ML070790208
| ML070790208 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/02/2006 |
| From: | Limpias O Entergy Nuclear Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| ENN-NDE-10.03, Rev 1 | |
| Download: ML070790208 (27) | |
Text
1 1 i I
NUCLEAR QUAltN~TED ENN-NDE-10.03 REV. 1 t@??Y I MANAGEMENT MANUAL i
1 1
i INFOAMATIONAL~SE 1 PAGE 1 OF27
Title:
VT-3 EXAMINATION (Print Name /?Title) t Approved:
g/& -
(Procgduh bwner Signahre) 17 I (date) t I i I Procedure Contains NMM REFLIB Forms: YES NO 0 Basis Statement ENN-NDE-10.03 RevWon 1 Includes:
0 Procedure reformatted per EN-AD-101 requirements.
0 PNPS requirements changed to reflect IS1 interval change.
Added reference io ASME Boiler & Pressure Vessel Code,Section XI, 2001 Edition, including 2003 Addenda 0 Paragraph 1.Of41Clarified paragraph to distinguish SWR VIP program 0 Added reference to ENN Site Relief Requests 0 Added reference to ENN-NDE-1.OO 0 NDE personnel section added for consistency with ENN procedures.
0 Added requirement for documenting procedure qualifications 0 Paragraph 5.2 121 (c) clarified.
PNPS VT-3 requirement for integral attachments removed.
Revised examination report review requirements 0 Revised obligations and commitments per EN-AD-101 requirements.
W Added sample NDE report forms with attributes for examinations.
S 6 and NMM Procedures Canceled or Superseded Bv This Revision ENN-NDE-10.03 Revision 0 Process Appficabilitv Exclusion (ENN-LI-100) I Proarammatic Exclusion (ENS-Lt-101) 411 Sites: Ixf Specific Sites: A N 0 GGNS IPECO JAF PNPSQ RBS c]W 0 W3 17
1 NUCLEAR I
QUALITY RELATED ENN-NDE-10.03 1 REV. 1 1 I I INFORMAllONALUSE
- i I VT-3 WAMINATION TABLE OF CONTENTS Section Paae 1 .o PURPOSE ............................................................................................. 3
2.0 REFERENCES
......................................................................................3 3.0 DEFINITJONS ........................................................................................ 4 4.0 RESPONSIBILITIES .............................................................................. 4 5.o DETAfLS ................................................................................................4 6.0 INTERFACES ...................................................................................... 16 7.0 RECORDS ........................................................................................... 16 8.0 REQUIREMENTSAND COMMITMENT CROSS-REFERENCE ........I7 9.0 AlTACHMENTS.................................................................................. 18 ATTACHMENT 9.1 VT-3 EXAMINATION REPORT(PUMP CASINGS AND VALVEBODIES) .....................................................20 ATTACHMENT9.2 VT-3 EXAMINATION REPORT(COMPONENT SUPPORTS) ...........................................................21 ATTACHMENT 9.3 m-3EXAMiNATfONREPORT (SNUBBERS) ..............22 AllACHMENT 9.4 VT-3 EXAMINATION REPORT(CONTAINMENT SURFACES)...........................................................23 ATTACHMENT 9.5 VT-3 EXAMINATIONREPORT(CONTAINMENT MOISTURE BARRIERS) ........................................... 24 A ~ A C H M E N 9.6 T VT-3 EXAMINATION REPORT(CONTAINMENT PRESSURE RETAINFNG BOLTING) ............................ 25 ATTACHMENT 9.7 SUPPORT EXAMINATION BOUNDARIES (TYPICAL) ......26 ATTACHMENT 9.8 INTEGRAL ATTACHMENT - COMPONENT SUPPORT DETAfL .................................................................. 27
I 1
1 NUCLEAR i
QuwnRELATED ENN-NDE-10.03 1 REV.l tw I MANAGEMENT MANUAL I
INFORMARONAL USE I
!I PAGE 30F27 VT-3 EXAMINATION 1.0 PURPOSE
[l] This procedure establishes the methods and requirements to be used for ASME Section Xt VT-3 examination of components.
121 The VT-3 examination shalt be conducted to determine the generat mechanical and structurat 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 bofted or welded connections.
[3] The VT-3 examination shall include examination for conditions that could affect operability or functional adequacy of snubbers, constant ioad and spring type supports.
