of Inspections Conducted in Accordance with the First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors

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Results of Inspections Conducted in Accordance with the First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
ML042100074
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 07/16/2004
From: Baucom C
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-03-009, RNP-RA/04-0086
Download: ML042100074 (46)
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10 CFR 50.4 EA-03-009 Progress Energy Serial: RNP-RA/04-0086 JUL 1 6 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 RESULTS OF INSPECTIONS CONDUCTED IN ACCORDANCE WITH THE FIRST REVISED ORDER ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Ladies and Gentlemen:

Inspections in accordance with the NRC's First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (EA-03-009) were completed during the most recent refueling outage, designated as RO-22, at H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. Inspections in accordance with Sections IV.C and IV.D of the Order were satisfactorily completed.

The results of these inspections are provided in the attachments to this letter. In accordance with Section IV.E of the Order, these results are being provided within 60 days of the completion of the refueling outage, which ended on May 28, 2004.

If you have any questions concerning this matter, please contact me.

Sincerely, 642sm-C. T. Baucom Supervisor - Licensing/Regulatory Programs CTB/cac Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

't'-) 0

U.S. Nuclear Regulatory Commission Serial: RNP-RA/04-0086 Page 2 of 2 Attachments:

1. Results of Inspections Conducted in Accordance with the First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors II. Westinghouse Reactor Vessel Head Penetration Examination Final Report C: Dr. W. D. Travers, NRC, Region II Mr. C. P. Patel, NRC NRC Resident Inspector

U.S. Nuclear Regulatory Commission Attachment Ito Serial: RNP-RA/04-0086 Page 1 of 3 II. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RESULTS OF INSPECTIONS CONDUCTED IN ACCORDANCE WITH THE FIRST REVISED ORDER ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS Background and Introduction H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, is a 3-loop Westinghouse-designed Nuclear Steam Supply System Pressurized Water Reactor, which is licensed to operate at 2339 Megawatts-thermal. The original operating license was issued July 31, 1970. Inspections in accordance with the NRC's First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel (RPV) Heads at Pressurized Water Reactors (EA-03-009) were completed during the most recent refueling outage, designated as RO-22. Inspections in accordance with Sections IV.C (bare-metal visual, non-destructive ultrasonic and eddy-current examinations) and IV.D (visual inspection) were completed.

In accordance with Section IV.A of the Order, the effective degradation years (EDY) for the HBRSEP, Unit No. 2, RPV head were calculated. The results of that calculation estimated the EDY for the end of the operating cycle that preceded RO-22 as 21.69. This places HBRSEP, Unit No. 2, in the "High" category of primary water stress corrosion cracking (PWSCC) susceptibility, in accordance with Section IV.B of the Order.

Section IV.C.(1) of the Order requires that plants in the "High" category inspect the RPV head and vessel head penetration (VHP) nozzles using the techniques of paragraphs IV.C.(5)(a) and IV.C.(5)(b) every refueling outage. Additionally,Section IV.D of the Order requires a visual inspection to identify potential boric acid leaks for pressure-retaining components above the RPV head. The inspections and examinations required by the Order were completed during RO-22. The results of these inspections and examinations revealed no active leaks or degradation of the HBRSEP, Unit No. 2, RPV head.

As stated in response to NRC Bulletins 2001-01, 2002-01, and 2002-02, the HBRSEP, Unit No. 2, RPV head was previously examined during RO-20 (April 2001) and RO-21 (October 2002). A bare-metal qualified visual examination of the RPV head and VHP nozzles was conducted during RO-20 in April 2001, which pre-dated the August 2001 issuance of NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles." Subsequent to the issuance of NRC Bulletin 2001-01, and as a result of correspondences, teleconferences, and meetings between HBRSEP, Unit No. 2, and the NRC staff, it was concluded that the April 2001 visual examination provided reasonable assurance of the structural integrity of the VHP nozzles until the next scheduled inspection in the fall of 2002 (Reference TAC No. MB2654).

U.S. Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/04-0086 Page 2 of 3 On December 13, 2002, HBRSEP, Unit No. 2, submitted the results of RPV head and VHP nozzle inspections completed in November 2002 as part of RO-21. That submittal and the associated RO-21 inspections were in accordance with the HBRSEP, Unit No. 2, responses to NRC Bulletin 2001-01, and NRC Bulletin 2002-02, "Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs." Inspections performed during RO-21 included a bare-metal qualified visual examination of the RPV head surface, which was a visual examination for evidence of leakage 360° around each nozzle-head intersection and non-destructive examination (NDE) of the VHP nozzles. As described within the December 13, 2002, submittal, the scope of the NDE for these examinations included:

  • Eddy current examinations of the 69 J-groove welds and penetration tube outer diameter (OD) surfaces,
  • Eddy current and ultrasonic examinations of the seventeen open penetration tubes from the penetration tube inner diameter (ID) surfaces, and
  • Eddy current examinations of 45 penetration tubes with thermal sleeves and seven penetration tubes with part length drive shafts from the penetration tube ID surfaces.

The RO-21 bare-metal qualified visual examination of the RPV head and VHP nozzles did not identify evidence of VHP nozzle leakage or PWSCC-induced cracking. Additionally, the NDE of the RPV head penetrations found no evidence of service-related degradation. One recordable indication was identified that did not require repair. An engineering analysis of that indication has been completed, and the crack growth model associated with that analysis shows the applied stress intensity factor for the indication to be below the threshold for crack propagation. The engineering analysis further concluded that the indication is most likely a scratch or other surface anomaly resulting from the manufacturing process, and there is no concern for this indication during future service (Reference TAC No. MB5916).

The results of the examinations and inspections conducted during the past three refueling outages (RO-20, 21, and 22) provide adequate assurance of the integrity of the HBRSEP, Unit No. 2, RPV head and VHP nozzles. Even in light of these results, Carolina Power and Light Company, now doing business as Progress Energy Carolinas, Inc., plans to replace the RPV head during the next refueling outage, which is scheduled for the fall of 2005. This replacement was deemed necessary due to the burden associated with the required examinations for a plant in the "High" susceptibility category.

Results of RO-22 Inspections and Examinations The RO-22 inspections and examinations were conducted in accordance with the Order requirements, which are summarized as follows:

  • Order Section IV.C.(5)(a) requires bare-metal visual examination of the RPV head surface.
  • Order Section IV.C.(5)(b) requires non-visual NDE of the VHP nozzles.

U.S. Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/04-0086 Page 3 of 3

  • Order Section IV.D requires visual inspection for boric acid leaks from pressure-retaining components above the RPV head.

These inspections and examinations were conducted during RO-22 in April and May of 2004.

The bare-metal visual examination and visual inspection of the components above the RPV head found no evidence of active leakage and no significant degradation. A boric acid film was found on two penetrations (Penetration Nos. 30 and 50) above the RPV head. This boric acid residue was determined to be attributable to RPV head penetration canopy seal weld leaks that had occurred during a previous operating cycle, and repairs were completed during the previous refueling outage (RO-21) to correct these leaks. No boric acid residue was observed on the RPV head insulation at these locations.

