ML20236T264
| ML20236T264 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/23/1987 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20236T199 | List: |
| References | |
| FNP-1-M-043, FNP-1-M-43, NUDOCS 8712010102 | |
| Download: ML20236T264 (270) | |
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.j, e id[J / ff FNP-1-M-043 JOSEPH M. FARLEY NUCLEAR ~ PLANT UNIT NO. 1 O SECOND 10-YEAR INSERVICE INSPECTION PROGRAM
;ASME CODE CLASS 1, 2, AND 3' COMPONENTS
,y TABLE OF CONTENTS If Page g
y 1. 0 Introduction 1.1 Scope 1-1 1.2 Effective Date 1 ' 1.3 Component Upgrading 1-1 1.4 . Subsequent ISI Plan' Revisions 1-2 1.5 Responsibility 1-2
/ 1.6 Records' 'l-2
- f. r 1.7 Methods'of Examinations 1-2 i/I" I y <
1.7.1 1.7.2 Ultrasonic Radiography
.1-2 1
- r 1.7.3 Eddy Current 1 ,
1.7.4 Liquid Penetrant 1-3 1.'7.5 Magnetic Particle 1-3
'f 1.7.6 . Visual- 1-3 1.8 Evaluation of Examination Results 1-4 1.9 Repair Procedures 1-4 O (
1.10 f 1.11 1.12 Limitations of Examinations Augmented; Examinations Code Cases 1-4 1-5 1-5 e2.0 Inservice Inspection of Class 1 Components 2-1 12.1 Exempt Components 2-1 2.2 System Pressure Tests 2-1 7 { 3.0 Inservice Inspection of Class 2 Components 3-1 }\ , 3.1 Exempt Components 3-1
,p 3.2 Hydrostatic Testing 3-2 J' , 4. 0 Inservice Inspection of Class 3 Components 4-1 i q ,, 4.1 Exempt Components 4-1 d 5.0 Inservice Inspections of Class 1, 2, and 3 Components Supports 5-1 t 5.1 Supports Selected for Examination 5-1 l 4, 6.j 0 Requests for Relief from ASME Section XI 6-1 Requirements L 7.0 References 7-1 7.1 Documents 7-l' 7.2 Letters 7-2' O'
0380I Rev.. 0: L t ! ;1". + n i - . _ - _ _ _ _ - _ _ _ - - _ _ _ _ _ - _ - _ - - - _ _ -
l FNP-1-M-043 1.1 SCOPE This document details the scope of the second 10-year inservice j inspection (ISI) program for Farley= Nuclear Power Plant Unit No. j 1 out.ed by Alabane. Power Company. The ISI requirements are 1 specified by the code of Federal Regulations, 10 CFR 50.55 a(g) ) and includes examinations for ASME Class 1, 2, and 3 components. Paragraph >1.11 of this sect 16n contains augmented inspection requirements committed to by the owner. All pertinent Nuclear Regulatory Commission (NRC) documents used in developing this program are listed as references in section 7.0. The following information is provided as part of this program.
- ISI. Boundary Diagrams.
- Ipplicable ASME Section XI examination requirements.
- Relief Requests.
- Angmented examination scope. _
The scope of examirintions, procedures, and acceptance criteria , meets the requirements outlined in Section XI of the American l Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1983 Edition, with Addenda through Summer 1983. The extent of examinations for ASME Code Class 1 and 2 piping
/ welds. is determined in accordance with the requirements of the
(_ 1974 Edition of ASME Section XI with Addenda t'hrough Summer 1975 as allowed by 10 CFR 50.55a paragraphs (b)(2)(ii) and (b)(iv)(B). Thus, the er.emption criteria utilized for Class 2 piping welds is in accordance with the IWC-1220 of the Summer ! 1975 Addenda to the ASME Code. l 1.2 EFFECTIVE DATE l The second 10-year program goes into effect at the start of the l second 120-month interval of plant commercial operation which fe l December 1, 1987. 1.3 COMPONENT UPGRADI_NG t All plant components have been reviewed to determine the appropriate classification for inservice inspection. ANSI, N-18.2 " Nuclear Safety Criteria for t.he Design of Stationary Pressurized Water Reactor Plant *.7,," is used as an acceptable alternate to Safety Guide 26 in determining component quality group classifications. It must be noted that the classification of components as ASME Class 1, 2, or 3 equivalent fer inservice inspection does not 7g (j imply that the components were designed in accordance with ASME 0380I 1-1 Rev. O
FNP-1-M-043 r~3 requirements. The component design codes remain as stated in j () the Final Safety Analysis Report (FSAR). ! 1.4 SUBSEQUENT ISI PROGRAM REVISIONS ; l In accordance with the existing regulations of 10 CFR 50.55a, ! the inservice examination program for Class 1, 2, and 3 j components will be reviewed near the end of each 120-month interval. At this time the program will be modified, as required, to bring it into compliance with the latest : NRC-approved version of Section XI. l l l 1.5 RESPONSIBILITY l Alabama Power Company bears the overall responsibility for the l performance of the inservice examinations. Certain i j nondestructive examinations may be performed by a qualified I examination agency. The results of such examinations would be . reported to Alabama Power Company for final evaluation and disposition. l 1.6 RECORDS (] Records and documentation of all information and inspection results, which provide the basis for evaluation and which l (_/ ' facilitate comparison with results from previous and subcequent ir.spections, will be maintained and will be available for the active life of the plant in accordance with Section XI, IWA-6000. 1.7 METHODS OF EXAMINATION l The method of examination planned for each area is delineated in subsequent sections. Personnel performing nondestructive examinations will be trained in accordance with the American l Society for Nondestructive Testing (ASNT) " Recommended Practice SNT-TC-1A, Supplements and Appendices," as applicable for the technique and method used. Personnel performing visual examinations outside the scope of nondestructive examinations shall be trained to the requirements of ANSI N45.2.6
" Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants".
1.7.1 ULTRASONIC Ultrasonic examinations will be conducted in accordance with the provision of Appendix III of Section XI and Articles 4 and 5 of [ Section V as required by Paragraph IWA-2232. V 0380I 1-2 Rev. O 1
1 FNP-1-M-043 i The 1974 Edition of Section XI of the ASME Boiler and Pressure (m) Vessel Code, with Summer 1975 Addenda, Appendix I, was used for the design of the existing ultrasonic calibration blocks for ferritic vessels 2-1/2 inches and greater in wall thickness. Existing calibration blocks for piping and thin-walled vessels under 2-1/2 inches in wall thickness were designed to the 1974 Edition of Section V, with Summer 1975 Addenda, Article 5. Because of the impracticality of some of the requirements of Article 5 of Section V, the 1977 Edition of Section XI, Appendix III was also used for guidance. This provided alternative machined notches for reference reflectors in lieu of side-drilled holes. 1.7.2 RADIOGRAPHY Radiographic techniques will be used to supplement ultrasonic examination as required. r 1.7.3 EDDY CURRENT Eddy current examinations will be performed on the steam generator tubing in accordance with the provisions of Appendix IV of Section XI and the plant Technical Specifications. 1.7.4 LIQUID PENETRANT Dye penetrant examinations will be used whenever a surface examination is required on nonferrous components. 1.7.5 MAGNETIC PARTICLE Magnetic particle tests will usually be used when surface ! examination of ferrous components is required. 1.7.6 VISUAL The following visual examinations will be employed as appropriate: VT-1: To detect detrimental condition (s) of parts, components, or on examined surfaces.
- VT-2: To locate evidence of leakage during a system or functional test.
- VT-3: To determine the general mechanical and structural condition of components and their supports, and also to determine conditions that
\_ could affect operability or functional adequacy of snubbers, and constant lead and spring type supports.
0380I 1-3 Rev. 0
i FNP-1-M-043 1.8 EVALUATION OF EXAMINATION RESULTS Examination results are evaluated in accordance with IWA-3000, IWB-3000, and IWF-3000 of the ASME Code, Section XI. Articles IWC-3000 and IWD-3OOO, titled " Acceptance Standards.for Flaw , Indications," are in the course of preparation and, as yet, are j not available for use. Therefore, the results of IWB-3000 may be utilized for ISI Class 2 and 3 components. 1.9 REPAIR AND REPLACEMENT PROGRAM Alabama Power Company's repair and replacement program is i defined in various plant administrative and departmental procedures. The detailed-program for welding and related activities is defined in.the Special Processes Manual, FNP-0-M-23.