143 This procedure is not applicable to VT-3 examinations performed per the In-vessel 2.0 Visual Inspection (IWI)8WR VIP program.
REFERENCES I
Nuctear Regulatory Commission, 10 CFR Part 50, Industry Codes and Standards.
ASME Boiler & Pressure Vessel Code,Section XI, 2001 Edition, including 2003 Addenda.
ASME Boiler 4% Pressure Vessef 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 Boiler and Pressure Vessel Code, Code Cases ENN Site Specific Relief Requests, Reference Section 8.0 Regulatory Guide 1,147Inservice Inspection Code Case Acceptability ASMWANSI O M 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.
21 ENN-NDE-10.01. VT-1 Examination
I I
i I I
i NUCLEAR j QUALlTf8ELATED , ENN-NDE-10.03 [ REV. 1
-- Enteagv 1 MANAGEMENT iNFOORMAnONAtUSE Ij PAGE 4 0 F 2 7
_L I 1131 ENN-NDE-10.02, VT-2 Examination 3.0 DEFINITIONS
[I] Reference ASME Boiler and Pressure Vessel Code, Sections V and XI, for the glossary of terms used in Nondestructive Examination (NDE).
4.0 RESPONSIBlLfflES SUPERVISOR The Supervisor, charged with the responsibility for NDE at each site, is respansible fur implementation of this procedure.
ENTERGY NDE LEVEL ill The Entergy Levet if l is responsibfe for development, interpretation and qualification of this procedure.
The Entergy Level flf 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 I I or I tI personnei shall be responsible for the examination and interpretation of results.
Level 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 I11 examiners.
5.0 DETAILS 5.1 PRECAUTIONS AND LJMITATIONS
[I] None
-c-1 "Enfyg I II NUCLEAR MANAGEMENT 1,
i OUAUTYRELATEO IHFORMAXONAL USE I
I E
N
- N
- D
-:E
- 5I OF ,pEV. 1 I
- MANUAL
__ i _I_
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 cornbination of access and lighting sufficient to resolve a 1/32" black line on an 18% 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 fower 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-2270-1 may be extended and the minimum illumination requirements specified in Table IWA-2210-I 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.
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) Measurementsof 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 fowercase characters without an ascender or descender meets the specified requirements.
Enfplgy 1
1 NUCLEAR MANAGEMENT MANUAL 1 QUALITY RELATED 1NFORMATIONAL US 1 ENN-NDE-10.03 1 REV. 1 PAGE 6 0 F 2 7 1
--- I VT-3 EXAMINATION i
1 (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.
EQUIPMENT 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 ACCESS AND ILLUMINATION (LIGHTING)
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.
NUCLEAR QUAL1N RELATED 1 ENN-NDE-10.m REV. 1 I -
j _.L-I i
VT-3 EXAMINATION (b) JAF, lPEC - 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 four feet shall apply to the distance from the eye to the surface being examined at an angle nut 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 examhations 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 !WA-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 IWA-2211-1.
(3) The remote visual examination system shalt be capabfe of distinguishing the cotors applicable to the component examinations being conducted.
[2] Illurnination (Lighting)
(a) Illumination 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.
=Enfq-y 1 MANAGEMENT lNFORMATlONALUSE 1 PAGE 80F27
- MANUAL j i / - - - I - - --
ASME Section XI 1992 Edition, including 1992 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 illumination of a light source when using a light meter shall be SO& candles for inspection.
- b. The illumination fevets 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 portab!e light source or similar installed lighting equipment is demonstrated to provide the specified illumination at the maximum distance.
PNPS - ASME Section XI 2001 Edition through 2003 Addenda Resolution of the specified characters (0.044 in.) can be used in lieu of iffurnination measurement to verify itlumination adequacy.
Minimum illumination of a light source when using a light meter shall be 50 ft-candles for inspection.
if illumination measurement is petformed, 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 tighting equipment is demonstrated to provide the illumination specified at the maximum examination distance.
When illumination measurement is performed during the examination and a battery-powered tight is used, the adequacy of the illumination levet shall be checked before and after each examination or series of examinations, not to exceed 4 hr between checks.