The non-visual NDE of the VHP nozzles was performed by Westinghouse Electric Company -

Nuclear Services. These examinations were completed using ultrasonic examination, eddy current examination, and combinations of these two techniques on individual penetrations. Attachment II provides a detailed report of these RO-22 examinations. This Westinghouse report concludes that the results from the time-of-flight diffraction (TOFD) ultrasonic and eddy current examinations of the 69 RPV head penetrations identified no indications that are characteristic of PWSCC.

Conclusion Inspections and examinations in accordance with the First Revised Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (EA-03-009) were completed during the most recent refueling outage (RO-22) at HBRSEP, Unit No. 2. These examinations found no indications of PWSCC, active leakage, or material wastage of the RPV head and VHP nozzles.

U.S. Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/04-0086 41 Pages (including cover page)

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 WESTINGHOUSE REACTOR VESSEL HEAD PENETRATION EXAMINATION FINAL REPORT

H.B. Robinson Unit 2 Westinghouse Reactor Vessel Head Penetration Examination H.B. Robinson Unit 2-RO22 Reactor Vessel Head Penetration Examination May 2004 Final Report 1302612-04, Rev. 0 May 27, 2004 Westinghouse Electric Company Nuclear Services Waltz Mill Service Center P.O. Box 158 Madison, Pennsylvania 15663 USA Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 4ftWestinghouse Reactor Vessel Head Penetration Examination Table of Contents Volume I Examination Summary 1.0 Introduction 2.0 Scope of Work 2.1 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations 2.2 Gapscanner Penetration Tube ID Surface Trinity Probe Examinations 2.3 Gapscanner Penetration Tube ID Surface Eddy Current Examinations 2.4 J-Weld and Penetration Tube OD Surface Eddy Current Examinations 3.0 Examination Results 3.1 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations 3.2 Gapscanner Penetration Tube ID Surface Trinity Probe Examinations 3.3 Gapscanner Penetration Tube ID Surface Eddy Current Examinations 3.4 J-Weld and Penetration Tube OD Surface Eddy Current Examinations 4.0 Examination Coverage 5.0 Discussion of Results 6.0 References Appendix A Westinghouse Letter #PGN-04-33; Alexander to Caba, Progress Energy H.B.

Robinson RVH Penetration Stress Distributions", dated April 21, 2004 Appendix B: H.B. Robinson Unit 2 RVHP Examination Coverage Summary Procedures Personnel Certifications Volume 2 Examination Results Volume 3 Calibration Data Data Disks 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations- Spring 2004 Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

'-')WstingousePage 3 of 40 I( Westinghouse Reactor Vessel Head Penetration Examination

1. H.B. Robinson Unit 2 7010 OHS Data, Disk 1 of 1- Penetrations
  1. 2,3,4,5,11,46,47,48,49,50,51,52,53,54,55,56, & 57 Gapscanner Penetration Tube IDSurface Trinity Probe Examinations - Spring 2004
1. H.B. Robinson Unit 2 Trinity Probe, Disk 1 of 7- Penetrations
  1. 1,6,7,8,9,10,12,13,14,15,16,17,18,19,20,21,22,25,28,29,30,31,34,35,36,37,38,41,42,43,44,45

,58,59,60,61,62,66 & 67 Gapscanner Penetration Tube ID Eddy Current Examinations - Spring 2004

1. H.B. Robinson Unit 2 Gapscanner ECT Probe & Cal, Disk 1 of 1 - Penetrations
  1. 15,23,24,26,27,30,32,33,35,37,39,40,63,64,65,68, & 69 J-Weld and Penetration Tube OD Surface Eddy Current Examinations - Spring 2004
1. H.B. Robinson 2 Grooveman Data, Disk 1 of 1 - Penetrations
  1. 15,23,24,26,27,30,32,33,35,37,38,39,40,43,44,60,61,62,63,64,65,66,67,68 &69 with calibrations Calibration Data - Spring 2004
1. Calibration Data 7010 Probe, Disk 1 of 1
2. Calibration Data Trinity Probe, Disk I of 1 Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 MWestinghouse Reactor Vessel Head Penetration Examination

1.0 INTRODUCTION

During the H.B. Robinson Unit 2 R022 outage in the Spring of 2004, Westinghouse performed nondestructive examinations (NDE) of the sixty-nine control rod drive mechanism (CRDM) penetration tubes in the reactor vessel head.

The purpose of the examination program was to identify evidence of primary water stress corrosion cracking (PWSCC) that might be present on the outside diameter (OD) and inside diameter (ID) surfaces of the head penetration tubes and to assess whether leakage might have might have occurred into annulus at the tube-to-head interface. Examinations were performed using procedures and techniques demonstrated through the EPRI/MRP protocol [1], and/or Westinghouse internal demonstration programs, and applied consistent with the requirements of the February 20, 2004, First Revision to USNRC Order EA-03-009, 'Establishing Interim Inspection Requirements for Reactor Vessel Heads at Pressurized Water Reactors".

The Robinson reactor vessel head is a Westinghouse design and manufactured by Combustion Engineering (CE). The head contains sixty-nine alloy 600 penetration tubes that are shrunk fit into the reactor vessel head and attached with alloy 182/82 partial penetration J-groove welds.

All CRDM penetration tubes in the H.B. Robinson Unit 2 reactor vessel head were manufactured from heats of material supplied by Huntington Alloys. To date, penetrations manufactured from Huntington material have exhibited better resistance to PWSCC than those manufactured from material supplied by B&W tubular products.

Locations of heats of Huntington material in the H.B. Robinson Unit 2 head are identified in Table 1-1, below.

Table 1-1: Penetration Location and Associated Heat Number Yield Ultimate Yield Ultimate Penetration Heat No. (psi) (psi) Penetration Heat No. (PsI) (Psi)

