ML070680154

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(2) ENN-NDE-10.01, Rev. 2; VT-1 Examination, 02/13/2006
ML070680154
Person / Time
Site: Indian Point, Pilgrim, Vermont Yankee, FitzPatrick  Entergy icon.png
Issue date: 02/13/2006
From: Limpias O
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
ENN-NDE-10.01, Rev 2
Download: ML070680154 (22)
v • d • e


Text

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r I 1 I I I mEntew NUCLEAR MANAGEMENT QUALIN RELATED ENN-NDE-10.01 PAGE 1 OF22 REV. 2 MANUAL lNFORMATlONALUSE

Title:

VT-1 EXAMINATION Procedure Owner: Oscar Limpias / Vic dent Engineering (Print Name / Title) / 1 EN Common Effective Effective GGNS Date Date IPEC Exception JAF WPO Procedure Contains NMM REFLIB Forms: YES [x1 NO 0 Basis Statement ENN-NDE-10.01 Revision 2 includes:

o Editorial change correcting section 9.0 attachment references from VT-3 to VT-1.

Site and NMM Procedures Canceled or Suuerseded Bv Thls Revision ENN-NDE-10.01 Revision 1 Process Amllcabilitv Exclusion (ENN-LI-100) / Proarammatic Exclusion (ENS-LI-101)

All Sites: Specific Sites: AN0 GGNS 0IPECO JAF 0 PNPSU RBS c]VY W3 0

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2 Ente~sy MANAGEMENT MANUAL INFORMATlONAL USE PAGE 2 0 F 2 2 I

I I I VT-1 EXAMINATION I

I TABLE OF CONTENTS Section -

Title Paae 1.o PURPOSE.................................................................................... 3

2.0 REFERENCES

............................................................................. 3 3.0 DEFINITIONS .............................................................................. 4 4.0 RSPONSISILIT/ES.................................................................... 4 5.0 DETAILS ...................................................................................... 4 6.0 INTERFACES ............................................................................ 14 7.0 RECORDS ................................................................................. 14 8.0 OBLIGATIONAND REGULATORYCOMMITMENT CROSS-REFERENCES ............................................................ 15 9.0 AlTACH MENTS ........................................................................ 17 AITACHMENT 9.1 VT-1 EXAMINATION REPORT (BOLTING) ........ 18 ATACHMENT 9.2 VT-1 EXAMINATION REPORT (INTEGRAL ATTACHMENTWELDS)................................. 19 ATTACHMENT9.3 VT-1 EXAMINATION REPORT(NOZZLE INNER RADIUS) ...................................................... 20 A-ITACHMENT 9.4 VT-1 EXAMINATIONREPORT(CONTAINMENT SURFACES) ................................................. 21 ATTACHMENT 9.5 VT-1 EXAMINATION REPORT(CONCRETE SURFACES) ................................................. 22

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2 MANAGEMENT terg). MANUAL fNFORMATlONAL USE PAGE 30F22 PURPOSE This procedure establishes the methods and requirements to be used for ASME Section XI VT-1 examination of components.

VT-1 examinations are conducted to detect discontinuities and imperfections on the surfaces of components, including such conditions as cracks, wear, corrosion, erosion, or physical damage.

IWE and IWL detailed visual examinations will be performed per VT-1 requirements to assess the condition of surfaces requiring augmented examinations and determine the magnitude and extent of any deterioration and distress of these surfaces.

This procedure is not applicable to VT-1 examinations performed per the lnvessel Visual Inspection (IWI)BWR VIP program.

REFERENCES Nuclear Regulatory Commission, 10 CFR Part 50, Industry Codes and Standards.

ASME Boiler & Pressure Vessel Code, Section XI, 2001 Edition, including 2003 Addenda.

ASME Boiler & Pressure Vessel Code, Section V and XI, 1998 Edition with addenda through 2000.

ASME Boiler & Pressure Vessel Code, Section V and XI, 1992 Edition, including 1992 e

Addenda.