It tw&
1 NUCLEAR MANAGEMENT MANUAL 1 Q~UYRELA~
~NFOAMAVONALUSE I ENN-NDE-10.03 1 i
PAGE 9OF27 REV. 1 I
_- i E A VT-3 EXAMINATION 1 SURFACE PREPARATION Visual examinations that require clean surfaces or decontamination for vatid interpretation of resutts 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 general oxidation, unless flaking or thickness reduction has occurred, is acceptable for VT-3 examination of component supports.
EXAMINATION 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 component 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 retajning components, and integral and non-integral supports. The examination boundary does not include the attachment of the intervening element to the building structure.
I QuamRELAED i
i ENN-NDE-10.03 I REV. 1 iNFORMnnONAL USE 1 PAGE 1OOF27
\IT-3 EXAMINATION (f) All integral and non-integral connections within the IWF support examination boundary are included.
[3] Pump Casings and Valve Bodies (8-L-2 & 8-M-2)
(a) Examine afl interior surfaces of the valve or pump pressure-retaining boundaries.
(b) Examine all areas within the specified boundary for:
(I ) Erosion / Corrosion (2) Wear (3) Crack-like surface flaws
[4] Component Supports (F-A)
(a) Examine ali integral and non-integral connections, intermediate members within the IWF examination boundary inctuding welded and bolted connections to the pressure retaining components, building structures, and at intermediate joints. Examination of component supports shall include:
Deformation or structural degradation Integrity of mechanical (e.g., bolted) or welded connections Corrosion Wear Missing, detached or loose support items Degraded close tolerance machined or sliding surfaces Improper hot or cold positions of spring supports and constant load supports Misalignment Clearances of guides and stops
I I I
i NUCLEAR QIJALKYREI-ATED I ENN-NDE-10.03 REV. 1
~~f~ i MANAGEMENT iNFORMAnONAL USE I
[ PAGE 11 OF27 1 MANUAL i Snubbers (ASMEYANSt OM Code, Part 4,1988 edition and 1995 edition through 2000 Addenda)
(a) Examination of integral 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 operability (2) Load ratings, location, 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 rnernbers or disconnected components (8) Restricted thermal movement (evidence of binding, misalignment or deformation)
General Visuat Examination of Containment Surfaces (a) General Visual examinations shall be performed in accordance with the Sites Containment Insetvice Inspection Program.
Examination of Containment Surfaces (E-A)
{a) The examination may be made from either the inside or outside surface.
(b) The examination shall include structures that are parts of reinforcing structure, such as stiffening rings, manhole frames and reinforcementaround openings.
1 --.A-I -- I VT-3 EXAMlNATtON 1 (c) Tbe inspected area, when painted or coated, shafl be examined in accordance with the Sites Containment Inservice Inspection Program for evidence of:
(1) Flaking (2) Biistering (3) Peeling (4) Discoloration (5) Other signs of distress (d) The inspected area, when not coated, shall be examined in accordance with heSites Containment Inservice Inspection Program for evidence of:
(1) Cracking (2) Discoloration (3) Wear (4) Pitting (5) Excessive corrosion (6) Arc strikes (7) Gouges (8) Su dace discontinuities (9) Dents (10) Other signs of surface irregularities
1 1 1
-4EntergY 11 NUCLEAR MANAGEMENT MANUAL i
QUALITYRELATED i lWORMAllONAL USE ENN-NDE-10.03 PAGE 13OF27 REV.1 1
(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 f9] VY, PNPS - Examination of Containment Pressure Retaining Botting (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 ffange 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 following attributes:
(1) Missing / Loose bolting (2) Containment leak tightness (3) Structural integrity
I I VT-3 EXAMINATION I
I 5.7 ACCEPTANCE CRITERIA
[13 Components whose visuai examination confirms the absence of the relevant conditions described in the examination section of this procedure shall be considered acceptable for continued service.
[21 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] Pump Casings and Valve Bodies (B-L-2 8t B-M-2)
(a) The following relevant conditions must be recorded as unacceptable:
(1) Erosion or corrosion that reduces the pressure retaining wall thickness by more than ten percent (10%).
(2) Wear of mating surfaces that may fead to a loss of function or leakage I (3) Crack-like surface indications developed in service or grown in size beyond that recorded during preservice visuai examination.
141 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 loosened 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 supports (5) Misafignment of supports (6) Improper displacement settings of guides and stops
I MANAGEMENT lNFORMATIONAL USE PAGE 15 OF 27 I -
VT-3 EXAMINATION (a) Snubbers Any visible signs of damage or impaired operability 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 revel is equal to or greater than the minimum amount that is sufficient for actuation at it's operating extension.
