ML050140187

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Reactor Pressure Vessel Upper and Lower Head Inspection Results
ML050140187
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/06/2005
From: Fadel D
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:4054-11
Download: ML050140187 (18)
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Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1395 INDIANA MICHIGAN POWER January 6, 2005 AEP:NRC:4054-11 10 CFR 50.4 Docket No:

50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 UNIT 2 REACTOR PRESSURE VESSEL UPPER AND LOWER HEAD INSPECTION RESULTS

Reference:

1. Revised U. S. Nuclear Regulatory Commission Order EA-03-009, "Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," dated February 20, 2004.
2. Letter from R. P. Powers, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission Document Control Desk, "Nuclear Regulatory Commission Bulletin 2003-02:

Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity Thirty-day Response,"

AEP:NRC:3054-14, dated September 17, 2003.

3. Letter from William H. Ruland, U. S. Nuclear Regulatory Commission, to Mano K. Nazar, Indiana Michigan Power Company, "Donald C. Cook Nuclear Plant, Unit 2 Relaxation of the Requirements of First Revised Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections Dated February 20, 2004 (TAC No. MC3074),"

dated September 27, 2004.

This letter provides information pertaining to reactor pressure vessel (RPV) upper and lower head inspections performed at Donald C. Cook Nuclear Plant (CNP) during the Unit 2 Cycle 15 outage. This information is submitted in

l U. S. Nuclear Regulatory Commission AEP:NRC:4054-11 Page 2 accordance with the Nuclear Regulatory Commission (NRC) Order (Reference

1) and the commitment made in response to NRC Bulletin 2003-02 (Reference 2).

The referenced order imposed enhanced requirements for inspection of pressurized water RPV heads and related penetration nozzles. A calculation of the susceptibility category of the Unit 2 RPV upper head as represented by a value of effective degradation years (EDY) was performed to determine the required inspections per Section IV.A of the order.

The EDY value at the beginning of the Unit 2 Cycle 15 refueling outage was 13.03, which combined with previous repairs, assigns this head to the high susceptibility category. This represents a reduction from previous cycles in the calculated EDY value due to the use of cycle specific operating data. In accordance with Section IV.C of the order and the relaxation approved per Reference 3, Indiana Michigan Power Company (I&M) conducted non-destructive examinations of the Unit 2 upper head RPV penetration nozzles and a bare-metal visual examination of the upper surface of the RPV head during the refueling outage that.ended November9, 2004.

I&M also conducted a visual inspection of the bottom mounted instrumentation (BMI) nozzle penetrations in accordance with Bulletin 2003-02. I&M hereby submits reports of these examinations in accordance with Section IV.E of the order and the CNP commitment made in response to Bulletin 2003-02. Attachment I provides the report of the non-destructive examination of the RPV upper head nozzles. Attachment 2 provides the report of the bare metal visual examination of the RPV head upper surface. Attachment 3 provides the report of the visual inspection of the BMI nozzle penetrations.

The visual inspections performed on the upper head in accordance with Section IV.D of the order during the Unit 2 refueling outage did not identify any leaks or boron deposits from pressure retaining components on or above the RPV head. Therefore, no report regarding that inspection is required by Section IV.E of the order.

This letter contains no new commitments.

Should you have any questions, please contact Mr. John A. Zwolinski, Director of Safety Assurance, at (269) 466-2428.

EnginerI V

P Engineering Vice President KAS/rdw

U. S. Nuclear Regulatory Commission AEP:NRC:4054-11 Page 3 Attachments:

1.

Wesdyne International Report - "D. C. Cook RVHI U2C 15 Final Report, Revision 1"

2.

Summary Report Bare Metal Visual Examination of the Donald C. Cook Nuclear Plant Unit 2 Reactor Pressure Vessel Upper Head

3.

Summary Report Bottom Mounted Instrumentation Penetration Inspection of the Donald C. Cook Nuclear Plant Unit 2 Reactor Pressure Vessel Lower Head c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachments Director, Office of Nuclear Reactor Regulation J. T. King, MPSC, w/o attachments C. F. Lyon - NRC Washington, DC MDEQ - WHMD/HWRPS, w/o attachments NRC Resident Inspector'

U. S. Nuclear Regulatory Commission AEP:NRC:4054-11 Page 4 AFFIRMATION I, Daniel P. Fadel, being duly sworn, state that I am Engineering Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.