ASME Boiler & Pressure Vessel Code, Section XI, 1989 Edition no Addenda.

ASME Boiler and Pressure Vessel Code, Code Cases ENN Site Specific Relief Requests, Reference Section 8.0 Regulatory Guide 1.147 "Inservice Inspection Code Case Acceptability" ENN-NDE-1.OO,Administrative Controls for Non-destructive Examination ENN-NDE-2.12, Certification of Visual Testing (VT) Personnel.

ENN-NDE-10.02, VT-2 Examination ENN-NDE-10.03, VT-3 Examination

NUCLEAR QUALITY RELAED ENN-NDE-10.01 REV. 2 tew MANAGEMENT MANUAL lNFOAMATlONAL USE PAGE 4 0 F 2 2 I

I I VT-1 EXAMINATION I

I 3.0 DEFINITIONS ill Reference ASME Boiler and Pressure Vessel Code, Sections V, for the glossary of terms used in Nondestructive Examination ( N E ) .

4.0 RESPONS1BILlTlES 4.1 SUPERVISOR VI The Supervisor, charged with the responsibility for NDE at each site, is responsible for implementation of this procedure.

4.2 ENTERGY NDE LEVEL Ill r11 The Entergy Level 111 is responsible for development, interpretationand qualification of this procedure.

PI The Entergy Level IIt is responsible for demonstration of this procedure to the ANI!

when requested.

4.3 NDE PERSONNEL PI Personnel performing examinations per this procedure shall be certified in accordance with a written certification program accepted by the site.

PI Level II or 111 personnel shall be responsible for the examination and interpretation of results.

l31 Level I and trainee (Level IT) personnel may be used to assist in performing examinations. Final interpretationof collected data shall be the responsibility of the Level II or 111 examiners.

5.0 DETAILS 5.1 PRECAUTIONS AND LIMITATIONS PI None 5.2 PROCEDURE DEMONSTRATION

[I 1 Procedure demonstrations shall be documented and contain or reference the examination techniques required to meet the Code requirements in the following paragraphs.

[21 JAF, IPEC -/ASME Sections XI, 1989 Edition.

(a) For procedural demonstration, the combination of access and lighting sufficient to resolve a 1/32" black line on an 18% neutral gray card may be used.

I I I I 1 aE'tqgy

-ZZ-I NUCLEAR MANAGEMENT QUALITYRELATED ENN-NDE-70.01 REV. 2 MANUAL lNFOAMATlONALUSE PAGE 50F22

[3] JAF, IPEC - ASME Section XI Subsection IWE and IWL, 1992 Edition including 1992 Addenda; VY - 1998 Edition with Addenda through 2000.

(a) For procedural demonstration, a near-distance vision test chart containing text with lower case characters without an ascender or descender meeting the requirements of ASME Section XI, IWA-2210 is required.

(b) Measurements of the of the near-distance test chart shall be made once before initial use with an optical comparator (1OX or greater) or other suitable instrument, to verify that the height of a representative lower case character for the selected type size meets the requirements of Table IWA-2210-1.

(c) When performing remote visual examinations, the maximum direct examination distance specified in Table IWA-2210-1 may be extended and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.

[4] PNPS - ASME Section XI 2001 Edition through 2003 Addenda (a) For procedural demonstration, a test chart containing text with some lowercase characters, without an ascender or descender (e.g. a, c, e, o), that meets the requirements of Table IWA-2211-1 is required.

(b) Measurements of the test chart or card shall be made once before its initial use with an optical comparator (1Ox or greater) or other suitable instrument to verify that the height of the lowercase characters without an ascender or descender meets the specified requirements.

(c) Remote examination may be substituted for direct examination. The remote examination shall be demonstrated capable of resolving characters in accordance with Table IWA-2211-1, Additionally, the remote visual examination system shall be capable of distinguishing colors applicable to the component examinations be conducted.