I NX1474 53 94 18 NX1872 57.5 91 2 NX1474 53 94 19 NX0399 41.5 94 3 NX0139 36 93 20 NX1872 57.5 91 4 NX1474 53 94 21 NX1872 57.5 91 5 NX1474 53 94 22 NX0399 41.5 94 6 NX1 872 57.5 91 23 NX0399 41.5 94 7 NX1 872 57.5 91 24 NX0399 41.5 94 8 NX1872 57.5 91 25 NX0399 41.5 94 9 NX1872 57.5 91 26 NX0399 41.5 94 10 NX1872 57.5 91 27 NX0399 41.5 94 11 NX1872 57.5 91 28 NX0139 36 93 12 NX1872 57.5 91 29 NX0399 41.5 94 13 NX1872 57.5 91 30 NX0399 41.5 94 14 NX1872 57.5 91 31 NX0399 41.5 94 15 NX1872 57.5 91 32 NX5981 35.5 91.5 16 NX0399 41.5 94 33 NX0399 41.5 94 17 NX0399 41.5 94 34 NX0399 41.5 94 Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 OWestinghouse Reactor Vessel Head Penetration Examination Yield Ultimate Yield Ultimate Penetration Heat No. (psi) (psi) Penetration Heat No. (psi) (psi) 35 NX0399 41.5 94 53 NX4277 36.5 91 36 NX0399 41.5 94 54 NX1527 47.5 95.5 37 NX0399 41.5 94 55 NXI 527 47.5 95.5 38 NX1474 53 94 56 NX1527 47.5 95.5 39 NX5983 36 88 57 NX1 527 47.5 95.5 40 NX1474 53 94 58 NX1474 53 94 41 NX1 527 47.5 95.5 59 NX1474 53 94 42 NX1 527 47.5 95.5 60 NX1474 53 94 43 NX1 527 47.5 95.5 61 NX1474 53 94 44 NX1 527 47.5 95.5 62 NX1474 53 94 45 NX1 527 47.5 95.5 63 NX1474 53 94 46 NX0139 36 93 64 NX1474 53 94 47 NX1 527 47.5 95.5 65 NX1474 53 94 48 NX1527 47.5 95.5 66 NX1474 53 94 49 NX1527 47.5 95.5 67 NX0400 49.5 92.5 50 NX1474 53 94 68 NX1474 53 94 51 NX1474 53 94 69 NX0400 49.5 92.5 52 NX1 527 47.5 95.5 Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

-')Westinghouse Reactor Vessel Head Penetration Examination Page 6 of There are a variety of configurations for the sixty-nine penetration tubes, each configuration requiring special consideration for examination. The penetration tubes measure 4.0" on the OD and have an ID dimension of 2.75". The wall thickness is 0.625". The penetration tube configurations are as follows:

  • 17 open penetration tubes
  • 45 penetration tubes with thermal sleeves installed
  • 7 penetration tubes with part length drive shafts The H.B. Robinson Unit 2 reactor vessel head is in the "high susceptibility" category.

For a reactor vessel head in this category,Section IV.C (5)of the first Revision to USNRC Order EA-03-009 [2] specifies:

a) Bare metal visual examination of 100% of the RPV head surface (including 3600 around each RPV head penetration nozzle), and b) For each penetration, perform a nonvisual NDE in accordance with either i, ii or ii,:

i. Ultrasonic testing of each RPV head penetration nozzle volume (i.e., nozzle base material) from two (2)inches above the highest point of the root of the J-groove weld to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis; OR from 2 inches above the highest point of the root of the J-groove weld to 1 inch below the lovkest point at the toe of the J-groove weld and including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level of 20 ksi tension and greater. In addition, an assessment shall be made to determine if leakage has occurred into the annulus between the RPV head penetration nozzle and the RPV head low alloy steel.

ii. Eddy current or dye penetrant testing of the entire wetted surface of the J-groove weld and the wetted surface of the RPV head penetration nozzle base material from at least 2 inches above the highest point of the root of the J-groove weld to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis; OR from 2 inches above the highest point of the root of the J-groove weld to 1inch below the lowest point at the toe of the J-groove weld and including all RPV head penetration nozzle surfaces below the J-groove weld that have an operating stress level of 20 ksi tension and greater.

iii. A combination of (i) and (ii) to cover equivalent volumes, surfaces and leak paths of the RPV head penetration nozzle base material and J-groove welds described in (i) and (ii).

... shall be performed at least once over the course of every refueling outage.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 if Westinghouse Reactor Vessel Head Penetration Examination The examination program selected for H.B. Robinson Unit 2 included ultrasonic examinations of the 69 CRDM penetration nozzles with leakage assessment in accordance with Section IV.C (5) (b) (i) of the Revised NRC Order.

Stress distribution curves were developed in advance of the examination which demonstrated that hoop stresses on the OD surfaces of the tubes are less than 20 ksi within 1.0" below the lowest point of the toe of the J-groove weld [3], thus the examination coverage required for all penetration locations was from 2 inches above the highest point of the root of the J-groove weld to 1 inch below the lowest point at the toe of the J-groove weld. The stress distribution curves are attached as Appendix A.

Contingency plans were in place to address the possibility that geometric conditions at certain penetration locations, including asymmetry of the penetration tubes due to weld distortion and "short tubes" below the J-groove welds, might result in an inability achieve the examination coverage specified in the Revised NRC Order. Contingencies included equipment and procedures necessary to: 1) perform wetted surface examinations in accordance with Section IV.C (5) (b) (ii) of the Revised Order using eddy current blade probes, which are thinner that the Trinity blade probes, on the tube ID surfaces supplemented by eddy current examinations of the associated J-groove welds and tube OD surfaces with the Grooveman end effector, and/or 2) use a combination of ultrasonic and eddy current techniques to satisfy the Revised Order in accordance with Section IV.C (5) (b) (iii). It was necessary to implement contingency inspections at twenty-five penetration locations. At seventeen locations tube asymmetry would not allow the Trinity probes to pass freely in the annulus between the penetration tubes and thermal sleeves, thus wetted surface eddy current examinations were performed. At eight locations, it was not possible to achieve 1.0" of examination coverage below the toe of the J-groove welds on the tube OD surfaces with TOFD-UT and supplementary eddy current examinations were performed.

The following Westinghouse field service procedures and associated field change notices (FCNs) were approved for use at H.B. Robinson Unit 2.

  • WDI-ET-002, Rev. 4 and FCN 01 -"Eddy Current Inspection of J-Groove Welds in Vessel Head Penetrations"
  • WDI-ET-003, Rev. 6 and FCNs 01 and 02-"lntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations"
  • WDI-ET-004, Rev. 5 and FCNs 01 and 02- "IntraSpect Eddy Current Analysis Guidelines Inspection of Reactor Vessel Head Penetrations"
  • WDI-ET-008, Rev. 3 and FCN "IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations With Gap Scanner"
  • WDI-UT-010, Rev 7 and FCIs 01, 02 and 03 - "IntraSpect Ultrasonic Procedure for Inspection of Reactor Vessel Head Penetrations, Time of Flight Ultrasonic &

Longitudinal Wave" Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 (a Westinghouse Reactor Vessel Head Penetration Examination

  • WDI-UT-013, Rev. 5 and FCNs 01 and 02 -"CRDM/ICI UT Analysis Guidelines"
  • WCAL-002, Rev. 3 - "Pulser/Receiver Linearity Procedure" The vessel head penetrations were dispositioned based on an assessment of results from the nondestructive examinations presented herein and results from visual examinations performed from the top of the reactor vessel head.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 (tWestinghouse Reactor Vessel Head Penetration Examination 2.0 SCOPE OF WORK The reactor vessel head penetration nondestructive examination scope at H.B. Robinson Unit 2 included all sixty-nine CRDM penetration tubes.

The examination methodology selected for each penetration was dependent upon the penetration tube configuration and penetration-specific geometric conditions. Refer to Appendix B for penetration-specific details.

