ML070680157

From kanterella
Jump to navigation Jump to search
(3) ENN-NDE-10.03, Rev. 1; VT-3 Examination, 02/02/2006
ML070680157
Person / Time
Site: Indian Point, Pilgrim, Vermont Yankee, FitzPatrick  Entergy icon.png
Issue date: 02/02/2006
From: Limpias O
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
ENN-NDE-10.03, Rev 1
Download: ML070680157 (27)


Text

I 1 NUCLEAR 11 QIJAUTVRELATED 1 ENN-NDE-10.03 I

REV.l 1 IHFORMATIONALUSE PAGE 1 OF27 i I 1 ProcedureOwner: I Oscar Limpid 1 Vibe President Engineering I I (Print Name //Title)I Approved: / $ $- y-2 GGNS uatcf IPEC Exception JAF WPO Procedure Contains NMM REFLl8 Forms: YES NO Basis Statement ENN-NDE-10.03 Reviston 1 includes:

Procedure reformatted per EN-AD-1 91 requirements.

PNPS requirements changed to reflect IS1 interval change.

Added reference to ASME Boiler & Pressure Vessel Code,Section XI, 2001 Edition, including 2003 Addenda Paragraph 1.0[4] Clarified paragraph to distinguish BWR VIP program Added reference to ENN Site Relief Requests Added reference to ENN-NDE-1.OO NDE personnel section added for consistency with ENN procedures.

Added requirement for documenting procedure qualifications Paragraph 5.2 121 (e) clarified.

PNPS VT-3 requirement for integral attachments removed.

Revised examination report review requirements Revised obligations and commitments per EN-AD-101requirements.

Added sample NDE report forms with attributes for examinations.

Site and NMM Procedures Canceled or Superseded Bv This Revision ENN-NDE-10.03Revision 0 Process Amlicabilitv Exclusion IENN-LI-100)/ Proaramrnatic Exclusion f ENS-LI-101)

All Sites: @ Specific Sites: AN0 0 GGNS IPECC] JAF 0 PNPSD RBS W 0 W3

I I I I I TABLE OF CONTENTS Section -

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

2.0 REFERENCES

.........................................  ;............................................ 3 3.0 DEFINtTIONS ........................................................................................4 4.0 RESPONSIBILITIES..............................................................................4 5 .o DETAILS ................................................................................................ 4 6.0 INTERFACES ...................................................................................... 16 7.0 RECORDS...........................................................................................16 8.0 REQUIREMENTSAND COMMITMENT CROSS-REFERENCE ........t 7 9.0 AfTACHMENTS.................................................................................. 18 ATTACHMENT9.1 VT-3 EXAMINATION REPORT(PUMP CASINGS AND VALVE BODIES) ..................................................... 20 AT~ACHMENT9.2 VT-3 EXAMINATION REPORT{COMPONENT SUPPORTS) ........................................................... 21 ATTACHMENT9.3 VT-3 EXAMINAT~ON REPORT(SNUBBERS) ..............22 ATTACHMENT 9.4 VT-3 EXAMINATION REPORT(CONTAINMENT SURFACES)........................................................... 23 ATTACHMENT9.5 VT-3 EXAMINATION REPORT (CONTAINMENT MOISTURE BARRIERS)...........................................24 AUACHMEWT 9.6 VT-3 EXAMINATION REPORT(CONTAINMENT PRESSURE RETAININGBOLTING) ............................25 ATTACHMENT9.7 SUPPORT WMINATION BOUNDARIES (TYPICAL) ...... 26 ATTACHMENT 9.8 INTEGRAL ATTACHMENT COMPONENT SUPPORT -

DETAIL .................................................................. 27

i I NUCLEAR j QUALITYRELATED 1 ENN-NDE-10.03 1 REV. I Enw 1 I

MANAGEMENT MANUAL 1 lNFoRMAnorVAi.USr 1 j

PAGE 3OF27 b

VT-3 EXAMINATION This procedure establishes the methods and requirements to be used for ASME Section XI VT-3 examination of components.

The VT-3 examination shall be conducted to determine the generat mechanical and structural condition of components and their supports, such as verification of clearances, settings, physical displacements, loosed or missing parts, debris, corrosion, wear, erosion, or the loss of integrity at bolted or welded connections.

The VT-3 examination shall include examination for conditions that could affect operability or functional adequacy of snubbers, constant toad and spring type supports.