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2

=Ente/gy MANAGEMENT MANUAL INFORMATlONAL USE PAGE 6OF22 El] The following or additional equipment may be used as determined necessary by the examiner:

(a) Flashlights / Drop Lights (b) Light Meter (c) Mirrors (d) Magnifying Lenses (e) Binoculars (f) Telescopes (9) Tape Measure / Six inch Scales (h) Borescopes (i) Fiber Optics (j) Cameras 5.4 ACCESS AND ILLUMINATION (LIGHTING)

[I] Accessibility (a) -

JAF, IPEC ASME Sections XI, 1989 Edition, no Addenda (1) Direct visual examination shall be conducted when access is sufficient for the eye to be within 2 4 (610 mm) of the surface to be examined and at an angle of not less than 30to the surface. Mirrors may be used to improve the angle of vision and/or accessibility in constricted areas.

(2) Remote visual examination may be substituted for direct examination.

For all remote visual examinations, optical aids such as telescopes, borescopes, fiber optics, cameras, or other suitable instruments may be used provided such systems have a resolution capability at least equivalent to that attainable by direct visual examination.

NUCLEAR QUALIW RELATED ENN-NDE-10.01 REV. 2 En&qy MANAGEMENT MANUAL INFORMAFONAL USE PAGE 7OF22 (b) -

JAF, IPEC ASME Section XI Subsection IWE and IWL, 1992 Edition including 1992 Addenda; VY 1998 Edition with Addenda through 2000.

(1) For direct examination, the maximum examination distance of two feet shall apply to the distance from the eye to the surface being examined at an angle not less than 30 degrees.

(2) Remote examination may be substituted for direct examination. The remote examination shall be demonstrated to resolve the selected test chart characters in Table IWA-2210-1.

a. Remote examinations may use visual aids such as telescopes, binoculars, fiber optics, and cameras.
b. The remote visual examination system shall have the capability of distinguishing and differentiating between colors applicable to the requirements for the component examinations being conducted.

(c) PNPS - ASME Section XI 2001 Edition through 2003 Addenda (1) Direct visual examination distance requirements shall be as specified in Table IWA-2211-1.

(2) Remote visual examination may be substituted for direct examination.

The remote examination shall be demonstrated capable of resolving characters in accordance with Table tWA-2211-1.

(3) The remote visual examination system shall be capable of distinguishing the colors applicable to the component examinations being conducted.

[2] Illumination (Lighting)

(a) Illumination may be achieved by natural or artificial means. Flashlights, drop lights, or industrial lighting may be used.

(b) -

JAF, IPEC ASME Sections XI, 1989 Edition, no Addenda (1) Lighting, natural or artificial shall be sufficient to resolve a 1/32 black line on an 18% neutral gray card or the finest line on a machinist scale.

NUCLEAR Q U A u N RELATED ENN-NDE-10.01 REV. 2 a

Entqy MANAGEMENT MANUAL lNFORMATlONAL USE PAGE 80F22 (c) -

JAF, IPEC ASME Section XI Subsection IWE and IWL, 1992 Edition including 1992 Addenda; VY - 1998 Edition with Addenda through 2000.

(1) The illumination of light source shall be measured using a calibrated light meter or the lighting verified to be adequate in resolving the lower case test characters of an approved test chart or character card meeting the requirements of ASME Section XI, IWA-2210.

a. The minimum illumination of a light source when using a light meter shall be 5 0 4 candles for inspection.
b. The illumination levels from battery powered portable lights shall be checked before and after each examination or series of examinations not to exceed four hours between checks.
c. Measurement of the illumination level on each examination surface is not necessary when the same portable light source or similar installed lighting equipment is demonstrated to provide the specified illumination at the maximum distance.

(d) PNPS - ASME Section XI 2001 Edition through 2003 Addenda (1) Resolution of the specified characters (0.044 in.} can be used in lieu of illumination measurement to verify illumination adequacy.

(2) Minimum illumination of a light source when using a light meter shall be 50 ft-candles for inspection.

(3) If illumination measurement is performed, it is not necessary to measure the illumination level on each examination surface when the same portable nonbattery-powered (e.9. drop light) or similar installed lighting equipment is demonstrated to provide the illumination specified at the maximum examination distance.