1. Seventeen penetration tubes without thermal sleeves were examined from the ID using the Westinghouse 7010 Open Housing Scanner (OHS).
2. Thirty-five penetrations, twenty-eight with thermal sleeves and seven part length locations, were examined from the ID using the Westinghouse Gapscanner and Trinity blade probes.
3. Due to the combination of probe design and penetration geometry, it was not possible to achieve 1.0" of examination coverage below the lowest portion of the J-groove welds on the OD surfaces of eight of the thirty-five locations identified in 2, above, using time-of-flight diffraction ultrasonic testing (TOFD UT) techniques with the Trinity blade probes. For these eight locations, TOFD UT coverage below the weld varied from 0.6" to 0.96". The penetration tube OD surfaces at these locations were examined using eddy current techniques with the Grooveman end effector to achieve at least 1.0" of examination coverage below the lowest elevation of the J-groove weld.
4. The examination program for seventeen penetration tubes containing thermal sleeves was changed from the Trinity blade probes to the eddy current probes, which are slightly thinner, because the sizes of the gaps between the OD of the thermal sleeves and the ID of the penetration tubes varied around the circumference and the Trinity probes would not pass freely in the annulus. This asymmetric condition appears to be a result of distortion of the penetration tubes due to welding.

These seventeen penetration tubes were inspected from the ID using the Westinghouse Gapscanner and dual-pancake eddy current blade probes. The J-groove welds and penetration tube OD surfaces at these locations were also examined using eddy current techniques with the Grooveman end effector.

The delivery system used for the CRDM examinations at H.B. Robinson Unit 2 was the Westinghouse DERI 700 manipulator.

The DERI 700 is a multi-purpose robot that can access all head penetrations and provides a common platform for all CRDM examination end effectors. The manipulator consists of a central leg, mounted on a carriage, which in turn is mounted onto a guide rail. The manipulator arm, with elbow and removable wrist, is mounted onto the carriage, which travels vertically along the manipulator leg.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 IM)Westinghouse Reactor Vessel Head Penetration Examination Page 10 d The DERI 700 was used to deliver 1) the Westinghouse 7010 Open Housing Scanner for ultrasonic and supplementary eddy current examinations of open penetration locations,

2) the Westinghouse Gapscanner end effector for Trinity probe examinations of penetration locations containing thermal sleeves and part length locations, 3) the Westinghouse Gapscanner for eddy current blade probe examinations where access was inadequate for the Trinity probes, and 4) the Grooveman end effector when required for eddy current examinations of the J-groove welds and/or penetration tube OD surfaces.

The Westinghouse 7010 Open Housing Scanner delivers an examination wand containing ultrasonic and eddy current probes to the ID surface of open reactor vessel head penetrations. The scanning motion is in a vertical direction moving from a specified height above the weld, in this case at least 2.0", to the bottom of each penetration. The probe is indexed in the circumferential direction. With the open housing scanner, multiple examination probes are delivered simultaneously. These include time-of-flight diffraction ultrasonic probes oriented in the axial and circumferential directions, straight beam ultrasonic probes to identify variations in the penetration tube-to-reactor vessel head shrink fit area that might indicate a leak path in the annulus between the tube and the head, and supplementary eddy current probes for identification of circumferential and axial degradation on the ID surfaces of the penetration tubes The Gapscanner end effector delivers either Trinity blade probes or eddy current blade probes into the annulus between the ID surface of the head penetration tube and the OD surface of the thermal sleeve or part length drive shaft. The typical annulus size is 0.125". The Trinity probes include a crosswound eddy current coil, a TOFD UT transducer pair and a 00 ultrasonic transducer. The eddy current blade probes use a dual pancake coil arrangement. Both probe designs feature a flexible metal "blade" on which ultrasonic and/or eddy current probes are mounted in a spring configuration that enables the probes to ride on the ID surface of the penetration tubes. The scanning motion is in a vertical direction moving from a specified height above the weld, in this case at least 2.0",

to the bottom of each penetration. The probes are indexed in the circumferential direction.

The Grooveman manipulator is designed to deliver crosswound eddy current probes for examination of the surface of the J-groove weld and the penetration nozzle OD surfaces.

The eddy current probe holders are designed to conform to the geometry of the J-groove welds and penetration OD surfaces and allow the probes to follow the contour of the assembly. Continuous positional and video feedback is provided to the operator to assist in achieving coverage of the weld and the penetration tube. Scanning of the penetration tube OD surface is conducted in a vertical direction and the probes are indexed in the circumferential direction. For scanning of the J-groove welds, scanning is conducted in the circumferential direction, along the weld, and the index is in a direction perpendicular to the weld.

2.1 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations 7010 Open Housing Scanner examinations were conducted on seventeen reactor vessel head penetrations without thermal sleeves.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 ftWestinghouse Reactor Vessel Head Penetration Examination Page 11 of 40 Examinations of these vessel head penetrations included:

1. TOED ultrasonic techniques demonstrated capable of detecting axial and circumferential degradation on the penetration tube OD and ID surfaces with PCS24 probes in accordance with WDI-UT-010, Rev. 7 and FCNs 01, 02 and 03

- "IntraSpect Ultrasonic Procedure for Inspection of Reactor Vessel Head Penetrations, Time of Flight Ultrasonic Longitudinal Wave" & Shear Wave",

2. straight beam ultrasonic techniques to identify possible leak paths in the shrink fit region between the head penetrations and the reactor vessel head, also in accordance with WDI-UT-010, Rev. 7 and associated FCNs, and
3. supplementary eddy current examinations demonstrated capable of detecting axial and circumferential degradation on the penetration tube ID surfaces in accordance with and WDI-ET-003, Rev. 6 and FCNs 01 and 02 - "IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations".

2.2 Gapscanner Penetration Tube ID Surface Trinity Probe Examinations Examinations were performed with the Gapscanner end effector and Trinity probes on thirty-five penetration tubes, twenty-eight with thermal sleeves and seven part length locations, from the penetration ID surfaces. These thirty-five penetration tubes were inspected from the ID using Trinity blade probes.

Examinations of these vessel head penetrations included:

1. TOED ultrasonic techniques demonstrated capable of detecting axial and circumferential degradation on the penetration tube OD and ID surfaces with PCS24 probes in accordance with WDI-UT-010, Rev. 7 and FCNs 01, 02 and 03

- "IntraSpect Ultrasonic Procedure for Inspection of Reactor Vessel Head Penetrations, Time of Flight Ultrasonic Longitudinal Wave" & Shear Wave",

2. straight beam ultrasonic techniques to identify possible leak paths in the shrink fit region between the head penetrations and the reactor vessel head, also in accordance with WDI-UT-010, Rev. 7 and associated FCNs, and
3. supplementary eddy current examinations demonstrated capable of detecting axial and circumferential degradation on the penetration tube ID surfaces in accordance with and WDI-ET-003, Rev. 6 and FCNs 01 and 02 - "IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations".