Indiana Michigan Power Company aniel P. Fadel Engineering Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS Ai, DAY OF 2005 M Cm s

on E

rye blic My Commission Expires Utlt

ATTACHMENT 1 TO AEP:NRC:4054-11 WESDYNE INTERNATIONAL REPORT -

"D. C. COOK RVHI U2C15 FINAL REPORT, REVISION I"

Gil W ES flE D. C. Cook Unit 2

rag, Reactor Vessel Head Pcnetration Inspection FINAL REPORT

SUMMARY

1.0 DISCUSSION During the D. C. Cook Unit 2 Outage U2C15 in October 2004, WesDyne performed nondestructive examinations (NDE) of the reactor vessel head penetrations. The purpose of the nondestructive inspection program was to identify evidence of primary water stress corrosion cracking (PWSCC) that might be present on the OD and ID surfaces of the head penetrations. Examinations of the CRDM penetration tubes also included the application of techniques to identify evidence of leakag in the shrink-fit region at the tube-to-head interface. Examinations were performed using procedures and techniques demonstrated through the EPRI/MRP protocol and/or Westinghouse internal demonstration programs. The examination program was applied in a nmnner acceptable within the context of the February 20, 2004, USNRC Order EA-03-009, "Establishing Interim Inspection Requirements for Reactor Vessel Heads at Pressurized Water Reactors," including the D. C. Cook Unit 2 Request for Relaxation of Requirements dated September 27, 2004.

The reactor vessel head at D. C. Cook Unit 2 is a Westinghouse design and manufactured by Chicago Bridge & Iron in Memphis, TN. The head contains 78 alloy 600 penetration tubes that are shrunk fit in the reactor vessel head and attached with alloy 182/82 partial penetration J-groove welds. The head also contains one alloy 600 vent tube, attached to the vessel head with an alloy 182/82 attachment weld.

There are a variety of configurations for the 78 penetration tubes, each configuration requiring special consideration for examination. The penetration tubes measure 4.0 inches on the OD and have an ID dimension of 2.75 inches. The wall thickness is 0.625 inches.

The penetration tube configurations are as follows:

  • five thermocouple column locations without thermal slzeves The vent line has a nominal ID dimension of 0.614 inches and a nominal OD dimension of 1.0 inch.

The nondestructive examinations were performed in accordance with the following field service procedures and field change notices (FCNs):

D. C. Cook U2C15 RVHI Final Report, Rev. I

P7 wESpyn-I.Te... Tioo^

D. C. Cook Unit 2 Reactor Vessel Head Penetration Inspection WCAL-002 Rev. 4 WDI-ET-002 Rev. 5 WDI-ET-003 Rev. 7 WDI-ET-004 Rev. 6 WDI-ET-008 Rev. 4 WDI-UT-010 Rev. 8 WDI-UT-01 1 Rev. 6 WDI-UT-013 Rev. 6 WDI-STD-101 Rev. 3 Pulser/Receiver Linearity Procedure IntraSpect Eddy Current Inspection of J-Groove Welds in Vessel Head Penetrations IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations IntraSpect Eddy Current Analysis Guidelines (with FCN 01)

IntraSpect Eddy Current Imaging Procedure for Inspection of Reactor Vessel Head Penetrations with Gap Scanner IntraSpect Ultrasonic Procedure for Inspection of Reactor Vessel Head Penetrations, Time of Flight Ultrasonic, Longitudinal Wave & Shear Wave (with FCN 01 and 02)

IntraSpect NDE Procedure for Inspection of Reactor Vessel Head Vent Tubes (with FCN 01)

IntraSpect UT Analysis Guidelines (with FCN 01 and 02)

RVHI Vent Tube J-Weld Eddy Current Examination (with FCN 01)

WDI-STD-114 Rev. 2 RVHI Vent Tube ID & CS Wastage Eddy Current Examination 2.0 SCOPE OF WORK The scope of the nondestructive examinations at D. C. Cook Unit 2 was based on a plan to perform ultrasonic examinations, including time-of-flight diffraction (TOFD) ultrasonic techniques, capable of detecting axial and circumferential reflectors in the parent tube and the J-weld and eddy current examinations capable of detecting axial and circumferential degradation of the penetration ID surfaces. WesDyne performed nondestructive examinations on one vent line and 78 CRDM reactor vessel head penetrations.