This procedure is @ applicable to VT-3 examinations performed per the In-vessel 2.0 Visual Inspection (IWI)BWR VIP program.

REFERENCES I

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 Addenda.

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

ASME loiter and Pressure Vessel Code, Code Cases ENN Site Specific Relief Requests, Reference Section 8.0 Regulatory Guide 1.147 Inservice Inspection Code Case Acceptability I

ASMEYANSI OM Code, Part 4, 1988 edition and 1995 edition through 2000 Addenda ENN-NDE-1.OO,Administrative Controls for Non-destructive Examination ENN-NDE-2.12, Certification of Visual Testing (VT) Personnel.

ENN-NDE-10.01, VT-1 Examination

fl3] ENN-NDE-10.02, VT-2 Examination 3.0 DEFINITIONS

[I] Reference ASME Boiler and Pressure Vessel Code, Sections V and XI, for the gtossary of terms used in Nondestructive Examination (NDE).

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

ENTERGY NDE LEVEL ill The Entergy Level Ill is responsible for development, interpretation and qualification of this procedure.

The Entergy Level 111 is responsible for demonstration of this procedure to the ANI1 when requested.

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

Level 11 or 111 personnel shall be responsible for the examination and interpretation of results.

tevet I and trainee (Level IT) personnel may be used to assist in performing examinations. Final interpretation of collected data shall be the responsibility of the Level I I or Ill examiners.

5.0 DETAILS 5.1 PRECAUTIONS AND LIMITATIONS

[I] None

"Enfwg i i

MANAGEMENT MANUAL

-I--L---

j lNFORMATlONALUSE j PAGE 5 0 F 2 7 VT.3 EXAMINATION PROCEDURE DEMONSTRATION Procedure demonstrations shall be documented and contain or reference the examination techniques required to meet the Code requirements in the following paragraphs.

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 f8% neutral gray card may be used.

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

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

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 setected type size meets the requirements of Table IWA-2210-1.

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 far which the visual examination is performed can be detected at the chosen distance and iIlumination.

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.9. a, c, e, o), that meets the requirements of Table IWA-2211-1 is required.

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

I I I I

I NUCLEAR j QWTYRELATEO ENN-NDE-10.03 i REV. 1

-- I En'm 1

i MANAGEMENT MANUAL

- - - _ II I

i lNFoRMATI0NALUSE I

1 1

PAGE 60F27 4

VT-3 EXAMINATION 5.3 EQUIPMENT

[I] The folfowing or additional equipment may be used as determined necessary by the examiner:

Flashlights / Drop Lights Light Meter Mirrors Magnifying Lenses Binoculars Telescopes Tape Measure / Six Inch Scales Borescopes Fiber Optics Cameras 5.4 ACCESS AND ILLUMiNATlON (LIGHTING)

[I] Accessibility (a} JAF, IPEC - ASME Sections Xi, 1989 Edition, no Addenda (1) For component supports and component interiors, the visual examination may be performed remotely with or without optical aids to verify the structural integrity of the component.

i I

NUCLEAR Q u m RELATED 1 I

I ENN-NDE-10.03 REV. 1 i MANAGEMENT t

I VT-3 EXAMlNATlON I -

I (b) -

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

(1) For direct examination, the maximum examination distance of four 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) There are no direct visual examination distance requirements, provided the examiner can resolve the characters (0.105 in.) specified in Table iWA-2211-t .

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

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

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

Illumination (Lighting)

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

(b) ASME Sections XI, 1989 Edition, no Addenda (1) Lighting conditions (either natural or artificial) shall be adequate in order to illuminate areas to be examined for the detection of recordabfe conditions.

i NUCLEAR Q U A L ~ R E L A ~

i MANAGEMENT I I I i I VT-3 EXAMINATION

_-x_-_-

I _

(c) ASME Section XI 1992 Edition, including f 992 Addenda and 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 illurnination of a light source when using a fight meter shall be 50-f-t 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 ofthe 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 Resolution of the specified characters (0.044 in.) can be used in lieu of iff umination measurement to verify iffurnination adequacy.

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

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.g. drop light) or similar installed lighting equipment is demonstrated to provide the illurnination specified at the maximum examination distance.