2.3 Gapscanner Penetration Tube ID Surface Eddy Current Examinations Gapscanner eddy current examinations were conducted on the remaining seventeen reactor vessel head penetration where the sizes of the gaps between the OD of the Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O Westinghouse Reactor Vessel Head Penetration Examination Page 12 o thermal sleeves and the ID of the penetration tubes varied around the circumference and the Trinity probes would not pass freely in the annulus. Eddy current blade probes with dual pancake eddy current coils were used to examine the tube ID surfaces. These examinations were applied to identify the presence of primary water stress corrosion cracking (PWSCC) on the inside diameter surfaces of the penetration tubes.

Examinations were conducted in accordance with WDI-ET-008, Rev. 3 and FCN 01 -

"IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations With Gap Scanner".

The J-groove welds and penetration tube OD surfaces at these locations were also examined using eddy current techniques with the Grooveman end effector.

2.4 J-Weld and Penetration Tube OD Surface Eddy Current Examinations Eddy current examinations were performed on the J-groove welds and outside diameter surfaces of seventeen reactor vessel head penetration tubes to supplement the Gapscanner ID eddy current examinations. The Grooveman end effector delivers crosswound eddy current coils to identify the presence of primary water stress corrosion cracking on the outside diameter surfaces of penetration tubes and on the surfaces of the J-groove welds attaching the penetrations to the reactor vessel head. Examinations were conducted in accordance with WDI-ET-002, Rev. 4 and FCN 01 - "IntraSpect Eddy Current Inspection of J-Groove Welds in Vessel Head Penetrations".

In addition, Grooveman eddy current examinations were conducted on the outside diameter surfaces of eight reactor vessel head penetration tubes where it was not possible to achieve 1.0" of examination coverage on the tube OD surface using TOED techniques with the Trinity Probes.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 OWestinghouse Reactor Vessel Head Penetration Examination 3.0 EXAMINATION RESULTS 3.1 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations Table 3-1 provides a summary of results from the 7010 Open Housing Scanner reactor vessel head penetration nondestructive examinations performed at H.B. Robinson Unit 2 during the RO22 refueling outage.

Table 3-1: Open Housing Scanner Examination Results Penetration # Axial TOFD Circ TOFD 2.25 5.0 Mhz Supplementary Channel 1 Channel 2 Mhz 00 00 Tube ID ECT 2 NDD NDD NDD NDD CC/NDD 3 NDD NDD NDD NDD NDD 4 NDD NDD NDD NDD CCINDD 5 NDD NDD NDD NDD NDD 11 NDD NDD NDD NDD NDD 46 NDD NDD NDD NDD NDD 47 NDD NDD NDD NDD CCINDD 48 NDD NDD NDD NDD NDD 49 NDD NDD NDD NDD CCINDD 50 NDD NDD NDD NDD CCINDD 51 NDD NDD NDD NDD CCINDD 52 NDD NDD NDD NDD CCINDD 53 NDD NDD NDD NDD CC/NDD 54 NDD NDD NDD NDD CC/NDD 55 NDD NDD NDD NDD CC/NDD 56 NDD NDD NDD NDD NDD 57 NDD NDD NDD NDD NDD Legend NDD: No Detectable Degradation CC: Craze Cracking No detectable degradation characteristic of PWSCC was reported in any of the penetration tubes examined with the 7010 Open Housing Scanner. There was no evidence of leakage in the annulus between the penetration nozzles and the reactor vessel head. Supplementary eddy current examinations showed evidence of craze cracking on the ID surfaces of ten penetration tubes. All were confirmed by historical data from the Fall 2002 examination and there was no change in size. None were visible in the ultrasonic data; i.e., there was no evidence of craze cracking in the TOFD UT results.

3.2 Gapscanner Penetration Tube ID Surface Trinity Probe Examinations Table 3-2 provides a summary of results from Gapscanner examinations performed with Trinity Probes performed at H.B. Robinson Unit 2 during the R022 May 2004 refueling outage. Penetrations identified as shaded in the table were examined using other Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O Westinghouse Reactor Vessel Head Penetration Examination techniques; i.e., either 1) the Open Housing Scanner or 2) the Gapscanner using eddy current probes supplemented with eddy current examinations of the J-groove weld and penetration tube OD surfaces with the Grooveman end effector.

Table 3-2: Trinity Probe Examination Results Supplementary .

Penetratlon#- PCS24TOFD 0° Leak Path Eddy Current Tube ID I NDD NDD NDD 2.... .

3 .... ._.- _

54 - _

6 NDD NDD CC/NDD 6 NDD NDD NDD 7 NDD NDD CC/NDD 9 NDD NDD CC/NDD 10 NDD NDD NDD 11 _. _.. __....

12 NDD NDD NDD 13 NDD NDD CCINDD 14 NDD NDD CCINDD 15 ....- -

16 NDD NDD NDD 17 NDD NDD NDD 18 NDD NDD NDD 19 NDD NDD NDD 20 NDD NDD NDD 21 NDD NDD NDD 22 NDD NDD NDD 23 -_ _ _ _ _ _ _ _ _ _ _ _ _

24 __ .

25 NDD NDD CCINDD 26 .... _. ._.

27 .... _._ ._._._.

28 NDD NDD NDD 29 NDD NDD NDD 30 .... . ._. . ....

31 NDD NDD NDD 32 --- __ _ __ _ __ _ _

33 --- _._ . . . . __ __ __ .

34 NDD NDD CCINDD 35 .... _.... ....

36 NDD NDD NDD 37 .... __ __

38 NDD NDD NDD 39 .... _- _

40 _-

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 9 Westinghouse Reactor Vessel Head Penetration Examination

- Supplementary Penetration # PCS24 TOFD 00 Leak Path Eddy Current Tube ID 41 NDD NDD NDD 42 NDD NDD NDD 43 NDD NDD CC/NDD 44 NDD NDD CCINDD 45 NDD NDD CC/NDD 46 ... ___. ....

___.... ___=

47 . . .. __ _ _ ... _ _ _ .... _ __ _

48 . . , . . . . . .

49 __ . . . .

50 ._. Ad_

51 .... A_ _

52 __

53 _.

54 ........

55 .... .... ....

56 _.

57 _ ._._....

58 NDD NDD CCINDD 59 NDD NDD CC/NDD 60 NDD NDD NDD 61 NDD NDD CCINDD 62 NDD NDD NDD 63 _... . . . . _

64 _. _.. _ _....

65 _. .. __ _

66 NDD NDD NDD 67 NDD NDD CC/NDD 68 .. . ._ .... _

69 . ... . .. . . - . ...

No detectable degradation characteristic of PWSCC was reported in any of the penetration tubes examined with the Trinity Probes. There was no evidence of leakage in the annulus between the penetration nozzles and the reactor vessel head.

Supplementary eddy current examinations showed evidence of craze cracking on the ID surfaces of fourteen penetration tubes. All were confirmed by historical data from the Fall 2002 examination and there was no increase in size. None were visible in the ultrasonic data; i.e., there was no evidence of craze cracking in the TOFD UT results.