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1.10 LIMITATIONS OF EXAMINATIONS Limitations may occur for the examination of piping system circumferential butt welds (Categories B-J and C-F) when the ) welds occur at geometric discontinuities such as pipe-to-vessel welds, pipe-to-fitting welds, or fitting-to-fitting welds. The volume of weld and base material required to be examined for piping welds has changed significantly from the first 10-year I inspection interval. Limitations evident during the first interval may no longer be relevent. ; For pipe-to-fitting or pipe-to-vessel nozzle welds, examinations can be performed to the extent required'by III-3230 of Section XI from the pipe surface. Examination from the fitting side would be dependent upon the geometric configuration. Where elbows or tees are concerned, examinations can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases, the required volume of the weld and base material will be examined. Where limitations are encountered and ultrasonic examinations cannot be performed on the required volume of the weld and base material, sur
- or visual examinations may be performed to supplement .imited volumetric examination.
i In instances where the locations of pipe supports or hangers ; restrict the access available for the examination of pipe welds , as required by IWB-2500, examinations will be performed to the ; extent practical unless removal of the support is permissible without unduly stressing the system. i l 0380I l-4 Rev. O l 1 ; 1 <
FNP-1-M-043 The ISI programs outlined in the attached tabulations have been developed as a result of a design review. Should certain ASME O Section XI Code requirements be. discovered to be impractical'due to unforeseen reasons during the process of-performing inspections or tests, relief will be requested from the specific Section XI Code requirement at that time. Radiation levels in certain areas or of certain components may q be found to prohibit the access for operators or examiners to ; perform the examinations or tests described in this program. If. 'l ' radiation levels cannot be reduced and access is still restricted by considerations of compliance with the requirements i of Regulatory Guides 8.8 and 8.10, relief will be requested from the specific Section XI Code requirements and alternative ! I examination requirements will be proposed. 1.11 AUGMENTED INSPECTIONS l The NRC has required certain augmented inspections as added , 4 1 assurance of structural reliability. The areas of interest and the examinations to be performed are as follows: . A. Reactor vessel examinations will be performed.in accordance with Alabama Power Company's " Augmented j Reactor Vessel Examination Program" dated 10/6/83, J which was developed in response to Generic Letter 83-15
- and Regulatory Guide 1.150, Revision 1.
B. The reactor coolant pump fly wheel will be inspected in j accordance with plant Technical Specification 4.4.11.2 and Regulatory Guide 1.14. C. The steam generator tubing will be inspected in accordance with plant Technical Specification 4.4.6 and j Regulatory Guide 1.83, Rev. 1. D. The main steam lines will be inspected in accordance ; with plant Technical Specification 4.4.11.3 and Branch Technical positions APCSB-3-1 and MEB-3-1. 1.12 CODE CASES ! l Code cases listed in Regulatory Guide 1.147 will be used by > Alabama Power Company as necessary. All other code cases will be used on a case-by-case basis. O 0380I 1-5 Rev. O l
FNP-1-M-043 2.0 INSERVICE INSPECTION OF CLASS 1 COMPONENTS The following provides a tabulation of the Class 1 pressure-retaining components that are subject to the inspection requirements of Subsection IWB of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1983 Edition and Addenda through Summer 1983. This tabulation identifies the components to be inspected, the Section XI Category, the examination method and its acceptance standard, and the extent and frequency of the examination required by the Code. Relief from the inspection requirements of Subsection IWB is requested where these inspection requirements have been determined to be impractical. Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative. Table IWB-2500 items that are not applicable to , the Farley Plant have also been listed and identified in the . tables. - 2.1 EXEMPT COMPONENTS Essentially, ASME Code Class 1 component connections, piping, and associated valves (and their supports) that are 1-inch nominal pipe size and smaller have been exempted from the ( volumetric and surface examination requirements of Table IWB-2500, as allowed by paragraph IWB-?.220(b) of the ASME Code Section XI, 1983 Edition through Summer 1983 Addenda. However, all the ASME Code Class 1 exempt components will be subject to , l the pressure / hydrostatic testing requirements of Examinations 1 Category B-P of Table IWB-2500. l 2.2 SYSTEM PRESSURE TESTS ' All exempt and nonexempt Class 1 components will be examined under pressure as required by Table IWB-2500. In addition to j the system hydrostatic pressure test at or near the end of the l inspection interval, a system leakage test will be performed prior to startup following each reactor refueling outage in accordance with Article IWB-5000. Requirements for the visual examination of Class 1 systems and . components for evidence of leakage during the performance of a ! system pressure test following each refueling are identified by ! IWB-5200. Exception is taken to the implementation of these requirements on those portions of Class 1 systems which are contained between two check valves or two normally closed valves, where pressure applied to the reactor coolant system will be retained at the first valve in the line. The portions (~wg of systems affected by this limitation are addressed separately V in relief requests. 0388I 2-1 REV. O f
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i FNP-1-M-043 i r- 3.0 INSERVICE INSPECTION.0F CLASS 2 COMPONENTS The following provides a tabulation of the' Class 2 pressure-retaining components that are subject to the inspection requirements of Subsection IWC of Section XI of the I.merican Society of. Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1983 Edition, with Addenda through Summer 1983. This tabulation' identifies the components to be inspected, the ; Section'XI examination category, the examination method and its i acceptance standard, and the extent and frequency of the I examinations required by the Code. Relief from the inspection I l requirements of Subsection IWC is requested where these j inspection. requirements have been determined to be impractical. ; Where relief is requested, specific information is provided I which identifies the applicable code requirement, the justification for the relief request, and the. inspection method to be used as an alternative. Table IWC-2500-1 items that are- - 1 not applicable to the Farley Nuclear Plant have also been listed and identified in the tables. . 1 3.1 EXEMPT COMPONENTS In accordance with 10 CFR 50.55a paragraph (b)(IV)(B), ASME Code Class 2 components are subject to the following exemptions as O described in paragraph IWC-1220 of the 1974 Edition with Addenda thrcugh Summer 1975 of Section XI. 3.1.1 On the basis of design pressure and temperature, the following Class 2 components are exempt from the volumetric and surface examination requirements of IWC-2500-1 as allowed by paragraph IWC-1220(a): A. Component Cooling System - Line numbers 6" HBB-1, 6" HBB-2, 6" HBB-3 and 6" HBB-4. B. Service Water System - Line numbers 12" HBB-5, 6" HBB-6, 10" HBB-6, 6" HBB-8, 6" HBB-9 and 6" HBB-10. i C. Containment Cooling & Purge System - Line numbers 8" HBB-16, 8" HBB-17, 14" HBB-16, 14" HBB-17, 18" HBB-16, 18"'HBB-17, 48" HBB-16 and 48" HBB-17. D. Safety Injection System - Line numbers 8" HCB-42, 8" < HCB-43, 12" HCB-152, 14" HCB-43, 16" HCB-42 and 16" HCB-43. 3.1.2 On the basis of system function, the following Class 2' lines are exempt from the volumetric and surface examination i F O requirements of Table IWC-2500-1 as allowed by paragraph IWC-1220(b): l 0402I 3-1 REV. O q \ .