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

I

NUCLEAR j QufifnRmRO 1 ENN-NDE-10.03 REV. 1 MANAGEMENT -

fw@ MANUAL I INFORMATIONMUSE j I PAGE 9OF27

-L 1

VT-3 EXAMINATION SURFACE PREPARATION Visual examinations that require clean surfaces or decontamination for vatid interpretation of results shall be preceded by appropriate cleaning processes.

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

The presence of protective coatings, and generaf oxidation, unless flaking or thickness reduction has occurred, is acceptable for VT-3 examination of component supports.

EXAMINAT10N Ail 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 inctude fabrication marks, scratches, surface abrasion, material roughness and any other conditions acceptable by material, design and manufacturing specifications.

Support Examination Boundaries The boundary of an integral attachment connected to a pressure-retaining component is the distance from the pressure-retaining component as indicated in attachment 9.7.

The boundary of an integral support or non-integral support connected to the building structure is the surface of the building structure.

The boundary of a non-integral support connected to a pressure-retaining cornponenf is the contact surface between the component and support.

Where the mechanical connection of a non-integral support is buried within the component insulation, the support boundary may extend from the surface of the component insulation provided the support either carries the weight of the component or serves as a structural restraint in compression.

The examination boundary of an intervening element shall include the attachment portion (welds, bolting, pins, clamps, etc.) of the intervening element to pressure retaining components, integral and non-integral attachments of pressure retaining components, and integral and non-integral supports. The examination boundary does not include the attachment of the intervening element to the building structure.

t j L VT-3 EXAMiNATION (f) All integral and non-integral connections within the 1WF support examination boundary are included.

131 Pump Casings and Valve Bodies (8-L-2 & 3-M-2)

(a) Examine all interior surfaces of the valve or pump pressure-retaining boundaries, (b) Examine all areas within the specified boundary for:

(1) Erosion / Corrosion (2) Wear (3) Crack-like surface flaws

[4] Component Supports (F-A)

(a) Examine all integral and non-integral connections, intermediate members within the IWF examination boundary inciuding welded and bolted connections to the pressure retaining components, building structures, and at intermediate joints. Examination of component supports shall include:

(1) Deformation or structural degradation (2) Integrity of mechanical (e.g., bolted) or welded connections (3) Corrosion (4) Wear (5) Missing, detached or loose support items (6) Degraded close tolerance machined or sliding surfaces (7) Improper hot or cold positions of spring supports and constant load supports (8) Misalignment (9) Clearances of guides and stops

i I

NUCLEAR I QUAL~TYRELATEII j ENN-WE-10.03 REV. 1

- ~ 1 MANAGEMENT

~ f i ~

PAGE 11 OF27

MANUAL INTORMAT~OMALUSE j

v ~ I EXATATION 3

[SI Snubbers (ASMWANSI OM Code, Part 4, 1988 edition and 1995 edition through 2000 Addenda)

(a) Examination of integrai and non-integral attachments for Snubbers including lugs, bolting pins and clamps shall be examined in accordance with the above requirements for component supports. In addition, snubber examinations shall include:

(1) Signs of damage or impaired operabifity (2) Load ratings, tocation, orientation, position setting and configuration (3) Swing clearance (4) Fluid level or indication of fluid level for hydraulic snubbers (5) Structural connections (6) Physical damage, leakage, corrosion or degradation from environmental exposure or operating conditions (7) Loose fasteners, missing hardware, deformed members or disconnected components (8) Restricted thermal movement (evidence of binding, misalignment or deformation)

[6] General Visual Examination of Containment Surfaces (a) General Visual examinations shall be performed in accordance with the Sites Containment Inservice Inspection Program.

[7] Examination of Containment Surfaces (E-A)

(a) The examination may be made from either the inside or outside surface.

(b) The examination shalt include structures that are parts of reinforcing structure, such as stiffening rings, manhole frames and reinforcement around openings.

I I

NUCLEAR MANAGEMENT I

QUALIWR~AW I

ENN-NDE-10.03 I

i REV. 1 i

fe@i MANUAL INFORMATIONALUSE f PAGE 12OF.27

-_..- - i VT-3 EXAMINATION (2) Blistering (4) Discoloration (d) The inspected area, when not coated, shall be examined in accordance with the Sites Containment inservice Inspection Program for evidence of:

(1) Cracking (2) Discoloration (3) Wear (4) Pitting (5) Excessive corrosion (6) Arc strikes (7) Gouges (8) Surface discontinuities (9) Dents (10) Other signs of surface irregularities

I I

VT-3 EXAMlNATtON I Examination of Containment Moisture Barriers (E-A, f 998 Edition with Addenda through 2000. / 43, 1992 Edition including 1992 Addenda).