- b. Fluid tevel for tisaga snubbers is indicated by the color of the site glass.
Structuraf 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 shall be instailed so that they can carry the load; Le., loose fasteners, missing hardware, deformed members or disconnected components.
Snubbers shall be instatfed in such a condition that they do not restrict thermal movement of the pipe or component.
- a. Evidence of binding, misalignment or deformation.
1 I I I
I i j --_I_--- -
VT-3 EXAMTNATION
[6] General Visual Examination of Containment Surfaces (a) The Containment IS1 program shall specify the site requirements for acceptance of General visual examinations.
171 VT-3 Examination of Containment Surfaces (E-A)
(a) The Containment IS1 program shall specify the site requirements for acceptance of VT-3 visual examinations.
(b) Acceptance of 1WE examinations shall be by engineering evaluation or based on site-specific acceptance criteria for the visuat examination of containment surfaces.
[8] Examination of Containment Moisture Barriers (E-A, 1998 Edition with Addenda through 2000. / E-D, 1992 Edition including 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] -
VY, 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 INTfRFACES E13 None 7.0 RECORDS
[1] Examination results shall be evaluated in terms of the applicable acceptance criteria and documented on Attachment 9.1 through 9.6 or similar forms.
[2] Examination reports shall be reviewed per ENN-NDE-1.OO requirements.
I I MANAGEMENT I
ENN-NDE-10.03 1 REV. 1 PAGE 170F27
[3] Examination reports shall be processed per site requirements and as a minimum, shali 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 Step Document Commitment Number
[I]
[2]
Nuclear RegulatoryCommission, 10 CFR Part 50, Industry Codes and Standards.
Entergy Quality Assurance Program Manual, Section 8.1 1, "Special None None I
Process Control"
[3j ASME Boiler & Pressure Vessel Code,Section XI, 2001 Edition, None including 2003 Addenda.
[4J ASME Boiler & Pressure Vessel Code,Section V and XI, 7998 Edition None through2000 Addenda.
[s] ASME Boiler & Pressure Vessel Code,Section V and XI, 1992 Edition, including 1992 Addenda.
None r61 L-1 1
ASME Boiler & Pressure Vessel Code,Section XI, 1989 Edition no Addenda. I None 1
I NUCLEAR 1 QUAI-~TYRUED 1 I
ENN-NDE-10.03 REV. 1 1 lFlMRMATlONALUSE 1 PAGE 180F27 Step Document Document Section 1 Commitment Number
[I] ASME Boifer & Pressure Vessef PNPS - Section 5.2,5.4, None Code.Section XI. 2001 Edition.
1 including 2003 Addenda. t I r21 1 ASME Boiler & Pressure Vessel I PNPS, W - Section 5.2, 5.4, 1 None Edition through 2000 Addenda.
[3] ASME Boiler & Pressure Vessel -
JAF, IPEC Section 5.2,5.4 None Code,Section V and Xi, 1992 Edition, including 1992 Addenda.