1 r. I FNP-1-M-043
'l l
A. Containment' Cooling and Purge System.- Line numbers l
\(~N ,) 8" HBB-11A and 8" HBB-11B
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i B. . Post Accident Containment Combustible Gas Control - j
- Line number 6" HCB-81. 1 I
l C. Safety Injection System - Line numbers 8" HCB-48,. 'l 8" HCB-55, 10" HCB-51, 10" HCB-52, 10" HCB-53, 10" 1 HCB-54, 12" HCB-51, 12" HCB-52, 12" HCB-53 and 12" i HCB-54, 3.1.3 On the basis of water chemistry control, the following j Class 2 lines are exempt from the volumetric and surface 1 examination requirements of Table IWC-2500-1 as allowed by. l Paragraph IWC-1220(c): j A. Safety Injection System - The 6" line inlet and outlet' ' of the boron injection tank. 'Also 12" ECB-8 and 12"
~
CCB-24. . l 3.1.4 Based on paragraph IWC-1220(d), all Class 2 component connections, piping and associated valves, and vessels that are 4 in. nominal pipe size and smaller are exempt from the volumetric and surface examination requirements of Table IWC-2500-1. This exemption is used wherever the size criteria is applicable. ( ' Class 2 components exempt per the above criterion shall be subjected to system hydrostatic and leakage test requirements of IWC-5000. 3.2 HYDROSTATIC TESTING All Class 2 exempt and non-exempt components will be examined to satisfy examination requirement of category C-H of. Table IWC-2500-1. Hydrostatic and leakage testing for Class 2 components will be in accordance with IWC-5000. Specific relief from the Code requirement is requested where limitations to performance of these examinations exists. l ('~) i V 0402I 3-2 REV. 0
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I FNP-1-M-043 4.0 INSERVICE INSPECTION OF CLASS 3 COMPONENTS (M G The following table provides a listing of the pressure-retaining components and their integral attachments, which are subject to the inspection requirements of Subsection IND of Section XI of j the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1983 Edition and Addenda through Summer 1983. Many of the components included in this program were not
]
designed or constructed to Section III of the ASME Code because it was not in effect at the time the component was ordered; however, these components will be inspected in accordance with the requirements of Subsection IWD to the extent practical. l This tabulation identifies the components to be inspected, the I Section XI examination category, the examination method and its acceptance standard, and the extent and frequency of the examination required by the Code. : Relief from the inspection and pressure test requirements of Subsection IWD is requested in cases where these requirements , have been determined to be impractical. Where relief is requested, specific information is provided that identifies the applicable code requirements, justification for the relief request, and the inspection method to be used as an alternative. g The table groups the pressure-retaining components and their
\~# integral attachments on a system basis. Only those portions of
) the system which contain pressure-retaining components and their integral attachments are subject to the inspection requirements of Subsection IWD. 4.1 EXEMPT COMPONENTS In accordance with paragraph IWD-1220 and IWD-5223 of the 1983 Edition of ASME Section XI, with Addenda through Summer 1983, ' the following exemption criteria will be considered in determining the exempt status of ASME Code Class 3 components: ) 4.1.1 Except for the Auxiliary Feedwater System, integral attachments of supports to components that are 4-inch nominal pipe size and smaller within the system boundaries of l examination categories D-A (systems in support of reactor shutdown function), D-B (systems in support of ECCS, reactor RHR, CHR and atmosphere cleanup), and D-C (systems in support of RHR from spent fuel storage pool) of Table IWD-2500-1, shall be exempted from visual examination VT-3. Essentially all of the Class 3 systems will be subjected to the above exemption. 0403I 4-1 Rev. O
FNP-1-M-043 4.1.2 Integral attachments of support to components exceeding-4-inch nominal pipe size may be exempted from visual examination VT-3 of Table IWD-2500-1 provided: (a) The components are located in systems'whose functions are not required in support of RHR, CHR, and ECCS and, (b) The components operate at'a pressure of 275 psig or less and a temperature of 200 F or 'less. The following. systems or portion of systems satisfy the above exemption criteria: Reactor make-up water system - Line numbers - 6" HCC-237, 16" HCC-236, 6" HCC-236, 6" HCC-204 Service Water System -. _ r
~
Components - Control Room A/C Condensers'(2)-tube side. Component Cooling Water - Components - CVCS Letdown HX. - shell side Spent-fuel Fool HX. (2) - shell side Post Accident Combustible Gas Control System - Line numbers - 6" HCC-250
) Spent Fuel Pool Cooling System - 1 Line numbers - 8" HCC-110, 8" HCC-107, 10" HCC-108, 10" HCC-105, 8" HCC-106, 8" HCC-109 4.1.3 Open ended systems or open-ended' vent'and drain lines.
from components extending beyond the last shutoff valve may be ; exempt from hydrostatic test and the associated visual i examination VT-2 of Table IWD-2500-1. 1 l l 1 ! l O 0403I 4-2 Rev. 0
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FNP-1-M-043 i I 5.0 -INSERVICE INSPECTION'OF CLASS 1, 2, AND 3 e. () s l COMPONENT. SUPPORTS The following-tables provide a listing of Class 1, 2, and 3
. component supports which are subject to the inspection requirements of Subsection IWF of Section XI of the American Society of' Mechanical. Engineers (ASME) Boiler and Pressure Vessel Code, 1983 Edition, with Addenda.through Summer 1983.
This tabulation identifies the components to be inspected,. j examination method, acceptance standard, frequency, and extent. .i of examination. Relief from the inspection requirements of: Subsection IWF is requested in cases where these inspection: requirements have been determined to.be impractical. Where relief is' requested, specific information'is provided which identifies the applicable code requirement, justification for- ) l 'the relief request, and the inspection method to be:used as an ' ;' alternative. - 5.1 SUPPORTS SELECTED FOR EXAMINAT' ION 5.1.1 Supports of those components that are required-to be examined under Subsections IWB, IWC and IWD shall be. selected for examination. l O 5.1.2 For multiple components within a system of similar g M l design, function, and service, the support of only one of.the l multiple components are required to be examined. 1 i J i l I j 1 : I 0405I 5-1 Rev. O.
0 s
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i l I\ d FNP-1-M-043 6.0 RELIEF REQUESTS FNP-1 l i i The following relief requests are applicable to Farley Nuclear i Plant Unit 1 second 10-year ISI, and include all pertinent l examination areas and details where the requirements of ASME Code, Section XI, 1983 Edition with Addenda through Summer 1983, could not be satisfied completely. Relief Request No. Examination Area
]
l RR-1 Material requirements for calibration , blocks used for ultrasonic examination ) of heavy wall vessels. RR-2 Dimensional requirements for calibration blocks used for ultrasonic examination l of the reactor vessel. RR-3 Dimensional requirements for calibration blocks used for ultrasonic examination
/"' of the reactor vessel.
( RR-4 Ultrasonic examination of piping systems and thin wall vessels. RR-5 Dimensional differences between the calibration blocks used for examination of piping systems and thin wall vessels and the components to be examined. RR-6 Material requirements for calibration blocks used for ultrasonic examination of piping systems and thin wall vessels. RR-7 Dimensional requirements for l calibratjan notches placed on
]
calibration blocks used for ultrasonic 1 examination of piping systems and thin I wall vessels. RR-8 Volume'cric examination of the reactor vessc1 bottom head meridional weld. ! RR-9 Volumetric examination of nozzle-to- l vessel welds in the pressurizer. [)
'v RR-10 Volumetric examination of nozzle-to-safe end welds in steam generators.
0406I 6-1 REV. O
FNP-1-M-043 .q RELIEF REQUESTS I FNP-1 L x_/ j Relief Request No. Examination Area RR-11 Volumetric examination of nozzle inner radius section for steam generators. RR-12 Delete VT-4 visual examination method and redefine VT-3 visual examination requirements in accordance with paragraph IWA-2213 of ASME Section XI, 1986 Edition. RR-13 Volumetric examination of pressure retaining branch connection welds in Class 1 piping. RR-14 Volumetric examination of the reactor - vessel flange ligaments. , 1 l RR-15 Visual examination of the reactor l coolant pump internal pressure boundary surfaces. RR-16 Visual examination of the internal (N pressure boundary surfaces of Class 1 (_) valves. l RR-17 Reference system for all welds and areas subject to volumetric and surface examination. ! l RR-18 Volumetric examination of pressure , retaining welds in the regenerative f heat exchanger. j l RR-19 Volumetric examination of pressure i retaining welds in thin wall Class 2 pressure vessels. ; RR-20 Surface examination of integrally welded attachments to Class 2 charging pumps. RR-21 Hydrostatic testing of Class 2 , containment pressure sensing lines J (capillaries). RR-22 Hydrostatic testing of portions of Class 2 components at reduced pressure. [s ( RR-23 Hydrostatic testing of portions of Class 2 piping to the connecting Class 1 requirement. 0406I 6-2 REV. O L-________________ _ _ _ _ _ _ _ _ _ _ __ ___. - _ _ - _ _ _ - _ _ -
'~
pp I r,
'F
'FNP-1-M-043J
' RELIEF. REQUESTS' FNP-l' Relief Request No. Examination: Area ,
RR-24 Hydrostatic' testing of the relief-line discharge headers to the pressurizer. relief tank (line No. HCB-62). .j RR-26 HydrostaticLtest.for the Class'2 reactor vessel flange seal' leakoff line. ( line ' No . - CCB-3 6.)'. - RR-26 Hydrostatic testing of portions of Class 2' piping systems isolated from the test boundary by. closed check. .1
/
valves. 4 RR-27 Hydrostatic testLfor Class 2 waste gas drain filter line toJvolume control tankF(line No. HCB-92). RR-28 Volumetric examination of the nozzle- j inside radius section of the steam' () RR-29 outlet nozzle on steam. generators. Hydrostatic testing of boron. injection. , recirculation discharge piping (line: 1 No. CCB-62). 'l 1 RR-30 Hydrostatic 1 testing of: Class 2 portion of the steam generator (4-hour hold: time). 1 RR-31 Visualf(VT-2) examination'forileakage 1 of Class.3 river and service water i pumps. RR-32 Visual (VT-2) examination _for leakage. j in encased piping in spentifuel pool. ? cooling system. RR-33 Hydrostatic testing of portions of- l Class 3 piping and components which u operate continuously;during all. modes of plant operation; ! s RR-34' Hydrostatic testing'of. Class'3-spray! additive lines in containment, spray ; system. \- .l - 0406I 6-3 .REV. O.