(a) Examination of moisture barriers include the internal and external containment moisture barrier materials at the concrete-to-metal interfaces intended to prevent the intrusion of moisture against the pressure retaining metal containment shell or liner.

(1) Examine the moisture barrier in accordance with the Sites Containment Inservice Inspection Program for evidence of:

a. Wear
b. Damage C. Erosion
d. Tear
e. Surface cracks
f. Other defects that may violate the leak-tight integrity E9 VY, PNPS - Examiliation of Containment Pressure Retaining Bolting (a) Examination of Pressure Retaining Bolting is conducted to detect defects, I

which may cause the bolted connections to violate leak-tightness or structural integrity.

(b) Examination of bolted connections includes bolts, studs, nuts, bushings, washers, and threads in base material and flange ligaments between threaded stud holes.

(c) Examination of bushings, threads, and ligaments in base material of flanges is required only when the connection is disassembled.

(d) VT-3 Examination of pressure retaining bolting shall include the foflowing attributes:

(1) Missing / Loose bolting (2) Containment leak tightness (3) Structural Integrity

I i 1 QUA~J~REUTED i

ENN-NDE-10.03 i REV. 1

_I_

MANAGEMENT PAGE 14 OF 27 b

F

  • R VT-3 EXAMINATION Y
  • n i M I IL U P E

[11 7 b! \ L i 3 ; / r v l b U C ~ ~ . CJL?

Components whose visual examination confims the absence of the relevant I c l ~ k d J J conditions described in the examination section of this procedure shall be considered acceptable for continued service.

[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.

[3f Pump Casings and Valve Bodies (64-2 & B-M-2)

(a) The following relevant conditions must be recorded as unacceptable:

(11 Erosion or corrosion that reduces the pressure retaining wall thickness by more than ten percent (10%).

(2) Wear of mating surfaces that may tead to a loss of function or leakage.

(3) Crack-like surface indications developed in service or grown in size beyond that recorded during presewice visuat examination.

f4] Component Supports (F-A)

(a) The following relevant conditions must be recorded as unacceptable:

(I) Deformation or structural degradation of fasteners, springs, clamps, or other support items (2) Missing, detached, or ioosened support items (3) Arc strikes, weld spatter, paint, scoring, roughness, or general corrosion on close tolerance machined or sliding surfaces (4) improper hot or cold settings of spring supports and constant load suppofts (5) Misafignment of supports (6) Improper displacement settings of guides and stops

1 NUCLEAR I QUJWTYRELATED ENN-NDE-10.03 1 REV. 1 1

i MANAGEMENT EnfwB MANUAL 1 lNFORMATlONAtUSE \ PAGE 1 5 0 F 2 7

--  ! I VT-3 EXAMINATiON

[5] Snubbers (ASMWANSI OM Code, Part 4,1988 edition and 1995 edition through 2000 Addenda)

(a) Snubbers Any visible signs of damage or impaired operabitity as a result of storage, handling, or installation.

Load ratings, location, orientation, position setting and configuration (attachments, extension, etc.) are in accordance with design drawings and specifications.

Adequate swing clearance is provided to allow snubber movement.

For hydraulic snubbers, fluid is at the recommended level and is not leaking from the snubber system.

a. Hydraulic snubber fluid level less than the minimum amount required for actuation. Fluid level is considered acceptable when the fluid level is equal to or greater than the minimum amount that is sufficient for actuation at its operating extension.
b. Fluid level for tisaga snubbers is indicated by the color of the site glass.

Structural connections such as pins, bearings, studs, fasteners and other connecting hardware; such as lock nuts, tabs, wire and cotter pins are installed correctly.

Impaired functional ability due to physical damage, leakage, corrosion or degradation from environmental exposure or operating conditions.

Snubbers shai be installed so that they can carry the load; Le., loose fasteners, missing hardware, deformed members or disconnected components.

Snubbers shall be instatled in such a condition that they do not restrict thermal movement of the pipe or component.

a. Evidence of binding, misalignment or deformation.