Examinations of the penetration tubes were performed using the following approaches.

The approach selected for each penetration was dependent upon the penetration tube configuration and penetration specific conditions.

  • Sixteen penetration tubes without thermal sleeves were examined from the ID using the 7010 Open Housing Scanner.

D. C. Cook U2C15 RVHI Final Report, Rev. I

wespyncD.

C. Cook Unit 2 Page Reactor Vcssel Head Pcnetration Inspection

  • Sixty one penetrations were examined from the ID using the Gapscanner with Trinity blade probes which perform TOFD ultrasonic examinations and eddy current examinations simultaneously.
  • The vent line tube ID surface and the vent line J-groove weld were examined using eddy current techniques with multiple coil arrays.
  • An eddy current examination was performed on penetrations 43 and 74 using a special excavation svord probe with the Gapscanner end effector.

The delivery system used for the CRDM examinations at D. C. Cook 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 The DERI 700 was used to deliver 1) the Westinghouse 7010 Open Housing Scanner for ultrasonic and supplementary eddy current examinations of penetration locations without thermal sleeves and 2) the Westinghouse Gapscanner end effector for ultrasonic and supplementary eddy current examinations of penetration locations containing thermal sleeves and 3) the Grooveman end effector for eddy current examinations of the J-groove welds and 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 ease at least 2.0 inches, to the ID chamfer at the bottom of each penetration. The probe is indexed in the circumferential direction. With the open housing scanner, four examinations are conducted simultaneously. These include:

1) Time-of-flight diffraction ultrasonic examination optimized for identification of circumferentially oriented degradation on the penetration tube OD surfaces
2) Time-of-flight diffraction ultrasonic examination optimized for identification of axially oriented degradation on the penetration tube OD surfaces D. C. Cook U2C15 RVHI Final Report, Rev. I

N WESDynE"D. C. Cook Un it2

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.Page Reactor Vcsscl Head Penetration Inspection

3) Straight beam ultrasonic examination to identify variations in the penetration tube-to-reactor vessel head shrink fit area that might indicate a leak path
4) Eddy current examination for identification of circumferential and axial degradation on the ID surfaces of the penetration tubes The Gapscanner end effector delivers combination blade "Trinity" probes which include a crosswound eddy current coil, a TOFD UT transducer pair and a 0° ultrasonic transducer into the annulus between the ID surface of the reactor vessel head penetration tube and the OD surface of the thermal sleeve. All three examinations are performed simultaneously. The typical annulus size is 0.125 inches. The blade probe design utilizes 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 inches, to the ID chamfer at the bottom of each penetration. The probes are indexed in the circumferential direction. The Gapscanner end effector also has a probe tilt and drive unit to advance and reverse the probe in the tube/thermal sleeve annulus, a turntable to rotate the probe drive around the axis of the penetration, a lifting cylinder to raise and lower the tilt and drive unit and a centering device consisting of two clamping arms.

The Grooveman end effector delivers eddy current probes for examination of the J-groove welds 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 typically 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.

The vent line weld scanner is delivered manually beneath the head and applies an array of plus-Point eddy current coils to the vent tube J-weld surface. The entire weld is examined with two 360 degree scans.

The vent line tube scanner is also delivered manually beneath the head and applies an array of plus-Point eddy current coils and a low frequency bobbin probe to the inside diameter surface of the vent tube.

Penetrations 74 and 75 were examined using dye penetrant techniques. Both penetrations had recordable indications in the J-weld region. These areas were repaired using weld overlay techniques as described in WCAP-15987-P, revision 2-P-A, as described in AEP's letter, Request for Relief for Donald C. Cook Nuclear Plant, "Proposed Alternative to Repair Requirements of Section Xl of the ASME Code for Unit I and 2 D.C. Cook U2CI 5 RVHI Final Report, Rev. I

n. ~syflE D. C. Cook Unit 2 Reactor Vessel Head Penetration Inspection Reactor Vessel Head Penetrations," which was submitted by letter dated October22, 2004, as revised October 27, 2004. The repair technique was approved by phone conversation on October 28, 2004, between J. Zwolinski (AEP), et al., with T. Chan and L. Raghavan (NRC), et al., when the NRC staff verbally approved the licensee's relief request in accordance with 10 CFR 50.55a (a) (3) (i). Post repair examination data had no indications, and is included in Volume 1, Section 4 of this report.