9 I < Of ,.
- ENP-1-M-043 f' / I RELIEF REQUESTS m, s x
, ,, , [I p ')> 7,l$KP-1 '
v)~ y
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. q< , .
4 g~ i L F,elief Request No. Examination Area j RR-35 Hydrostatic testing of Class 3 buried y piping in river water and 'servics water .; system. b- l 1 RR-36 Visual (VT-2) examination of the tubes 1 in the Class 3 component cooling vater o 4' heat exchangers. >
.. i l'
RR-37 Visual (VT-2) examination of condenser , coils (tubes)'in Class 3,cdolers. l
,n <,
RR-38 Hydrostatic testing of Class 3 portions # of auxiliary steam piping.' ' v s : 2 ,. . . RR-39 Hydrostatic. testing of Class 3 auxiliary feedwater pump minimum flow [( r-piping.
}
l RR-40 Hydrostatic testing of 11 Class 2 N Ct' t i4 '{ branch cire lines from VCT to first valve. ' - !
/'I t ti %. J , ,
v RR-41 , Break away Erag test for hydraulic - snubbers. t j, t q RR-42 Additional sample testing' requirements l for snubbers. ; RR-43 Hydrostatic testing of Class 2 portions of the RCS head vent lines. i RR-44 Operational monitoring of the Class 3 l spent fuel pool cooling heat exchangers. ! o l>
]
,?
t . . . / , l s ('
'I h
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t
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A ( 0406I 6-4 ' REV. 0 2IL
-r,.
h FNP-1-M-043 t RELIEF REQUEST ( p i,. FNP-1 i
,e, t
?, RR-1 i Component or Relief Area: Relief from the material requirements for calibration blocks used to perform ultrasonic examination of the following:
APR-6: Steam generator channel h head-to-tubesheet welds. I i ALA-RV-1: Lower head-to-lower shell ) weld and all lower head El , welds'. e . . .
~
yf 1' 1 ALA-RV-3: Reactor. vessel shell-to-nozzle welds and . I' ' top head welds, r Requirement from ; whieb Relief is ! Requested: Section XI, 1983 Edition with Addenda through Summer 1983, paragraph IWA-2232 requires that () iss/ ultrasonic examination of vessel welds in ferritic materials greater than 2 in. in thickness be performed in accordance with "y a Article 4, Section V. Paragraph
/ y, T-434.1.l(3), Article 4, requires that the
^
material from which calibration blocks are fabricated be of the same material
- - specification, product form, and heat l ,
treatment as one of the materials being
? ,4 joined.
i , b Basis for Relief: During fabrication of the Farley Unit 1
'/' nuclear steam supply system vessels, the calibration blocks used to perform examinations by the vessel manufacturer were fabricated to the requirements of American e
Society of Mechanical Engineers (ASME)
^
Section III. When ASME Section XI was issued for inservice inspection, the new requirements for vessel calibration blocks l ( '
/ rendered the existing blocks unacceptable for use. The original blocks had to be replaced I '
,, but some vessel materials were no longer o y available. The vessel calibration blocks had
, to be prefabricated to the Section XI
..-q
. ,' requirements applicable at that time.
N,) 1 J
/
\' 0406I 6-5 REV, O 4 /1 n x
1]4
;dl;'
.... A, s, W .
i
9: RELIEF-REQUEST' ,
f" ') \ . . T ,. FNP -
- 4. _ ,s < .
p, <i,,i
'f RR-1?(Continued) s '
, Alternate Examination: Ths 14 ,
.fu, bove cal.fshpation blockri. are -in compliance requireme$ts lof paragraph
; widh'the.materi.A)SectionVof:.the:1974-ASME, T-520, Article 5,.
p ' Code, This parngraph.requ' ires thefblock.to s. be of similar metallurgical struiiture:.and:the'.
>. same or -:'an equivalent..P-number;. grouping , as >
.- the finished component.
r
/-
r
, ,w
, c ,
)
', Y .,
'i is a
/
, h, # .,
Rj s-
.,! .c i
'. {
' F
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) '
. , .-1 V \
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I. .: y j j ' 1 N t 1
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,1 1
i < 1 i l t "r,> 0406I 6-6 < REV. O (l 2 6 1 , ., y ,
FNP-1-M-043 RELIEF REQUEST g (_,) FNP-1 RR-2 Component or Relief Area: Relief from specific dimensional requirements for calibration blocks used to perform the following: ALA-RV-1: Lower head-to-lower shell weld and all lower head welds. ALA-RV-3: Reactor vessel shell-to-nozzle welds and top head welds. ALA-RV-5: Reactor vessel flange and shell
?
welds. Requirement from , which Relief is Requested: Section XI, 1983 Edition with Addenda through Summer 1983, paragraph IWA-2232, requires that ultrasonic examination of vessel welds in ferritic materials greater than 2 in. in thickness be conducted in accordance with l Article 4, Section V, 1983 Edition. Figure
} T-434.1, Article 4, requires that the minimum distance from the ends of the 2 in. long 2-percent T notches to the edges of the block be 3 in.
Basis for Relief: Figure T-546.1, Article 5, Section V, 1983 Edition, is a similar calibration block; however, the clearance required from the ends of the 2-percent notches is 2 in. instead of the 3 in, required by Figure T-434.1, Article
- 4. Experience performing calibration.s using j these blocks has proven fully satisfactory. :
Alternate Examination: The above calibration blocks are ir compliance with the clearance dimensions required for notches by Figure T-546.1, Article 5, Section V, 1983 Edition.
/ '^T 04061 6-7 REV. O
1 FNP-1-M-043 .! f RELIEF. REQUEST FNP-1 RR-3 Component or ' L Relief Arear- Relief from specific dimensional requirements l for calibration-blocks used to perform.the l following: l . . l' ALA-RV-5: Reactor vessel flange and shell welds. Requirement from which Relief is Requested: Section XI, 1983 Edition with Addenda'through' Summer 1983, paragraph IWA-2232, requires that' ultrasonic examination of. vessel' welds 0
^
in ferritic materials greater than 2 in. in ij thickness be conducted in.accordance with , 1 Article 4, Section V, 1983 Edition. Figure i T-434.1, Article 4, requires the aligned side-drilled holes and notches to be located a minimum distance.of T/2 from the end of the l block. The above calibration block'is 0.5 in. short of the required' minimum clearance. OA Basis for Relief: Experience performing calibrations usinglthis block has proven fully satisfactory. Alternate Examination: None; the calibration block is acceptable for-use as is. I t l l l-
'l 1 l
0406I 6-8 REV. O
)
1 l FNP-1-M-043 ) RELIEF REQUEST I i k_ FNP-1 1 RR-4 Component or Relief Area: Ultrasonic examination of piping systems and j vessels less than 2 in. in thickness. l 1 Requirement from j which Relief is j Requested: Section XI, 1983 Edition with Addenda through / Summer 1983, paragraph IWA-2232(b), limits I the use of Appendix III'to ultrasonic examination of Class 1 and Class 2 ferritic steel piping systems having a nominal wall thickness of 0.2 in. to 6 in.