I i

NUCLEAR 1 QUAUTYRELATEO ENN-NDE-10.03 i

1 REV. 1

[6] General Visual Examination of Containment Surfaces (a) The Containment IS1 program shall specify the site requirements for acceptance of Genera! visual examinations.

[7] VT-3 Examination 05 Containment Surfaces (E-A)

(a) The Containment 1st program shall specify the site requirements for acceptance of VT-3 visual examinations.

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

[8] Examinationof Containment Moisture Barriers (E-A, I998 Edition with Addenda through 2000. / E-D, 1992 Edition inctuding 1992 Addenda}.

(a) The Containment IS1 program shall specify the site requirements for acceptance of VT-3 visual examinations.

(b) Moisture barriers with wear, damage, erosion, tear, surface cracks, or other defects that permit intrusion of moisture against inaccessible areas of the pressure retaining surfaces of the metal containment shell or liner shall be corrected.

[9] -

W, PNPS Examination of Containment Pressure Retaining Bolting (a) Flaws or degradation identified during the performance of a VT-3 examination must be examined in accordance with the VT-1 examination method. The criteria in the material specification or IWB-3517.1 must be used to evaluate containment bolting flaws or degradation.

6.0 INTERFACES

[l] None 7.0 RECORDQ

[If Examination results shall be evaluated in terms of the applicable acceptance criteria and documented on Attachment 9.1 through 9.6 or similar farms.

[2] Examination reports shall be reviewed per ENN-NDE-1.OOrequirements.

1 I

Q~AwY~~ELAT~ ENN-NDE-10.03 1I

MANAGEMENT  ;

i

!I lNFORMAllONAF USE I

PAGE 17 OF 27 I VT-3 E X A M I N A T I ~ ~

I 1

[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 (e) Component examined (d) Equipment used (e) Examination results (f) Names and certification levels of examination personnel (9) Examination date 8.0 REQUIREMENTS AND COMMITMENT CROSS-REFERENCE I Step Document Commitment Number ,

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

Entergy Quality Assurance Program Manual, Section B.ll, "Speciaf None Process Control" ASME Boiler & Pressure Vessel Code,Section XI, 2001 Edition, None including 2003 Addenda.

ASME Boiler & Pressure Vessel Code,Section V and XI, t998 Edition None through 2000 Addenda.

ASME Boiler & Pressure Vessel Code,Section V and Xf, 1992 Edition, None including 1992 Addenda.

ASME Boiler & Pressure Vessel Code,Section XI, 1989 Edition no None Addenda.

r 1 Entprgy 11 1

NUCLEAR MANAGEMENT I

1L 1

I Q~AL~WRUATED

~NFORMATIONALUSE I

j 1

I ENN-NDE-10.03 I

i MANUAL I PAGE 18 OF 27

! I iI I VT-3 EXA~INATION 1 8.2 SECTION SPECIFIC OBLIGATIONS AND COMMITMENTS Step Document Document Section 1 Commitment Number

[I J ASME Boifer & Pressure Vessel PNPS - Section 5.2, 5.4, None Code,Section XI, 2001 Edition, including2003 Addenda.

p] ASME Boifer & Pressure Vessel -

PNPS, VY Section 5.2, 5.4, None Code,Section V and XI, 1998 5.6191, 5.7[9]

Edition through 2000 Addenda.

[3] ASME Boiler & Pressure Vessel JAF, IPEC - Section 5.2, 5.4 None Code,Section V and XI, I992 Edition, including 1992 Addenda.

141 ASME Boiler 8t Pressure Vessel -

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

Step Site Document 1 Document Section Commitment Number El] JAF Third In-service inspection Section 5.2, 5.4 RR-27 Interval Relief Request.

[2] IP2 Third In-service Inspection Section 5.2, 5.4 RR- 33, RR-42 and RR-Interval Relief Request 49.

[3] IP3 Third In-service Inspection Section 5.2, 5.4 RR-3-1 (H), RR-3-5 (H)

Interval Relief Request and RR-3-24(C)

. [4] PNPS Fourth In-service Inspection Section 5.2, 5.4 P f L-05-R-002

, Interval Relief Request 9.0 ATTACHMENTS NOTE Sample forms used to implement this procedure are listed above. It is not mandatory that the forms included in this procedure be used. Equivalent forms may be used that contains all the required code information.