(4) When illumination measurement is performed during the examination and a battery-powered light is used, the adequacy of the illumination level shall be checked before and after each examination or series of examinations, not to exceed 4 hr between checks.

(e) IP2 RR-9rt , 1Or1 and IP3 RR Examination of Nozzle Inner Radius sections (1) All nozzles (except the pressurizer surge nozzle 251R at IP3 and PZRS1&6 at IP2) shall be examined using a remote color video camera with resolution sensitivity capable of detecting a 1-mill width wire or crack. This enhanced VT-I (Em-1) is consistent with the requirements found in the latest version of 1oCFR50.55a(b)(2)(xxi)(A).

I I I I I i aEn&gy

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NUCLEAR MANAGEMENT QUALITY RELATED ENN-NDE-10.01 REV. 2 MANUAL lNFORMATlONAL USE PAGE 9OF22 5.5 S URFACE PREPARATION PI Visual examinations that require clean surfaces or decontamination for valid interpretation of results shall be preceded by appropriate cleaning processes.

E21 Mechanical or chemical cleaning processes may be used, if required, to remove contaminants such as carbon, rust, scale, or coatings.

~31 The presence of protective coatings, and general oxidation, unless flaking or thickness reduction has occurred, is acceptable for VT-1 examination of integral attachment welds.

5.6 EXAMI NAT1ON E11 All relevant conditions observed during an examination that may require supplemental examination, corrective measures, repair, replacement or analytical evaluation shall be identified.

(a) Relevant conditions do not include fabrication marks, scratches, surface abrasion, material roughness and any other conditions acceptable by material, design and manufacturing specifications.

Examination of Pressure Retaining Bolting General (1) The VT-1 examination shall be conducted to detect discontinuities and imperfections such as cracks, wear, corrosion, or physical damage.

(2) Bolting may be examined in place under tension, when the connection is disassembled, or when bolting is removed. Code and Relief Request requirements for disassembly of connections should be identified by the work order.

VT-1 Examination of bolting greater than 2" in diameter (Category 6-G-1).

(1) Examine nuts, bushings, washers and flange surfaces.

a. Bushing and threads in base metal of flanges require examination only when the connections are disassembled. Bushings may be examined in place.
b. Flange surface examinations include 1-inch annular surface of the flange surrounding each stud.

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2

'w MANAGEMENT MANUAL INFORMAllONAL USE PAGE 1oOF22 (c) VT-1 Examination of bolting 2" and less in diameter (Category 8-G-2).

(1) Examine bolts, studs, and nuts.

(2) CRD Flange Bolting (JAF RR-14).

a. The visual examination (VT-1) will be performed on all accessible surface areas of the bolts.
b. Augmented surface (Liquid Penetrant) examinations shall be performed on all areas of CRD bolting with relevant indications or suspect areas. New design bolting intended for reuse shall require a VT-1 and an augmented surface examination.

(d) VT-1 Examination, Class MC Pressure Retaining Bolting (Category E-A, E-G)

(1) VT-1 Examination of Pressure Retaining Bolting is conducted to detect defects which may cause the bolted connections to violate leak-tightness or structural integrity.

a. Examination of bolted connections includes bolts, studs, nuts, bushings, washers, and threads in base material and flange figaments between threaded stud holes.
b. Examination of bushings, threads, and ligaments in base material of flanges is required only when the connection is disassembled.

(e) VT-1 Examination of pressure retaining bolting shall include the following attributes:

(1 ) Crac k-like flaws (2) Thread damage (deformed or sheared threads)

(3) Corrosion /Wear (4) Physical damage (bending, twisting or deformation)

(5) Missing / Loose bolting (6) Fractured bolts, studs or nuts (7) Degradation of protective coating (8) Evidence of coolant leakage near bolting

a

  • En&yg NUCLEAR MANAGEMENT Q u ~ uRELATED n ENN-NDE-10.01 PAGE 11 OF22 REV. 2 MANUAL lNFORMATlONAL USE

[3] Examination of Integral Attachment Welds (Category D-A and 1P2 RCP integral welded attachments per RR-38).