~
Basis for Relief: When the calibration blocks used for performing ultrasonic examinations at Farley . Nuclear Plant were designed, the 1974 ASME I Code, Section XI, combined the requirements i for piping and vessels under 2.5 in. The details of calibration block design were provided in Article 5 of Section V. Consequently, the calibration blocks for most (~) (_/ piping and all thin-wall vessels were I designed to the same requirements. With the i addition of the alternative machined ! calibration notches, the calibration blocks i for thin-wall vessels and piping are {' compatible with the calibration block design , requirements of Appendix III, Section XI, l 1983 Edition. The calibration blocks for ! l ferritic and austenitic piping systems 2 in. and greater in thickness are considered under the provisions of IWA-2240 and Appendix III-3430 of Section XI, 1983 Edition, i Alternate Examination: Section XI, 1983 Edition, with Addenda through Summer 1983, Appendix III, will be used to perform ultrasonic examination of f l Class 1 and 2 ferritic or austenitic I materials, piping systems, or vessels under 2 in. in thickness.
)
s_- 0406I 6-9 REV. 0 l l 1
FNP-1-M-043 RELIEF REQUEST
,m
'(_) FNP-1 RR-5 Component or Relief Area: Wall thickness and curvature differences between calibration blocks used to perform ultrasonic examinations and the components to be examined. Requirement from which Relief is Requested: Section XI, 1983 Edition with Addenda through Summer 1983, Appendix III, paragraph III-3410, requires that the basic calibration shall be made from material of the same nominal
~
diameter and nominal wall thickness or pipe ' schedule as the pipe to-be examined. Basis for Relief: The design of the existing calibration blocks used for piping and thin-wall vessels was done under the provisions of Section V, 1974 Edition with Addenda through Summer 1975. Alternate
/% Examination: The existing calibration blocks for piping ')
(_ and thin-wall vessels are in compliance with 3 j the wall thickness and curvature tolerances between the blocks and the test part as required by Section V, 1974 Edition with Addenda through Summer 1975, Figure T-533(a) , and paragraph T-533.1, respectively. j l l 1 I 0406I 6-10 REV. O __________________2
( FNP-1-M-043-RELIEF. REQUEST-
) FNP-1 RR-6 ] l Component or l Relief Area: Materials for fabrication of calibration
! blocks used to perform ultrasonic examination H l and acoustic compatibility with the. component to be examined. Requirement from which Relief is . . Requested: Section XI, 1983 Edition with Addenda through Summer 1983, Appendix 1III, paragraph III-3411,. requires that calibration blocks shall be 1 fabricated'from one of the materials 'l specified for the piping being joined by the r f weld.
. . .i Basis for' Relief: The materials used for fabrication.of the j existing calibration blocks used for piping j and thin-wall vessels was selected under the:
provisions of Section V, 1974 Edition with ] Addenda through Summer 1975. f Alternate Examination: The existing calibration blocks for piping , and thin-wall vessels are'in compliance with the acoustic compatibility requirements of Section V, 1974 Edition with Addenda through Summer 1975, paragraph T-533.
'I
\
i 1 0406I' 6-11 REV. O __________________J
FNP-1-M-043 RELIEF REQUEST (3 FNP-1 (m / RR-7 Component or Relief Area: Dimensional requirements for calibration notches placed in ultrasonic calibration blocks. Requirement from which Relief is i Requested: Section XI, 1983 Edition with Addenda through 1 Summer 1983, Appendix III, paragraph III-3430, j requires that basic calibration blocks shall 1 contain notches that are at least 1.0 in. .] long. l l Basis for Relief: Piping calibration blocks ALA-9 and ALA-26 I have notches that are 5/32 in. and 1/16 in., , I respectively, under the required length of j 1.0 in. The only possible consequences of !; these discrepancies is that the sensitivity level of the ultrasonic instrument could be j slightly higher than required, resulting in a s more critical examination. These ( irregularities have not presented.any A problems to date. Correcting the condition would not be prudent and would be of questionable value when considering possible damage to the blocks by subjecting them to additional machining. Alternate 1 Examination: None; ALA-9 and ALA-26 are acceptable for use as is, i lV 0406I 6-12 REV. O
FNP-1-M-0431 RELIEF REQUEST l- FNP-1 -
-)
RR-8 l 1 Component o. Relief Area: Volumetric examination of the pressure-retaining reactor vessel lower. head peel segment meridional weld. Reference drawings ALAl-1100B, weld No. 9 through 14, and i D-351114, sheet'1 of 3. , I Requirement from which Relief is Requested: Item No. Bl.22, Category B-A, Table. IWB-2500-1 of ASME Section XI, requires a volumetric examination of one of the meridional welds during successive inspection r
~ i intervals. Applicable examination volume is l shown on Figure IWB-2500-3, and includes. ,
essentially 100 percent'of the~ weld length., Basis for Relief: Incore instrumentation housing penetrating, the vessel bottom head limits.the coverage of 1 the required volume and length'of the' weld. (~ Alternate ) i Examination: None, manual ultrasonic examination will' be performed from the outside of the vessel to j 1 the maximum extent on a best effort basis. ] 1 i i I 1 l l t 1 0406I 6-13 REV. 0 i
y l FNP-1-M-043 RELIEF REQUEST FNP-1 RR-9 Component or . ) Relief Area: . Volumetric examination of all nozzle-to- U vessel: welds in the pressurizer. . Reference drawings.ALA1-2100B, weld No. 9 through'14,. and D351'114,.. sheet 2.of 3. , Requirement from which' Relief-is Requested: . Item No. B3 .110, : Category B-D, Table 1 IWB-2500-1.of ASME,Section XI requires'a. j volumetric examination of the nozzle-to-vessel. weld. .TheLapplicable examination volume is shown in Figure r . IWB-2500-7(b) and' includes 100 percent ofjthe - weld length. - Q 1 Basis for Relief: The geometric configuration of all'these nozzles (Attachment 9-1) prevents ultrasonic j examination from being performed from the a nozzle side of the weld to the extent k L required. Approximately 25 percent of the base metal (n) the nozzle side of the weld.can
]j be examined.
Alternate Examination: All these welds will receive a surface examination of the areas not scanned by the
)
l ultrasonic method. 1 l 1
'l 4
l t 1 0406I 6-14 REV. 0
'I
FNP-1-M-043 RR-9 ) ATTACHMENT 9-1 i i W ' 1 NOZZLE FORGING * (CARBON STEEL) NOZZLE-TO-VESSEL WELD (CARBON STEEL) l 4 ( l t VESSEL HEAD (CARBON STEEL) WELD DEPOSITED CLADDING (STAINLESS STEEL WELD) l l PRESSURIZER NOZZLE-TO-VESSEL WELD CONFIGURATION s] 6-15 REV 0
i FNP-1-M-043 RELIEF REQUEST ,s N_-) FNP-1 RR-10 ! i, Component or Relief Area: Volumetric examination of nozzle-to-pipe safe-end welds in all steam generators (primary side). Reference drawings ALAl-4100, ALAl-4200, and ALAl-4300, weld No. 4DM and SDM, and D351114, sheet 1 of 3. Requirement from which Relief is Requested: Item No. B5.70, Category B-F, Table IWB-2500-1 of ASME Section XI requires a { volumetric examination of nozzle-to-safe-end < butt welds in the steam generator. : Applicable examination volume is shown in - Figure IWB-2500-8 and includes 100 percent of ' the weld length. Basis for Relief: The configuration of the steam generator ) nozzle-to-safe-end welds is shown in Attachment 10-1. Examination of these welds is limited both by nozzle geometry and the 1
/~N presence of a weld-deposited clad overlay on l
'qs) the safe-end nozzle interface. Ultrasonic ! examinations can be performed from the pipe side and the weld surface, but are severely limited from the nozzle side by the rough, j as-cast surface and the clad overlay. ) Coverage of approximately 90 percent of the required volume is achieved from the pipe side of the weld. 1 Alternate Examination: Surface examinations will be performed on ; essentially 100 percent of the required l examination area. Also, ultrasonic examinations will be performed from both the pipe and weld surfaces as allowed by T-532 of Section V. All of the weld metal, including the weld root, will be inspected. i O 0406I 6-16 REV. 0
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i FNP-1-M-043 RELIEF REQUEST () FNP-1 RR-11 i Component or Relief Area: Volumetric examination of the nozzle innar ! radius section for steam generator inlet and ! outlet nozzles. Reference drawings ALAl-3100, ALAl-3200, and.ALAl-3300, steam {a generators 1A,'1B, and IC, and D351114, sheet { 1 of 3. i 1 Requirement from which Relief is i Requested: ASME Code. Item No. B3.140,* Category.B-D, I requires. volumetric examination of the nozzle j inside-radiusLsection for steam generator . r i nozzles. Figure IWB-2500-7 shows the ..