9.1 Sample VT-3 Examination Report (Pump Casings and Valve Bodies) 9.2 Sample VT-3 Examination Report (Component Supports) 9.3 Sample VT-3 Examination Report (Snubbers) 9.4 Sample VT-3 Examination Report (Containment Surfaces) 9.5 Sample VT-3 Examination Report (Containment Moisture Barriers) 9.6 Sample VT-3 Examination Report (Containment Pressure Retaining Bolting)

-~ I t VT-3 EXAMINATEPI 9.7 Support examination boundaries (Typical) 9.8 -

Integral attachment component support detail (Typical)

I VT-3 EXAMINATION I

Review Lwei Date ANI1 Date L

i ATTACHMENT 9.2 VT-3 EXAMINATIONREPORT (COMPONENT SUPPORTS)

Work Document: Component: Report No.:

Deformed / degraded comp. IO aln Mechanical / welded connection I a Corrosion 10 Lf Missing, loose support items ;Ellolo Degraded close tolerance surf. c]

lmproper support settings I n 0 El Misalignment I n a cf Clearances of guides/stops a OIO El n l o 0 nlo cl 010 c] O D R 010l Serial Number: alaio Required Setting = 01 10 Actualsetting=

Examiner Lzvel Date Examiner Level Date

I I I

I i NUCLEAR 1

1 O~~WRELATU) ENN-NOE-30.03 1 REV. 4 w1 1

I MANAGEMENT I INFOR#mATiONAL~SE PAGE 2 2 0 F 2 7 MANUAL I I

1

___~

ATTACHMENT 9.3 VT-3 EXAMINATION REPORT (SNUBBERS)

Work Document: Component: Report No.:

I I

I System: Drawing: Page of Examiner Levct Date Examiner Level Date

1 I i

QUALINRELATE~

1 ENN-NDE-10.03 I I

REV. 1 I NUCLEAR "Enipqy MANAGEMENT I j lNF0RMnTlONALUSE I PAGE&-2-"3--0-.-F-2 7 MANUAL I

_I_ _

i -

.Examiner Level Date Examiner LeveE Date 1

1 I

Review Level Date I ANI1 Date I

i i  !

NUCLEAR i

j QUfilNREum 1 f

ENN-NCIE-10.03 i REV. 1 MANAGEMENT  !

MANUAL '! lNFORMAVONAL USE I PAGE 24OF27

--- -l_ l-I I -

VT-3 EXAMINATION ATTACHMENT9.5 VT-3 EXAMNATION REPORT (CONTAINMENT MOISTURE BARRIERS)

Work Document: Component: Report No.:

System: Drawing: Page of Line #: cf Direct fl Remote Equipment:

a Light Meter (17NIA)

Wear nECltEll Damage nlotnl Erosion ninini Tear UKIttII Leak-tigMintegrity CIlotEl Other TllaltI um o n u n o Cloo C l a n nKl a u n o u n o alof Remarks:

Examiner Level Date I Examiner Level Date I

I I NUCLEAR 1 I Q U A ~ ~ ~ R E ~ = D ENKNDE-10.03 REV. 1

-Entt.r;py 1 MANAGEMENT I INFORMAllONAL USE 1

i PAGE 250F27 i MANUAL i! i 1 I . I _

VT-3 EXAMtNATlON

%ACWMEk 9.6 m-3EXAWHNATION REPORT (CONTAINMENT PRESSURE RETAINING BOLTING)

L Examiner Level Date 1 Examiner Level Date I

Review Level Date I

1 ANI1 Date

NUCLEAR 1 Q~ALw~WATED 1 ENN-NDE-10.03 1- REV. 1

-- Enterrry I MANAGEMENT i

1 blBORMAllONALUSE i

1 PAGE 26UF27 j MANUAL I i I vT% EXAMINATION ATTACHMENT9.7 SUPPORT EXAMINATYON BOUNDARf ES (TYPICAL)

Page 1 of 1

i i NUCLEAR I

1 I

QUALITYREIATED 1 I ENKNDE-10.03

- /

-J------

REV. 1 I I I VT-3 EXAMINATION ATTACHMENT 9.8 -

INTEGRAL ATTACHMENT COMPONENT SUPPORT DETAIL -

1 of I Component, (b)

Comnonent IWD Boundary (Weld Len&)

support Component (e)

Integral Attachment - Component Supports