[4] ASME Boiler & Pressure Vessel -
JAF, PEC Section 5.2,5.4 None Code,Section XI, 1989 Edition no I Addenda. I I 8.3 SITE SPECIFIC COMMITMENTS Step f Site Document Document Section Commitment Number
[l] 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 (ti), RR-3-5 (H)
Interval Relief Request and RR-3-24 (C)
[43 PNPS Fourth In-service Inspection Section 5.2, 5.4 PIL-05-R-002 Interval Relief Request 9.0 ATTACHMENTS i 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 Sampfe 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)
Entwm 1 NUCLEAR lANAGEMENT I i i
REV. I PAGE f9OF27 9.7 Support examination boundaries (Typical) 9.8 Integral attachment - component support detail (Typical)
Enfw, 1
1 EjUCLEAR I
I j
1 QoALinREtATto I
1 ENN-NDE-10.03 I
j REV.1 i
-.-- MANAGEMENT MANUAL I lNFORMATlONALUSE I
PAGE 2OOF27
-_II____F- 1 -
VT-3 EXAMINATION ATTACHMENT 9.1 m-3EXAM~NATION REPORT (PUMP CASINGS AND VALVE BODIES) 1 wok Document: f Component: I Report No,:
Remarks:
~ -~ __
Examiner Levet Date II Examiner Level Date I
t Rwiew Levei Date f ANI1 Date
II \
1
'w 1I NUCLEAR MANAGEMENT MANUAL 1' i -
QUAL~TVRELATED lNFORMATfONAL&E VT-3 EXAMINATtON I
1 i
ENN-NDE-10.03 PAGE 21 OF27 REV. 1 ATTACHMENT9.2 VT-3 EXAWNAWN REPORT (COMPONENT SUPPORTS)
Work Document: Report No.:
Acceptance Criteria: ASME Section Xt 1998 Edition, 2000 Addenda Remarks:
I Examiner Level Date 1 Examiner Level Date I
VT-3 EXAMINAftON
__~_____-
ATTACHMENT 9.3 VT-3 EXAMINATKIN REPORT (SNUBBERS)
Work Document: J Component: 1 Report No.:
System: Drawing: Page of Line #: Direct c]Remote Equipment:
0 tight Meter ((23 N/A)
Support Attributes Acc I Rej IVA 1 Snubber Attributes Acc 1 Re DeformedI degraded comp. CJ 1 c] 1 Damageor impairedoperability 0 I C MechanicaVweldedconnection I 0 I 0 I /J Load, location, configuration a10 Corrosion I 0 Swing clearance Io a Wear r] 1 0 Structural connections lo 0 Missing, loose support items ' fJ IJ I 0 1 Physical damage / degradation 1 0 Degraded close tolerance surf. I 0 I 0 c] 1 Loose/missing/deformed comp 0 0 I
Improper support settings- a- - Restmedthermal movement 0 0 Misalignment 0 I 0 Other ala Clearances of guides/stops D E l U nlo Other la D a a o Lo 0 [a a ru olu In 0 a UlU fa a 0 oln Cl'U Serial Number: 0 0 0 Fluid level - D E I I
RequiredSetting = 1 I a . 0 Actual Setting = - 0 i O Acceptance Criteria: ASME Section XI 1998 Edition, 2000 Addenda Remarks:
~ ~
Examiner Level Date I Examiner Level D%
I Review Level Date I ANI1 Dat
ij NUCLEAR I QUALRYRUAtED 1 ENN-NDE-10.03 1 REV. 1 En'q I MANAGEMENT MANUAL I--
INFORMATIONAL USE I _
I I
PAGE 23OF27 VT-3 EXAMINATION ATTACHMENT9.4 VT-3 EXAMINATION REPORT (CONTAINMENT SURFACES)
Work Document: Component: Report No.:
Examiner Level Date I1 1
Examiner Level Date I
lW@
NUCLEAR MANAGEMENT MANUAL /
1 QUKlNREu\rrr, fNFORMATtONAt &E f
i ENN-NDE-10.03 i PAGE 24OF27 1
REV. I System: Drawng: Pwe of Line #: IJ Direct Remote Equipment:
L Light Meter (a N/A)
Moisture Barriers Attribute 1 Acc Rej WA 1 Comments
. Wear I U . 0 01 Damage a : a nf Erosion a lEllo 1 ofcl I
fear Surface cracks 0 : o 01 .
I Leak-tight integrity a OI Other 'El a ala a r l n a n 0 0 OlO 0 a fl.
ofn u n o a 0 01 u 0 01 I Level Date f
Examiner Level Date
I NUCLEAR I I ENN-NDE-10.03 1 REV.l I w I Q~JALITVRELATED MANAGEMENT MANUAL tNFORMATIONAL USE 1i PAGE 25UF27 I -
1 I
VT-3 EXAMINATION Examiner Date 1
I Examiner Date
En&j-gy I 1 NUCLEAR MANAGEMENT 1 Q~IwwRELATED k4FORMATlONALUSE 1 ENN-NDE-10.03 1 PAGE 26OF27 REV. 1 g MANUAL I !
j - I VT-3 EXAMINATION AUACHMENT 9.7 - SUPPORT EXAMfNATlON BQUNDARiES (TYPICAL)
Page 1 of 1
!dl
i i VT-3 EXAMINATION AITACHMENT 9.8 INTEGRALATTACNMEM - COMPONENT SUPPORT DETXL 1 of 1 Component, Component - IC L3e- support (a)
Component Component ent Integral Attachment - Component Supports