~
applicable examination volume. Relief is , 'j requested from performing this examination- l for the inlet and outlet nozzles on'all steam { generators, i Basis for Relief: The steam generator primary side nozzles are ) I integrally cast as part of the channel head; j
/~' therefore, no welds exist which' require "
(,)s volumetric examination. The steam generator nozzle inner radiused section cannot be volumetrically examined from the outside of the nozzle or channel head because the rough, I as-cast contact surface is not suitable for ultrasonic coupling and the geometrical configuration requires an excessively long test metal distance resulting in high ultrasonic attenuation. The areas inside of the nozzles and channel head are covered with cladding in the "as-welded" condition; therefore, meaningful volumetric examination ! cannot be performed from the as-welded surface. Even with proper preparation of the , inside surface for volumetric examination, an adequate examination of the area of interest (base metal just.below the cladding).could not be achieved due to the resulting ultrasonic response at the clad-to-base metal interface. Alternate Examination: The inside surface of each steam generator primary side nozzle inner radiused.section will be visually examined. The examination O' area will include the inner radius surface region shown in Section XI, Figure IWB-2500-7, to the extent practical. 0406I 6-18 REV. O i l
l FNP-1-M-043 i RELIEF REQUEST , 1 [.s- FNP-1
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RR-12 l i Component or i Relief Area: Delete VT-4 visual examination method and I l examination requirement and redefine VT-3 l visual examination method in accordance with l Paragraph IWA-2213 of ASME Section XI, 1986 i Edition. 1 1 Requirement from j ! which Relief is 1 l Requested: Item No. F3.50, Category F-C, Table IWF-2500-1 and paragraph IWA-2214 of ASME : Section XI, 1983 Edition, require that VT-4 )j visual examination shall be conducted to . determine conditions relating to the - ! operability of components such as snubbers i and spring loaded / constant weight hangers. j Also VT-4 testing confirms functional j adequacy, verification of the setting, or j freedom of motion, which may require ; operability testing. j f-w Basis for Relief: Operability testing was inapproiately (_,g/ included in VT-4 as an examination method. 1 Also, paragraph IWA-2214(b) from the 1983 j Section XI code is inconsistent with industry } visual examination practices. An inspector l does not perform bench testing of snubbers / constant load / spring type supports. l These activities are performed by maintenance , technicians. The 1986 Edition of ASME i Section XI has deleted VT-4 examination I altogether and has redefined VT-3 to include examinations for conditions that could affect i operability or functional adequacy of snubbers, and constant load and spring type supports. Alternate 1 Examination: None. Operability tests shall be performed in accordance with the Farley Technical l Specifications. j l 1 0406I 6-19 REV. O - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . - . ._ _A
RELIEF REQUEST FNP-1-M-043-FNP-1 (a) % RR-13 Component or Relief Area: Volumetric examination of pressure retaining branch pipe connection welds in Class 1 piping. Attachment 13-2 lists all affected welds. Reference drawing D351114, sheet 1 of l 3. Requirement from which Relief is Requested: Item No. B9.31, Category B-J, Table IWB-2500-1 of ASME Section XI, requires volumetric examination of branch pipe connection welds 4 in. nominal pipe. size and , larger. Applicable examination volumes are ! shown in Figures IWB-2500-9, -10, and -11 and - include 100 percent of the weld length. ~ Basis for Relief: The geometric configuration of these welds (see Attachment 13-1) prevent ultrasonic ! examinations from being performed from the weld surfaces. Attachment 13-2 describes the location of those limited areas and the approximate examination coverage. f "s'3 ') Alternate Examination: None; however, the surface examinations as required by the Code will also be performed ) on these welds. l
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I l l 1 L s en 1 0406I 6-20 REV. 0
1 k FNP-l-M-043 RR-13 ATTACHMENT 13.1-
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CENTERLINE NOZZLE l r ! NOZZLE FORGING (STAINLESS STEE L)
- 1 l BRANCH CONNECTION l WELD (STAINLESS STEEL)
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[ REACTOR COOLANT PIPE (CAST AUSTENITIC STAINLESS STEEL) BRANCH NOZZLE CONNECTION WELD 6-21 REV O
RELIEF REQUEST FNP-1-M-043 FNP-1 j RR-13, ATTACHMENT 13-2 Category B-J, Branch. Pipe' Connection. Welds with Exam Limitations Examinations () Configurations Dwg. No. Weld No. Extent Hot leg loop #1 .ALAl-4100 15 BC 80% 6 in. branch connection Hot' leg loop #1' ALAl-4100 '.16 BC- 80% i 12 in, branch connection : Cold leg loop #1 ALA1-4100 20'BC. -80%i
- 6 in, branch connection Cold leg loop #1 ALA1-4100 21 BC 80%-
4-in. branch connection Cold leg loop #1 ALA1-4100 22 BC- 80% 12 in. branch connection Hot leg loop #2 ALA1-4200 15 BC -80% 6 in, branch connection i i Hot leg loop #2 ALAl-4200 16 BC 80%; ] 14 in. branch connection i Cold leg loop #2 ALA1-4200 20 BC 80% , 4 in. branch connection 1 Cold leg loop #2 ALAl-4200 21 BC- 80% 12 in, branch connection Cold leg loop #2 ALA1-4200 23 BC 80% 6 in.-branch connection j Hot leg loop #3 ALAl-4300 15 BC 80% 6 in. branch connection Hot leg loop #3 ALAl-4300- 16 BC 80% 12 in. branch' connection Cold leg loop #3 ALAl-4300 20 BC. 80%' 6 in. branch connection Cold leg loop #3 ALA1-4300' 21 BC, 80% 12 in. branch connection 0406I 6-22 REV. 0 _ _-_ __ - _ L
1 l RELIEF REQUEST FNP-1-M-043 FNP-1 r~'s i
! RR-14 Component or i' Relief Area: Volumetric examination of the reactor vessel flange ligament areas. Reference drawing ALAl-1100A and ALA1-1300, Examination Identification No. L1, L25, L26, L27, L41, L42, L43, L57, L58, and D351114, sheet 1 of 3.