3.3 Gapscanner Penetration Tube ID Surface Eddy Current Examinations Table 3-3 provides a summary of results from Gapscanner examinations performed with eddy current performed at H.B. Robinson Unit 2 during the R022 May 2004 refueling outage.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

'bWestinghouse Reactor Vessel Head Penetration Examination Table 3-3: Gapscanner ID Eddy Current Results Penetration# --- Eddy Current 15 NDD 23 NDD 24 NDD 26 NDD 27 NDD 30 NDD 32 NDD 33 NDD 35 NDD 37 NDD 39 NDD 40 NDD 63 NDD 64 NDD 65 NDD 68 NDD 69 NDD No detectable degradation characteristic of PWSCC was reported in any of the penetration tubes examined with the eddy current blade probes and Gapscanner.

3.4 J-Weld and Penetration Tube OD Surface Eddy Current Examinations The following table provides a summary of results for all J-groove weld and penetration tube OD surface eddy current examinations performed on the Robinson 2 reactor vessel head during the R022 outage.

Examinations of penetrations #15, 23, 24, 26, 27, 30, 32, 33, 35, 37, 39, 40, 63, 64, 65, 68 and 69 were specified when it was discovered that the sizes of the gaps between the OD of the thermal sleeves and the ID of these penetration tubes varied around the circumference and the Trinity probes would not pass freely in the annulus. These examinations covered both the J-groove welds and the penetration tube OD surfaces.

Examinations of penetrations #38, 43, 44, 60, 61, 62, 66 and 67 were specified because the TOFD UT examinations from the inside diameter surfaces were not able to achieve 1.0" of examination coverage below the lowest portion of the J-groove weld on the OD surface due to the combination of probe design and penetration geometry. TOFM UT coverage ranged from 0.6" to 0.96". For these penetrations, the examinations covered only the tube OD surfaces from the lowest elevation of the J-groove weld to at least 1.0" below that elevation.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 Westinghouse Reactor Vessel Head Penetration Examination Table 3-4: Grooveman Eddy Current Results Penetration # J-GWoove Weld Scan l Tube Scan 15 NDD NDD 23 NDD NDD 24 NDD NODD 26 NDD NDD 27 NDD NODD 30 NDD NDD 32 NDD NDD 33 NDD NDD 35 NDD NDD 37 NDD NDD 38 NDD 39 NDD NDD 40 NDD NDD 43 _ NDD 44 ._.__ NDD 60 - NDD 61 NODD 62 NODD 63 NDD NDD 64 NDD NDD 65 NDD NDD 66 . _ NDD 67 NDD 68 NDD NDD 69 NDD NDD No detectable degradation characteristic of PWSCC was reported in any of the J-groove welds or penetration tubes examined with eddy current blade probes and the Grooveman end effector.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 lO Westinghouse Reactor Vessel Head Penetration Examination 4.0 EXAMINATION COVERAGE 4.1 Penetration Tube Configuration and Examination Summary The typical configuration of a sleeved H.B. Robinson Unit 2 CRDM penetration tube is illustrated in Figure 4-1. This figure represents the tube-to-head geometry at the penetration 00 azimuth, or "downhill" side of the tube. The tubes are 0.625" thick and have a 0.188" radius machined at the bottom. The distance from the bottom of the tube to the elevation where the fillet of the J-groove weld intersects the tube (identified as the sum of distances "A" and "0.45" in Figure 1)varies based on location of the penetration in the head. These distances are typically bnger for penetrations at "inboard" locations and become progressively shorter for penetrations located further away from the center of the head. The examination methodology selected for each penetration in order to meet the revised NRC Order was dependent upon the penetration tube configuration and penetration-specific geometric conditions, as described in Sections 4.2, 4.3 and 4.4.

A penetration-specific summary is provided in Appendix B.

Carbon Steel Buttering Thermal Sleeve 1f In Stainless Steel Figure 4-1: Illustration of Axially Oriented TOFD Examination Coverage on H.B.

Robinson Penetration Geometry at 0° (Downhill Side)

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O Westinghouse Reactor Vessel Head Penetration Examination Page 19 of 40 4.2 Ultrasonic Testing Coverage in Accordance With Section IV.C (5) (b) (i) of the Revised NRC Order The ultrasonic method demonstrated through the EPRI/MRP Protocol for detection of circumferential and axial degradation on the OD and ID surfaces of CRDM penetration tubes is the axially-oriented time-of-flight diffraction (TOFD) technique. The TOED technique is a pitch/catch" ultrasonic method, where the signal is transmitted into the tube at an angle by a transmitter (T) and reflects off of the backside of the tube to a receiver (R), as shown in path 1-2 in Figure 4-1. A lateral wave also travels on the tube ID surface between the transmitter and receiver as shown in path 3. The two transducers are mounted on a probe head with a probe center spacing of 0.925". ID TOED coverage is provided by the lateral wave to the bottom of the tube on the ID surface. OD TOFM coverage becomes effective at an elevation of -0.45" from the bottom of the tube.

For ID examinations of the fifty-two penetration tubes performed with the Open Housing Scanner and Trinity blade probes, TOFM PCS24 and supplementary eddy current examination coverage extended from the bottom of each tube to at least 2.0" above the uppermost elevation of the welds. The extent of coverage was verified for each penetration by confirming that: 1) tube entry signals were evident in the eddy current and ultrasonic data, and 2) scan coverage elevations were in excess of 2.0" above the uppermost elevation of each weld. In all cases, ID coverage included at least 1.0" below the lowest elevation of the J-groove welds.

For OD examinations of fifty-two penetration tubes performed with the Open Housing Scanner and Trinity blade probes, the TOFD PCS24 transducer coverage extended from 0.45" above the bottom of each tube to elevations at least 2.0" above the welds. The extent of coverage was verified for each examination of each penetration by confirmation that 1)TOFD tube entry signals were evident ultrasonic data and 2) scan coverage elevations were in excess of 2.0" above the uppermost elevation of each weld. TOED UT coverage obtained for forty-four of the fifty-two tubes included at least 2.0" above the uppermost elevation of the welds and 1.0"' below the lowest elevation of the J-groove welds. This coverage is illustrated in Figure 4-2.

At eight penetration locations it was not possible to achieve 1.0" of TOFD coverage on the penetration tube OD surface below the lowest point of the weld. Supplementary eddy current examinations were performed on the tube OD surface at these eight locations to achieve the required 1.0" of coverage below the welds as described in Section 4.4.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 dWestinghouse Reactor Vessel Head Penetration Examination E UT Coverage Figure 4-2: UT Coverage in Accordance With Section IV.C (5)(b) (i) of the Revised NRC Order 4.3 Eddy Current Coverage in Accordance With Section IV.C (5) (b) (i) of the Revised NRC Order Gapscanner eddy current examinations were conducted on the remaining seventeen reactor vessel head penetration where the sizes of the gaps between the OD of the thermal sleeves and the ID of the penetration tubes varied around the circumference and the Trinity probes would not pass freely in the annulus. Eddy current blade probes with dual pancake eddy current coils were used to examine the tube ID surfaces. The thickness of the eddy current probes, when fully compressed, allows access into gaps on the order of 0.085" as compared to 0.095" for the Trinity probes.