The top 3 OD threads on the downhill side of penetration 73 were also examined by liquid penetrant techniques. No indications were detected. This examination was performed by Cook personnel.

A bare metal remote visual inspection of 100% of the RPV head surface was performed in accordance with EA-03-009, section IV.C (5) (a) by contractor and AEP personnel. No evidence of leakage or base metal wastage was identified.

3.0 EXAMINATION RESULTS The following tables provide a summary of all RVHP nondestructive examinations performed at D. C. Cook Unit 2 during the U2C15 October 2004 refueling outage.

Penetration numbers with an asterisk show eddy current indications and have been identified as special interest by D. C. Cook personnel. The final disposition of the examination results is provided in the tables below.

3.1 7010 Open Housing Scanner Ultrasonic and Eddy Current Examinations Sixteen penetrations without thermal sleeves were examined from the ID using the Westinghouse Open Housing Scanner.

10 NDD NDD NDD NDD NDD 11 NDD PTI/IPA/NDD NDD NDD NDD 12 NDD NDD NDD NDD SAI*

13 NDD NDD NDD NDD NDD 18 NDD NDD NDD NDD NDD 19 NDD

  • ND NDD NDD NDD 20 NDD WII/PTIIIPA NDD NDD NDD NDD 21 NDD NDD NDD NDD SAI*

24 NDD PTI/IPAINDD NDD NDD NDD 62 NDD NDD NDD NDD SGIICBH D.C. Cook U2C15 RVHI Final Report, Rev. I

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D. C. Cook Unit 2 im

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Page6ofll Rcactor Vessel Hcad Pcnctration Inspection 63 NDD NDD NDD NDD NDD 65 NDD PTI/IPAINDD NDD.

NDD NDD 75 NDD PTIIIPAINDD NDD NDD SAI*

76 NDD PTIIIPAICBH NDD NDD SGIINDD 77 NDD NDD NDD NDD NDD 78 NDD NDD NDD NDD NDD

3.2 Gapscanner Trinity Probe Examination Results The following table provides a summary of the results of the examinations of sixty one penetration tubes examined from the ID using the Gapscanner end effector with Trinity probes.

NDD 2

PTI/IPAINDD NDD NDD NDD 3

PTIIIPAINDD NDD NDD NDD 4

NDD NDD NDD NDD 5

WII/NDD NDD NDD NDD 6

NDD NDD NDD NDD 7

NDD NDD NDD NDD 8

PTI/IPAINDD NDD NDD NDD 9

NDD NDD NDD NDD 14 WIIIIPAINDD NDD NDD NDD 15 NDD NDD NDD SAI*

16 WIIINDD NDD NDD NDD 17 PTIIIPAINDD NDD NDD NDD 22 NDD NDD NDD NDD 23 WIIINDD NDD NDD NDD 25 PTIIIPA/NDD NDD NDD NDD 26 NDD NDD NDD NDD 27 WIIINDD NDD NDD NDD 28 PTIIIPA/NDD NDD NDD NDD 29 NDD NDD NDD NDD 30 NDD NDD NDD NDD 31 PTIIIPAINDD NDD NDD NDD 32 WIIIPTIINDD NDD NDD NDD D. C. Cook U2C15 RVHI Final Report, Rev. I

D. C. Cook Unit 2 Page 7 of 11 Reactor Vessel Head Penetration Inspection Sfuppementaryi i

Eddy C rrent. Tube JO NDD PTIIIPAINDD NDD PTIIIPAINDD NDD PTIIIPAINDD NDD PTIIIPAINDD NUU NDD 38 WIIIIPAINDD 39 PTIIIPAINDD 40 NDD 41 NDD 42 NDD 44 NDD 45 WIIIPTIINDD I NDD NDD NDD NDD NDD NDD NDD SGIINDD NDD NDD NDD NDD INDDN NDD 46 WIIIPTIINDD NDU NDD NDD 47 NDD NDD NDD NDD 48 NDD NDD NDD NDD 49 PTIIIPAINDD NDD NDD NDD 50 NDD NDD NDD NDD 51 WIIINDD NDD NDD NDD 52 NDD NDD NDD NDD 53 PTIIIPAINDD NDD NDD NDD 54 PTIIIPAINDD NDD NDD NDD 55 PTINIIIIPAI NDD NDD NDD 56 NDD NDD NDD NDD 57 NDD NDD NDD NDD 58 NDD NDD NDD NDD 59 NDD NDD NDD SAI*