Requirement from which Relief is i Requested: Item No. B6.40, Category B-G-1, Table j , IWB-2500-1 of ASME Section XI, requires a .j l volumetric examination of threads in reactor ] vessel flange stud holes. The applicable examination volume is shown in Figure IWB-2500-12. r Basis for Relief: During the examination, these guide studs , j prevent the ultrasonic transducers mounted on- l l the remote tool arm from accessing the l l ligaments around each guide stud as well as ! the ligaments between the stud holes on l l either side of the guide studs (numbers 1, l 25, 27, 41, 43, and 57). l c (" \ 1 N Alternate i Examination: None; however, the remaining 49 ligaments I will be ultrasonically examined as required by the ASME Code, Section XI. t i '
%..s) 0406I 6-23 REV. 0-
RELIEF REQUEST FNP-1-M-043 q FNP-1 O ( ,) RR-15 i I Component or Relief Area: Visual examination of reactor coolant pump internal pressure boundary surfaces. Reference drawing D351114, sheet 1 of 3. Requirement from which Relief is Requested: Item No. B12.20, Category B-L-2, Table IWB-2500-1 of ASME Section XI, requires a visual (VT-3) examination of Class 1 pump internal pressure boundary surfaces. This examination is limited to one pump in a group j performing similar functions in a system. Basis for Relief: Disassembly of a reactor coolant pump for the ~ i visual examination during the inspection interval in the absence of required , maintenance represents an unnecessary exposure to radiation and contamination and violates as-low-as-reasonably-achievable (ALARA) guidelines for occupational dose rates. In view of the cost in man-rem and in view of the minimal benefits obtained, we
./~ conclude that this code requirement does not i
(_}/ provide sufficient benefits to justify the radiation exposure. i' Alternate Examination: The exterior of the RCP casing will be visually examined during the RCS hydrostatic j pressure test as required by IWB-5000. A i visual examination, not to exceed once per i interval, will be performed on the internal pressure boundary surface of one RCP as required by Item B12.20, Category B-L-2, if l maintenance or operational problems are ' encountered which require the removal and disassembly of the internals. l l l l rw 1 i 0406I 6-24 REV. O l 1 - - - - - - _ -
1 i RELIEF REQUEST FNP-1-M-043 FNP-1 l
/~5 l Q RR-16 i
Component or Relief Area: Visual examination of the internal pressure j boundary surfaces of Class 1 valves. See l Attachment 16-1 for valves requiring this I examination. 'l
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Requirement from which Relief is l [ Requested: Item No. 12.50, Category B-L-2, Table j IWB-2500-1 of ASME Section XI, requires a { visual (VT-3) examination of the internal : pressure boundary surfaces of Class 1 valves ) exceeding 4 in. nominal pipe size. The ) examinations are limited to one valve'within each group that are of the same . r
~
constructional design and manufacturing l method, and that perform similar functions in , I the system. j i l Basis for Relief: Disassembly of these valves for visual i examination during the inspection interval in j the absence of required maintenance { represents an unnecessary exposure to l l /~T radiation and contamination and violates l (_) ALARA guidelines for occupational dose rates. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this code requirement does not provide sufficient benefits to justify the radiation exposure. In addition, the ! manufacturer of these valves neither recommends nor requires valve disassembly for the performance of routine maintenance or inspections. Alternate Examination: As required by Section XI, IWA-5000, the exterior of this valve body will be visually examined during the RCS hydrostatic test. A visual examination, not to exceed once per l interval, will be performed on the internal I pressure boundary surface of one valve in ( each group listed in Attachment 16-1 as required by Item B12.50 and Category B-M-2 if I maintenance or operational problems are encountered which require disassembly and complete removal of the valve internals.
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FNP-1-M-043
,_3 RELIEF REQUEST
(_/ FNP-1 RR-17 Component or Relief Area: Reference system for all welds and areas subject to surface or volumetric examination. Requirement from which Relief is Requested: IWA-2600 of ASME Section XI requires the establishment of a reference system for all I welds and areas subject to surface or volumetric examination. This system shall permit identification of each weld, the location of each weld centerline, and marking . at regular intervals along the length of each J weld. . Basis for Relief: To perform actual marking of welds in order' to identify each weld centerline, length ! locations, etc., would require many manhours i of radiation exposure. Many of the welds are -i ,g insulated and as such many manhours of () radiation exposure would be required to remove and reinstall insulation just to j facilitate marking. Also many manhours of I radiation exposure would be involved in i marking the welds. l Alternate Examination: Administrative controls which are detailed in procedures provide adequate instructions to ensure measurements are repeatable and that any indications can be accurately located. l V) 0406I 6-27 REV. O .!
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RELIEF REQUEST FNP RR-18 Component or. Relief Area: Volumetric examination of pressure retaining. welds in the regenerative heat exchanger. Reference' drawings ALA2-3560, welds No. 1 through 12, and D351116, sheet._1'of 4. Requirement from which Relief is
' Requested: Items No. C1.20 and C1.30, Category C-A,-
Table IWC-2500-1^of'ASME Section~XI, require volumetric examination of' pressure vessel-head circumferential-welds.and' tube sheet-to-shell: welds. The' applicable -- examination volume is shown in Figures ' IWC-2500-1.and -2,'and includes essentially- ,, 2 100 percent of.the. weld length.- Basis for Relief: The: regenerative heat exchanger 1shell is fabricated from centrifugally; cast austenitic steel material which limits ultrasonic examination to the half-node technique ~. -The geometric configuration of the. weld surface. l O and the location of_ adj acent nozzles and . supports provide. limitations to the' extent'of the examinations coverage. Alternate Examination: Ultrasonic examination will be performed to the maximum extent practical on a best effort basis. Surface examination will.also be performed to supplement ~ volumetric examinations. l l l l [\' U 0406I 6-28 REV. O
, ,l
'FNP-1-M-043' RELIEF REQUEST
) FNP-1 1 RR-19 Component or Relief Area: Volumetric examination of.the pressure retaining welds in thin wall. Class 2' pressure .
I vessels. Affected areas are head-to-shell-and flange-to-shell welds.in the following: o Seal water heat exchanger reference- ! drawings ALA2-3550 and D351116,. sheet 2 of i
- 4. O i
o Letdown reheat'h' eat exchanger - reference drawings ALA2-3540 and D351117, sheet-1. , o Reactor coolant filter - reference l drawings ALA2-2110 and D351116, sheet 2 of .- 1 4. o Seal water return filter - reference ! drawings ALA2-2100 and D351116', sheet 2 of ,
- 4. j4;
, Requirement from \-, which Relief is Requested: Items No. C1.10 and C1.20, Category C-A, 1 Table IWC-2500-1 of ASME Section X1, requires j volumetric examination of pressure retaining y welds in Class 2 pressure vessels. I Applicable examination volumes are shown on Figures IWC-2500-1 and -2 and include essentially 100' percent of the-weld length. Basis for Relief: The thickness of the materials. utilized for .; the construction of these. components-(0.165 ! to 0.188 inches).is such that meaningful J results could not be expected with ultrasonic examination. I Alternate Examination: Welds on these components will be examined by surface and visual methods. ; o0 v
, i 0406I. 6-29 REV. 0 ,
'FNP-1-M-043 RELIEF. REQUEST. q
( FNP-1 . RR-20 Component or .
. Relief Area: . Surface examination.of integrally. welded
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attachments on charging pumps. Reference pump:No. lA, IB, and'1C,. drawings ALA2-5100, ALA2-5110, and ALA2-5120,'and D351116, sheet' 2 of 4'. Requirement from' , which Relief is-Requested: Item No. C3.30, Category C-C, Table IWC-2500-1 of'ASME SectionLXI, requires a i surface: examination of 100 percent'of'the l areas required by Figure IWC-2500-5 for each- -' welded attachment of one charging pump. w-Basis for Relief: Due to the component configuration, location, and support; design,-approximately 20' percent of each integrally welded attachment'is inaccessible for examination. Alternate
/"'g Examination: None;'all accessible. portions.of' welded 'V attachments will receive a surface examination. supplemented by a visual, examination.
l O 0406I 6-30 REV. O'
FNP-1-M-043 RELIEF REQUEST
,O N ,/ FNP-1 RR-21 Component or Relief Area: Hydrostatic testing of Class 2 containment pressure sensing lines. Reference drawings }
D351115, sheet 3 of 4, penetration no. 65, 73, 74, 75, 76, and 97. Requirement from which Relief is Requested: Item No. C7.40, Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test for all Class 2 pressure i retaining components once every 10-year inspection interval, in accordance with ' paragraph IWC-5222, Basis for Relief: These containment pressure sensing l capillaries are filled with silicone oil and . are sealed. There are no provisions to l pressurize these lines with additional silicone oil to satisfy the ASME Section XI hydrostatic test requirements. However, a (~h full range (0-65 psi for low pressure sensors
\s l and 0-225 psi for high pressure sensors) calibration is performed on these-lines every 18 months to verify their accuracy and integrity, in accordance with Farley l Surveillance Test Procedures STP-220.1 through 220,4. Any leakage from these pressure sensing lines during normal operation would result in instrument failure and would be corrected to maintain instrument operability.