(a) Examine all surfaces of Integral Attachment Welds for evidence of the following:

(1) Crack-like surface flaws.

(2) Structural degradation of the attachment welds.

[4] Examination of Nozzle Inner Radius sections (IP2 RR-9rl , 1Or1 and 1P3 RR-16)

(a) All nozzles (except the pressurizer surge nozzle 25lR at IP3 and PZRS1&6 at 1P2) shall be examined using a remote color video camera with resolution sensitivity capable of detecting a 1-mill width wire or crack.

(b) Examine all interior surfaces for evidence of the following:

(1) Crack-like surface flaws.

(2) Structural degradation

[5] Examination of Coated and Non Coated Containment Surfaces Requiring Augmented Examination (Category E-C)

(a) Examination attributes for containment surfaces.

(1) Examine all (visible) painted or coated containment surfaces for evidence of the following:

a. Flaking
b. Blistering
c. Peeling
d. Discoloration
e. Any other signs of distress (2) Examine all (visible) non-coated containment surfaces for evidence of the folfowing:
a. Cracking
b. Discoloration
c. Wear

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2 "E'tersy MANAGEMENT MANUAL [NFORYATIONALUSE PAGE 1 2 O F 2 2 t I I VT-1 EXAMINATION I

I

d. Pitting
e. Erosion / Corrosion
f. Arc Strikes
g. Gouges
h. Surface Discontinuities
i. Dents
j. Any other signs of surface irregularities

[6] Examination of Concrete Surfaces (a) Visual examinations are conducted to determine concrete deterioration and distress for suspect areas detected by general or VT-3 examinations, and conditions (e.g., cracks, wear, or corrosion) of tendon anchorage and wires or strands.

(b) Visual examination of concrete surfaces shall be examined for evidence of:

(1 ) Cracking / Checking (2) Abrasion (3) Blistering (4) Delaminations (5) Efflorescence (6) Peeling (7) Pitting (8) Popouts (9) Scaling (10) Spalling (11 Other signs of distress.

NUCLEAR QUALITY REL&TED ENN-NDE-10.01 REV. 2 MANAGEMENT MANUAL lNfORMATlONAL USE PAGE 130F22

[2] Any relevant condition observed during an examination that may require supplemental examination, corrective measures, repair, replacement or analytical evaluation shall require engineering evaluation for continued service.

[3) Pressure retaining bolting (B-G-1, B-G-2, E-A and E-G).

(a) Visual examinations detecting the following relevant conditions shall be considered unacceptable and processed in accordance with the site IS1 or corrective action program.

(1) Crack-like flaws that exceed the allowable linear flaw standards of IWB-3515.

(2) More than one deformed or sheared thread in the zone of thread engagement of bolts, stud, or nuts.

(3) Localized general corrosion that reduces the bolt or stud cross-sectional area by more than 5%.

(4) Bending, twisting, or deformation of bolts or studs to the extent that assembly or disassembly is impaired.

(5) Missing or loose bolts, studs, nuts, or washers.

(6) Fractured bolts, stud, or nuts.

(7) Degradation of protective coatings on bolting surfaces.

(8) Evidence of coolant leakage near bolting.

[4] Integral Attachment Welds (Category D-A and lP2 RCP integral welded attachments per RR-38).

(a) Visual examinations detecting the following relevant conditions shall be considered unacceptable and processed in accordance with the site IS1 or corrective action program.

(1) Crack-like surface flaws that exceed the allowable linear flaw standards of IWB-3516.

(2) Structural degradation of the attachment welds such that the original cross-sectionalarea is reduced by more than 10 percent.

NUCLEAR QUALITYRELATED ENN-NDE-10.01 REV. 2

-zz= Entergv MANAGEMENT MANUAL INFORMATIONAL USE PAGE 140F22 Examination of Nozzle Inner Radius sections (IP2 RR-9r1, lor1 and lP3 RR-16)

(a) Visual examinations detecting the following relevant conditions shall be considered unacceptable and processed in accordance with the site IS1 or corrective action program.