Eddy current examinations were also conducted on the J-groove weld surfaces to a distance of 0.25" past the welds and on the OD surfaces of the penetration tubes using the Grooveman end effector.

Coverage provided by the eddy current examination program is illustrated in Figure 4-3.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 GWestinghouse Reactor Vessel Head Penetration Examination a aaa Eddv Current 1 0

. 9j .

Figure 4-3: Wetted Surface Examination Coverage in Accordance With Section IV.C (5) (b) (ii) of the Revised NRC Order 4.4 Combination Ultrasonic and Eddy Current Coverage in Accordance With Section IV.C (5) (b) (iii) of the Revised NRC Order At eight penetration locations it was not possible to achieve 1.0" of TOFD coverage on the penetration tube OD surface below the lowest point of the weld due to the combination of probe design and penetration geometry. Supplementary eddy current examinations were performed on the tube OD surface at these eight locations to achieve the required 1.0" of coverage below the welds.

For these locations, complementary eddy current examinations were performed on the OD penetration tube surfaces using the Grooveman end effector. These examinations were performed from the elevation where toe of the J-groove weld at its lowest elevation intersects the penetration tube to the bottom of the tube. Since the TOFD UT coverage below the weld at these eight locations varied from 0.6" to 0.96" below the weld, sufficient overlap was accomplished when the upper elevation of the scan was started at the point where weld intersects the tube.

Coverage provided by the combined ultrasonic and eddy current examination program is illustrated in Figure 4-4.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

@)Westinghouse Reactor Vessel Head Penetration Examination 2.0" Alin.

-L E0 UT Coverage Supplementary

<1.0" - ECIr Coverage I-L 0.45" 1r Figure 4-4: Combination UT and ECT Examination Coverage in Accordance With Section IV.C (5) (b) (iii) of the Revised NRC Order Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 tkWestinghouse Reactor Vessel Head Penetration Examination Page 23 of 40 5.0 DISCUSSION OF RESULTS Penetration tube ultrasonic examination data were analyzed in accordance with WDI-UT-013, Rev. 5 with FCNs 01 and 02- "CRDM/ICI UT Analysis Guidelines". Eddy current data were analyzed in accordance with WDI-ET-004, Rev. 5 with FCNs 01 and 02 - "IntraSpect Eddy Current Analysis Guidelines Inspection of Reactor Vessel Head Penetrations". Data from the Fall 2002 Robinson reactor vessel head penetration examinations were loaded on the analysis workstations to allow comparison of the current results with history. The disposition process for ID indications is summarized in the logic chart in Figure 5-1 and the process for OD indications is summarized in the logic chart in Figure 5-2.

Data sheets and printouts of the results of each examination performed on each penetration are found in Volume 2.

Eddy current results from tube inside diameter surface examinations identified twenty-four penetration tubes with indications characteristic of craze cracking. This phenomenon was found typically at the 180 degree location and below the weld. The craze cracking was not detectable with the TOFD ultrasonic probes, indicating the depths of this condition is significantly less than 0.040", the TOFD detection limit. As such, they are not considered to have any impact on the integrity of the reactor vessel head penetration tubes. All were confirmed by review of the historical data from the Fall 2002 reactor vessel head penetration examination and there was no increase in size.

Results from the TOFD ultrasonic and eddy current examinations of the sixty-nine reactor vessel head penetrations identified no indications characteristic of PWSCC.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O)Westinghouse Reactor Vessel Head Penetration Examination Figure 5 Penetration Tube ID Flaw Evaluation Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 Page 25 of 40 b)Westinghouse Reactor Vessel Head Penetration Examination Figure 5 Penetration Tube OD Flaw Evaluation Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 4 Westinghouse Reactor Vessel Head Penetration Examination

6.0 REFERENCES

[1] EPRI/MRP89 Technical Report, 'Materials Reliability Program: Demonstrations of Vendor Equipment and Procedures for the Inspection of Control Rod Drive Mechanism Head Penetrations (MRP-89)", EPRI, Palo Alto, CA: July, 2003.

[2] USNRC Letter EA,03-009, "Issuance of First Revised NRC Order (EA-03-009)

Establishing Interim Inspection Requirements for Reactor Vessel Heads at Pressurized Water Reactors", February 20, 2004.

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 Westinghouse Reactor Vessel Head Penetration Examination Appendix A V)Westinghouse Wesdnghouse Ekctrk Company NudearServies P.O.Box 355 Pittsburgh Pennsytvana 1523Of03s5 USA Mr. Erdal Caba Direatet 412-374-5651 Progress Energy Difectfahc 412-374-3451

}1. B. Robinson Site e-maul alexaldwestinghousecn 3581 West Entrance Road WeinghouSe0.: 25084 Hartsville, SC 29550 CuastomeP.O. 3382 Task WorklAuth. 37 Ourre. PGN-04-33 April 21. 2004 PROGRESS ENERGY

11. B. ROBINSON RVH Penetrtslon Stress Distributions

Dear Mr. Caba:

Attached are curves (LTR-PAFM-04-32) for noted penetrations showing stress distributions including the distance from the bottom o tthe I groove weld to where the hoop stress drops below 20 ksi. If you have any questions concerning these curves please call either Chris Ng on 724-722.6030 or Warren Bamford on 724-722-6049.

Sincerely, WESTINGHOUSE ELECTRIC COMPANY LLC Dwain W. Alexander Customer Projects Manager Attachment cc: Pete Harden Westinghouse Charlotte Chris Church Robinson J. Zook Westinghouse Offiial record ekdtronkally appbved i WE6 2000 A BNR GCrup cpany Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 4fWestinghouse Reactor Vessel Head Penetration Examination Appendix A S Tn Westinghouse Dwain Alexander Dat April 20,2004 cc: SLb Swamy rrm:

Ext 724--6030 Fix 724722-5597 Your ret.

Our retf: LTR-PAFM.04-32 Aftchmnent to: PON.04-33 (10 Pages)

Subject l oop Stress Dlstribution Curves and 20 kil Inspection Zone for H. B. Robinson The hoop stm distribution below the J-wld Curves hnve been geneated for the H. B. Robinson head pnctration nozzlcs. The distance from the bottom or die weld to where the hoop stress drops below 20 ksi is also shom in each cave. Pkease transmit the attached Information on pagrs 2 to 10 to CPL Autho___ __

C.K. Ng', Piping Analysis Fracture Mechanics

' Official Record Elctronically Approved in EDMS 2000 ARNFLCeoupconpany Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

&Westinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-1 As-Designed Hoop Stress Distribution Below the Weld Downhill and Uphill Side, (0 CRDM Penetration Nozzle) 60,000 50.000 40.000 0 30,000 20,000 CL o

0 0

0 0

0.0 0.5 1.0 1.5 2.0 2.5 Distance from Bottom of Weld (in)

-4inside -- Outside I Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O )Westinghouse ReactorVesselHeadPenetrationExamination Appendix A Figure 6-2 As-Built Hoop Stress Distribution Below the Weld Downhill Side (27.10 CRDM Penetration Nozzle) th 0.