60 PTIIIPAINDD NDD NDD NDD 61

- NDD NDD NDD NDD 64 NDD NDD NDD SAI*

66 PTIJWIIINDD NDD NDD NDD 67 PTIIIPAINDD NDD NDD NDD 68 NDD NDD NDD SAI*

69 PTIIIPAINDD NDD NDD NDD 70 PTIIWII/NDD NDD lND NDD 71 PTI/WII/NDD NDD NDD NDD 72 NDD NDD NDD NDD 73 NDD NDD NDD NDD 74 PTIIIPAILOF NDD NDD SAI*

N ODD_

D.C. Cook U2CIS RVHI Final Report, Rev. I

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-I i D. C. Cook Unit 2 Reactor Vessel Head Penetration Inspection 3.3 Special Grooveman Eddy Current Examination Results A special eddy current examination was conducted on the tube and roof area of the OD of penetration 43 using the Grooveman end effector. The table below shows the results of this examination.

3.4 Special Excavation Probe Examination Results The following table provides a summary of the examination of penetrations 43 and 74 excavation areas using eddy current sword probes and the Gapscanner end effector.

3.5 Vent Line Eddy Current Examination Results 3.6 Post Repair Examination Results D. C. Cook U2CIS RVHI Final Report, Rev. I

nIWESpynlE D. C. Cook Unit 2 Pag Reactor Vessel Head Penetration Inspection Legend:

CBH - Cleared by History IPA - Indication Profile Analysis Resolution of Indication LOF-Lack of Fusion at the tube to weld interface NDD -No Detectable Defect

'PTI - Penetration Tube Indication SAni 1AI - Single/Multiple Axial Indication SGI - Surface Geometry Indication SSI - Surface Scratch Indication WII - Weld Interface Indication 4.0 EXAMINATION COVERAGE The configuration of the D. C. Cook UJnit 2 CRDM penetration tubes is shown in Figure

1. This figure represents the tube-to-head geometry on the "downhill" side of the tube (O° azimuth of the penetration). The bottom ends of all seventy-eight penetration tubes are threaded on the OD surface and have a 150 chamfer on the ID surface.

Carbon Steel 1DuttleringA Staint.eJ Steel Wed 600 Theirmal Sleeve Masked

'A/C Area

.233 0.75

.625-J 15 Figure 1 D.C. Cook U2C15 RVHI Final Report, Rev. I

F7-i wEspylnEl D. C. Cook Unit 2 Page Reactor Vcsscl Head Penetration Inspection The threads on the OD surfaces extend from the bottom of the tube to an elevation of approximately 0.625" where there is a thread relief machined. The top of the thread relief is 0.750" above the bottom of the tube. The distance from the top of the thread relief to the bottom of the fillet of the J-groove weld (identified as "A/C" in Figure 1) varies based on location ofthe penetration in the head. These distances are longer for penetrations at "inboard" locations and become progressively shorter for penetrations located further away from the center of the head.

The ID surfaces of the penetration tubes are chamfered at a 15° angle from the bottom of the tube to an elevation of 0.233". The presence of the thread relief results in masking of the propagation of ultrasound to the OD surface of the tube to an elevation of 0. 101" above the elevation of the thread relief for axial shooting TOFD probes. In this masked OD region degradation would not be detected until the depth of indications exceeds the depth of the masked area.

The threads on the tube OD surfaces and chamfer on the ID surfaces represent geometric conditions which limit examination coverage near the bottom of the tubes.

For ID examinations of all 78 penetration tubes the TOFD PCS24 examination coverage extended from the uppermost elevation of the chamfer (0.233" from the bottom of the tube plus half of the PCS) for axial shooting probes to elevations at least 2.0" above the weld (identified as "B" in Figure 1). For circumferential shooting TOMD PCS24 probes the examination coverage extended from the uppermost elevation of the chamfer (0.233" from the bottom of the tube plus half of the probe diameter) to elevations at least 2.0" above the weld (identified as "B" in Figure 1).