(1) Crack-like surface flaws that exceed the allowable linear flaw standards Of IWB-3512.

(2) Structural degradation such that the original cross-sectionalarea is reduced by more than 10 percent.

Coated and Non Coated Containment Surfaces Requiring Augmented Examination (Category E-A, E-C)

(a) The containment IS1 program shall specify the site requirements for acceptance of VT-1 visual examinations.

(b) Acceptance of IWE examinations shall be by engineeringevaluation or based on site-specific acceptance criteria for the visual examination of Containment Surfaces.

Examination of Concrete Surfaces (Category LA, LB)

(a) The containment 1SI program shall specify the site requirements for acceptance of VT-1 visual examinations.

(b) Acceptance of IWL examinations shall be by engineering evaluation or based on site-specific acceptance criteria for the visual examination of Containment Surfaces.

INTERFACES None RECORDS Examination results shall be evaluated in terms of the applicable acceptance criteria and documented on Attachment 9.1 through 9.6or similar forms.

Examination reports shall be reviewed per ENN-NDE-1.OO requirements.

a "En&yp NUCLEAR MANAGEMENT QUALITY RELATED INFORMATIONAL USE ENN-NDE-10.01 REV. 2 MANUAL PAGE 15 OF 22

[3] Examination reports shall be processed per site requirements and as a minimum, shall include the following:

(a) NDE report number / Identification (b) Examination procedure and revision (c) Component examined (d) Equipment used (e) Examination results (f) Names and certification levels of examination personnel (9) Examination date 8.0 OBLIGATION AND REGULATORY COMMITMENT CROSS-REFERENCES 8.1 OBLIGATIONSAND COMMITMENTS IMPLEMENTED OVERALL Step Document Commitment Number

[I] Nuclear Regulatory Commission, 10 CFR None Part 50, Industry Codes and Standards.

[2] Entergy Quality Assurance Program None Manuat, Section B.ll, "Special Process Control"

[3] ASME Boiler & Pressure Vessel Code, None Section XI, 2001 Edition, including 2003 Addenda.

[4] ASME Boiler & Pressure Vessel Code, None Section V and XI, 1998 Edition through 2000 Addenda.

[5] ASME Boiler & Pressure Vessel Code, Section V and XI, 1992 Edition, including 1992 Addenda.

[6] ASME Boiler & Pressure Vessel Code, Section XI, 1989 Edition no Addenda,

a

-Entw NUCLEAR MANAGEMENT QUALITY RELATED ENN-NDE-10.01 PAGE 16OF22 REV. 2 MANUAL INFORMATIONAL USE 8.2 SECTION SPECIFIC OBLIGATIONS AND COMMITMENTS Document Section 1 Commitment 1 Number ASME Boiler 8t Pressure PNPS - Section 5.2, 5.4 None Vessel Code, Section XI, 2001 Edition, including 2003 I Addenda.

[2] ASME Boiler & Pressure -

VY Section 5.2, 5.4 None Vessel Code, Section V and Xi, 1998 Edition through 2000 Addenda.

[3] ASME Boiler & Pressure JAF, IPEC - Section 5.2, None Vesset Code, Section V and XI, 1992 Edition, including 1992 Addenda.

[4]

.~

ASME Boiler 8t Pressure -

JAF, IPEC Section 5.2, None Vessel Code, Section XI, 5.4 1989 Edition no Addenda.

8.3 SITE SPECIFIC COMMITMENTS Step Site Document Document Section Commitment Number

[l] JAF Third In-service Section 5.2, 5.4 RR-4, RR-14 and Inspection Interval Relief RR-27 Request.