In In L.

U) a.

0 0

0.0 0.2 0.4 0.6 0.8 1.0 12 1.4 Distance from Bottom of Weld (in) l--Inside -- Outside Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O Westinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-3 As-Built Hoop Stress Distribution Below the Weld Uphill Side (27.10 CRDM Penetration Nozzle) n.

en 0

ta vL U) 0.

0 0

X 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 Distance from Bottom of Weld (in)

-- Inside -- Outside Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 O Westinghouse Reactor Vessel Head Penetration Examination Pa Appendix A Figure 64 As-Designed Hoop Stress Distribution Below the Weld Downhill Side (41.50 CRDM Penetration Nozzle) 80,000 70,000 60,000-50,000-40,000

,a 30,000 40 \1.39",

e~ 20,000 0.

0 X ~ 0.18" 0.0 0.5 1.0 1.5 2.0 2.5 Distance from Bottom of Weld (in) l-Inside - Outside Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

( Westinghouse Reactor Vessel Head Penetration Examination Anpendix A Figure 6-5 As-Designed Hoop Stress Distribution Below the Weld Uphill Side (41.50 CRDM Penetration Nozzle) 60,000 50,000 40,000 I2 .40 30,000

,,.in nnn j N 1~2.40" E lI 0.

0. 10,000

\ I I l\

0 0 I U,_I I __

-1,UUU I-

-20,000'. 11~

.,n nnn .

-JV ,uuV 0.0 1.0 0 2.1 3.0 4.0 M 5.0 6.0 Distance from Bottom of Weld (in)

Inside -U--Outside I Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 OWestinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-6 As-Designed Hoop Stress Distribution Below the Weld Downhill Side (43.00 CRDM Penetration Nozzle) 0.

CX

-30.000 1 - il _ I 0.0 0.5 1.0 1.5 2.0 2.5 Distance from Bottom of Weld (in)

Il Inside U Outside Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 Westinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-7 As-Designed Hoop Stress Distribution Below the Weld Uphill Side (43.00 CRDM Penetration Nozzle) 60..000 .I . . .

rn

-"'I Mn 40, in 30, 000 vw 20, 0002 o 10, 000 0 0

M 0 53

-10, 000.

-20, AA, 0.0 1.0 2.0 3.0 4.0 5.0 6.0 Distance from Bottom of Weld (in)

I-- Inside -m-Outsidel Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2

'hWestinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-8 As-Built Hoop Stress Distribution Below the Weld Downhill Side (46.00 CRDM Penetration Nozzle)

I_

C)

CL en CD, a.

0 X

0 0.0 0.1 0.2 0.3 OA 0.5 0.6 0.7 0.8 Distance from Bottom of Weld (in)

I- inside-Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 (Westinghouse Reactor Vessel Head Penetration Examination Appendix A Figure 6-9 As-Built Hoop Stress Distribution Below the Weld Uphill Side (46.00 CRDM Penetration Nozzle) 60,000 50,000 40,000 30,000 2.83" L L\

0 20,000

0. 10,000 0.48"\

0 0 0

-10,000

-20,000

-30,000

-40,000 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 Distance from Bottom of Weld (in)

It Inside - Outside I_

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 MWestinghouse Reactor Vessel Head Penetration Examination Apoendix B Appendix B: H.B. Robinson Unit 2 RVHP Examination Coverage Summary

. . UTCoverage. - .ECT Coverage. Combined UT and ECT Coverage

. .;- . , - . In.Accordance With Section IV.C'(5) In Accordance With Sectlon IV.C (5) In Accordance With Section iV.C'(5)

-,(b) (i)ofthe Revised NRaCOrder - (b) (ii) of the Revised NRC Order (b) (iii) of the Revised NRC Order'

. _ '.._ ,,.' , 4, of 69. Penetrations 17 of 69 PenetrUatons - 8 of 69 Penetrations

Open Housing' J-Groove Weld Penetratlon # ; : Scanner Trinity Probes;. Tube ID ECT and Tube OD ECT Trinity Probes Tube OD ECT 1 X X 2 X _ _ _

3 X .-

4 X 5 X _

6 X 7 X I __IT_

8 X _ _ _

9 X _ _ _

10 X _

11 X 12 X 13 X _ _ _ _ _ _ _ _ _ _ _

14 X I_ x_1__IT_

15 x x 16 X _

17 X 18 X 19 X 20 X 21 X 22 X .

23 X X 24 X X Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 eWestinghouse Reactor Vessel Head Penetration Examination Appendix B

. - UT Coverage -. - ECT Coverage Combined UT and ECT Coverage.

in Accordance With Section IV.C (5j In Accordance With Section iV.C (5)'j In Accordance With Sectlon IV.C (5)

(b) ( of the Revised, NRC Order (b) (II)of the Revised NRC Order; (b) (III) of the Revised NRC Order 44 of 69 Pinetrations - 17 of 69 Penetaons -  : 8 of 69 Penetrations '

- Open Housing ;.  :;-.....  : -. JrooveWeld ,- .--

Penetration # Scanner Trinity Probes' Tube ID ECT and Tube OD ECT Trinity Probes . -TubeOD ECT 25 X 26 X X 27 X X 28 X __ X___XI__

29 X X 30 X X 31 X 32 X X X 33 X X__ _ _ _ _

34 X 35 X X _ _ _ _ _ _

36 X _ _ _ _ _ _ _ _ _ _ _

37 X X 38 __ _ _ _ _ _X X 39 X X 40 X X _ _ _ _ _ _

41 X 42 X__ _ _ _ _

43 X X 44 _ _ _ _ _ __ _ _ _ _ _ _X X 45 X _ _ _ _ _ _ _ _ _ _ _ _ _

46 X_ _ _ _ _ _ __ _ _ _ _ _

47 X_ _ _ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _ _

48 X_ _ _ __ _ _ __ _ __

4 9 X_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

50 x_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

51 X_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Robinson 2004 Final Report REVOCorrected Typos

H.B. Robinson Unit 2 Westinghouse Reactor Vessel Head Penetration Examination Appendix B UT Coverage ECT Coverage - Combined UTand ECTCoverage-.

In Accordance With Section IV.C (5): In Accordance With Section IV.C (5) In Accordance With Section IV.C (5)

(b)(l) of the Revised NRC Order - (b) (II) of the Revised NRC Order '(b) (III) of the Revised NRC Order-,

4of 69 PenetratIons -. . 17 of 69 PenetratIons 8 of 69 Penetrations Open Housing JGroove Weld. -

Penetration 1 Scanner Trinity Probes Tube ID ECT .,and Tube OD ECT Trinit Probes Tube OD ECT.

52 X 53 X_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

54 X 55 X 56 X 57 X _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

58 X _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

59 X 60 X X 61 X X 62 X X X X 63 _ _ _ _ _ _ _X X _ _ _ _ _ _ _ _ _ _ _ _

64 X X 65 X X 66 _ X X 67 X X 68 X X 69 X X

  • Partial Scan Robinson 2004 Final Report REVOCorrected Typos
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