Supplementary eddy current examination coverage extended from the uppermost elevation of the chamfer (0.233" from the bottom of the tube plus half of the probe diameter) to elevations at least 2.0" above the weld. The extent of coverage was verified for each penetration by confirmation that 1) tube entry signals were evident and 2) scan coverage elevations were in excess of 2.0" above the uppermost elevation of each weld.

For OD examinations of all 61 sleeved penetration tubes, the TOED PCS24 transducer coverage extended from 0.851 " (for Gap Scanner examination) above the end of the tube to elevations at least 2.0" above the uppermost elevation of each weld (Figure 2). For the other 16 penetration tubes the TOED PCS24 transducer coverage extended from the uppermost elevation of the chamfer (0.233" from the bottom of the tube plus half of the probe diameter) to elevations at least 2.0" above the uppermost elevation of each weld (Figure 3). From the thread relief to the chamfer region the UT coverage from the ID equals 0.406" in depth. The extent of coverage was verified for each penetration by confirmation that: 1) TOFD ultrasonic signals from the thread relief and thread area were evident and 2) scan coverage elevations were in excess of 2.0" above the uppermost elevation of each weld.

D.C. Cook U2C15 RVHI Final Report, Rev. I

A.

. L 1.

D. C. Cook Unit 2 Reactor Vessel Hcad Penetration Inspection D.C. COOK UNIT 2 INSPECTION COVERAGE 0.2331-

+1/20 X THE TRANSDUCER j.406 FIGURE 3 FOR NON-~SLEEVED PENETRATMNS F)GURE 2 FOR SLEEVED PENETRATIONS 5.0 DISCUSSION OF RESULTS Results from the nondestructive examinations of the 78 reactor vessel head penetrations, the vent line tube and vent line weld are presented in the previous tables. Details for each examination performed on each penetration are found in Volume 2 of this report.

D. C. Cook U2C15 RVHI Final Report, Rev. I

.V ATTACHMENT 2 TO AEP:NRC:4054-11

SUMMARY

REPORT BARE-METAL VISUAL EXAMINATION OF THE DONALD C. COOK NUCLEAR PLANT UNIT 2 REACTOR PRESSURE VESSEL UPPER HEAD A bare-metal visual examination of the Donald C. Cook Nuclear Plant (CNP) Unit 2 reactor pressure vessel (RPV) head was conducted during the refueling outage that ended November 9, 2004. This inspection was required by Sections IV.C(1) and IV.C(5)(a) of Nuclear Regulatory Commission (NRC) Order EA-03-009, "Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," dated February 20, 2004. Contractor personnel in conjunction with

-CNP personnel conducted the examination. A remotely operated crawler with multiple cameras was used to examine 360 degrees around each of the 79 RPV head penetrations. A bare-metal visual examination of 100 percent of the RPV head was also performed. The inspection did not identify any evidence of leakage or base metal wastage.

ATTACHMENT 3 TO AEP:NRC:4054-11

SUMMARY

REPORT BOTTOM MOUNTED INSTRUMENTATION PENETRATION INSPECTION OF THE DONALD C. COOK NUCLEAR PLANT UNIT 2 REACTOR PRESSURE VESSEL LOWER HEAD A visual inspection of the Donald C. Cook Nuclear Plant (CNP) Unit 2 bottom mounted instrumentation (BMI) nozzle penetrations was completed during the Unit 2 Cycle 15 refueling outage that ended November 9, 2004. This inspection was completed in accordance with Indiana Michigan Power Company's commitment made in response to Nuclear Regulatory Commission Bulletin 2003-02, "Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity," dated August 21, 2003.

The inspection was conducted by CNP Performance Verification personnel qualified as Level 2 examiners. A pole mounted, alternating current powered camera was used to perform a VT-2 examination to VT-3 examination criteria on all 58 Unit 2 Reactor Pressure Vessel (RPV) BMI nozzle penetrations, including 360 degrees around each BMI penetration. No boric acid deposits were found at any RPV BMI nozzle penetration or anywhere on the RPV bottom head surface area. No boric acid residue sampling or analysis was required or performed. The as-found condition of the Unit 2 RPV bottom head was identical to the as-left condition following the bottom head cleaning performed during the Unit 2 Cycle 14 refueling outage. No indications of through-wall leakage were found during the Unit 2 Cycle 15 RPV BMI inspection. The bottom two sections of insulation were lowered to allow unobstructed access to all penetrations and the membrane areas of the lower reactor vessel. The inspection results were saved to computer drives as video clips.

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