[2] IP2 Third In-service Section 5.2, 5.4, RR-9, RR-10, RR-Inspection Interval Relief 5.6[3],5.7[4] 38 Request

[3] IP3 Third In-service Section 5.2, 5.4 RR-16 inspection Interval Relief Request

[4] PNPS Fourth In-service Section 5.2, 5.4 PIL-05-R-002 Inspection Interval Relief Request

a "Entw NUCLEAR MANAGEMENT QUALiTV RELATED ENN-NDE-10.01 REV. 2 MANUAL 1NFORMATlONAL USE PAGE 17OF22 VT-1EXAMINATION 1 9.0 ATTACHMENTS 9.1 VT-1 Examination Report (BOLTING) 9.2 VT-1 Examination Report (INTEGRAL ATTACHMENT WELDS) 9.3 VT-1 Examination Report (NOZZLE INNER RADIUS) 9.4 VT-1 Examination Report (CONTAINMENT SURFACES) 9.5 VT-1 Examination Report (CONCRETE SURFACES)

mEntqy

-=z-NUCLEAR MANAGEMENT QUALITY RELATED ENN-NDE-10.01 PAGE 18OF22 REV. 2 MANUAL lNFORMATlOWL USE ATTACHMENT 9.1 VT-1 EXAMINATION REPORT (BOLTING)

Work Document: Component: Report No.:

r System: Drawing: Page of Line #: [7 Direct 0Remote Equipment:

nLight Meter (aN/A)

Bolting Attributes Acc Rej W A Comments I

Crack-like flaws u u u Thread damage u c l o Corrosion /Wear IZJDCI Physical damage 0 0 0 Missing / Loose bolting UCICI Fractured bolts, studs or nuts 0 0 c]

Degraded of protective coating [z1 Coolant leakage near bolting 0 Other C I U U D C I O 0 0 UI n o u O D D D U O 0 0 0 n u u Acceptance Criteria: ASME Section XI 1998 Edition, 2000 Addenda Remarks:

Examiner Level Date Examiner Level Date I

Review Level Date 1 ANI1 Date

NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2 Entergy MANAGEMENT MANUAL INFORMATIONAL USE PAGE 19OF22 ATTACHMENT9.2 VT-1 EXAMINATION REPORT (INTEGRALATTACHMENT WELDS)

Work Document: Component: Report No.:

System: Drawing: Page of o c l n 0 0 0 0 0 0 0 0 0 n u n 0 0 0 0 0 0 0 0 0 0 0 0 o o n 0 0 0 I

I Review Level Date I ANI1 Date

aEntersy NUCLEAR MANAGEMENT QUALITY RELATED ENN-NDE-10.01 REV. 2 MANUAL lNFORMATlONAL USE PAGE 200F22 ATTACHMENT 9.3 . VT-1 EXAMINATION REPORT (NOZZLE RADIUS)

INNER Work Document: Component: Report No.:

System: Drawing: Page of Line #: 0Direct 0Remote Equipment:

0Light Meter (0 N/A)

Nozzle IR Attributes I Acc Rei NIA I Comments Crack-like surface flaws lo 0 Ol Structural degradation Io 0 n Other I O 0 In 0 I O cl lo 0 I O cl I O 0 I O I O cl 0 IO 0 I O cl 0 In 0 lo 0 I O 0 0 In 0 0

a"Entergy NUCLEAR MANAGEMENT QUALITY RELATE^

lNFORMATlONAL USE ENN-NDE-10.01 REV. 2 MANUAL PAGE 21 OF22 I I A ~ A C H M E N9.4 T VT-1 EXAMINATIONREPORT (CONTAINMENT SURFACES)

System: Drawing: Page of Remarks:

Examiner Level Date Examiner Level Date Review Level Date ANI1 Date

I I I I 1 NUCLEAR QUALITY RELATED ENN-NDE-10.01 REV. 2

-==- Entersy MANAGEMENT MANUAL INFORMATIONAL USE PAGE 2 2 0 F 2 2 VT-1 EXAMINATION L AITACHMENT9.5 VT-1 EXAMINATION REPORT (CONCRETE SURFACES)

Work Document: Component: Report No.:

System: Drawing: Page of Remarks:

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