Alternate Examination: The calibration of these sensors will be performed in lieu of a hydrostatic or pressure test. l l r~ r k l l 0406I 6-31 REV. O
i i i n - o y h,, s r " ' y l F.ELIEF REQUEST f' FNP-1-M-043 k]) FNP-1 s [ I } ;
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RR-22 , s '
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Component or i < o _ Relief Area: Hydr,ostatic testing of portions of Clas's2 '[ p' pipi,xg and inter 4 components at reduced ; pre 9aure. + 3 .3 h i The following portions of Class 2 piping are affected. A. Chemical injection :o main feedwater l t lines between valv . Q1N25V002A, B, and C j and main feedwater lines (line Nos. DCB-1A, DCB-1B and DCB-1C). 'R'eference ; drawing D351102, sheet 1 of El B. Main feedwater lines from valves t Q1N21V001A, B,; and C to the steam generators (linedk[ DBB-1) . Reference . i drawing D351123, $nfeet 1 of 1. r , C. Steam generato&r blowdown lines to valves
< Q1G24V003A, B, and C from th9 steam l generators (line No. j e CBB-8, CBB-9, and CBB-10). CBB-5;laEterencefAhp5y CBB-7,a
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) drawing D351122, Sheet 1 of 3. !
,.8, h 'D. AU;hliary feedwater piping from valves !
Q1N23V011A,'Bh and C toIche main , feedwater ines A l Referedce }trawkng(line D351106, No. DBB-2). Sheet 1 of 1. I l 1 l i E. Gross f, ailed fuel dstector to letdown betwojaQ1E21V400'andconnectionwith y i GCB-/. ' ;..i ne (lino No.'ECB-1). sReference drayfugD351116, Sheet 2 of 4. s F. Chargttg pump discharge mini-flow piping from valves Q1E21V259A, B, and C up to valve, Q1E21V265 (line no. CCB-18). Reference drawing'D351116, sheet 2,of 4. b Requirement from which Relief is >. r Requested: Category C-H, Table IWC-2500-1 of ASME . Section XI, requires a hydrostatic test of ' , ..a all Class 2 pressure retaining components "i d once ever3n,10-year inspection interval in ( accordance Ipth paragraph IWC-5222. ~ ,
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RELIEF REQUEST FNP-1-M-043 ( FNP-1 9p)- t I RR-22 (Continued)
< Eard's for Relief: The portions of the Class 2 systems listed
'"i above cannot be isolated from lower pressure
( '- rated Class 2 piping. Performing the - 7' hydrostatic tests at the required pressure would result in overpressurizing the lower fi'
- pressure rated Class 2 piping.
o i Alternate ! Examination: Visual examination for evidence of leakage
,, will be conducted on the portions of Class 2 systems listed above while at the test i pressure for the lowest pressure rated Class '
2 piping. !
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.3 m ( )
.i s j RR -23 1
Compo:ssnt or .i . l RelieIIArea: ' Hydrostatic testing of portior.v g of Class 2 1
't components to' the requirements of the 1 connecting Class 1 piping. Affected portions <
are as followw: i i ff A. Vents, drains, instrumentation lines, and branch connections off Class 1 lines-l (line No.~CCB-27, CCD-33, CCB-34,.CCB~38,. l , CCB-39, CCB-40, CCB-41,.CCB-42, CCB-43,
- CCB-44, CCB-47A, CCB-47B,.4no'CCB-47C).
. Reference drawings D351114; sheets 1~'of cf '
3,'2 of 3, 3 of 3,'and D351107, sheet 1
of 3. '%4 i
s B. Pressurizer sp' ray #41ves bypass' lines L
;- (line No. CCB-57).' Reference. drawing ,
D351114, sheet 2 of 3. , C. Sample lines offnreactor coolant system I
,J
,(RCS) loops and pressu'riz.tr (line No.
I
'CCB-37, CCB-54, CCB-55,'and CCB-56).
Reference drawing D351114,- sheets 1 of 3, ) 2 of 3, a d D351107, sheet'2.of'3. j D. 'Soron injection tank discharge to;RCS i (cold legs) between valves Q1E21VOO4A.and ,
'B, Q1E21V029;, and Q1E21VO62A,.B, and C i
(' (line No. CCB-21). . Reference drawing' D351115, sheet *1 of 4. 1 E. High-head safety injection (HHSI) pump a discharge to RCS (cold: legs) betWeen i valves Q1E21V063 and Q1E21VO66A, B, and C (line No. CCB-22). Reference drawing l D351115, sheet 1 of 4.
- l ,\
i F. HHSI pump discharge to RCS (hot 11egs) j
'A between valves Q1E21V068-and.Q1E21VO78A, ;
I f- .B, and C (line No. CCB-30). Reference ; l drawing-D351115, sheet 1 of-4. ! G. URSI pump discharge to RCSlThot legs) between' valves Q1E21V072 ar.d Q1E21V079A, E B, and C.(line No. CCB-31);C Reference, e drcawing D351115, sheet 1 oi 74' .
- H. Brandh.linesconnecting'the' accumulator.
X.,- discharge. lines to the accumulator test I ' line (line No. CCB-24, CCB-53, and l ; , CCB-54). Reference drawing D351115, l sheet 2 of 4. L 0406I 6-34 REV. 0 1 I T _ :_...__.__ -
1 RELIEF REQUEST FNP-1-M-043 FNP-1 ( v f. RR-23 (Continued) I. Residual heat removal (RHR) pump discharge to RCS (hot legs) between valves Q1E21V044 and Q1E21V076A and B (line No. CCB-29). Reference drawing D351115, sheets 1 of 4 and 2 of 4. J. RHR to RCS (cold legs) between valves QlE21V023A and B and Q1E21VO21A, B, and C (lines No. CCB-22 and CCB-32). Reference drawing D351115, sheets 1 of 4 and 2 of 4. K. Alternate charging line between valves Q1E21V243 and Q1E21V113 (line No. CCB-9). Reference drawing D351116, sheet 1 of 4. l r L. Normal charging line between valves - (Q1E21V244 and QlE21V112 (line No.
- CCB-10). Reference drawing D351116, sheet 1 of 4.
M. Normal charging line control valve bypass line between valves Q1E21V143 and
~w Q1E21V112 (line No. CCB-45). Reference l drawing D351116, sheet 1 of 4. '~#
N. Reactor coolant pump No. I seal-leakoff lines to valves Q1E21V589A, B, and C (line No. CCB-48A, CCB-48B, and CCB-48C). Reference drawing D351116, sheet 1 of 4. O. Reactor pressure vessel (RPV) head vent line from Class 1 line to valves i Q1B13HV-2 and Q1B13HV-4 (line No. l CCB-63). Reference drawing D351114, sheet 1 of 3. Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI requires a hydrostatic test for all Class 2 pressure retaining components once every 10-year inspection interval, in accordance with paragraph IWC-5222. Basis for Relief: It is impractical to conduct a Class 2 hydrostatic test on the portion of the system listed where the only means of pressurizing-the Class 2 system is through the Class 1 system or when the boundary between the two (~} ( ,/ systems is a check valve arranged for flow l from the Class 2 system to the Class 1 system. 0406I 6-35 REV. 0 l i
i RELIEF REQUEST -FNP-1-M-043 I FNP-1 ('h (s) RR-23 (Continued) J Alternate Examination: Visual examination for_ evidence of leakage will be conducted on these portions of ! systems.in conjunction with.the hydrostatic - test performed on the adjoining Class 1 system. I
.]
.?
i
=
1 e l
)
O l l v} 0406I 6-36 REV. O
RELIEF REQUEST' FNP-1-M-043 FNP-1 RR-24 Component or . . Relief Area: Hydrostatic testing'of theJrelief line. discharge header piping to the pressurizer relief tank. :Affected line'No. 2" HCB-62. Reference drawing D351114, Sheet 2 of 3. Requirement from which. Relief is Requested: .' Article IWC-5000 of ASME Section XI requires a hydrostatic test for all Class 2. pressure' retaining components once every lO-year interval'in accordance with paragraph-IWC-5222. Basis'for Relief: By installing a blind flange. downstream of. ' r check valve QV054 a system hydrostatic test can be' performed,- but this test will .. jeopardize the' relief functions of the RHR pump relief valves. Since at least one train-of the RHR system is always. required'to-operate, a system hydrostatic test downstream of the relief valves is impractical. O Alternate Examination: None. O 0406I 6-37 REV. O 1 L---__-_--______.---_-__-___-- __ -_ ----_ -- _ . _ _ . _ . _ _ .
RELIEF REQUEST FNP-1-M-043 FNP-1 l RR-25 Component or Relief Area: Hydrostatic 1 test for'the Class 2 pressure retaining reactor' vessel flange' seal leakoff 1
.line from the reactor vessel to' valves- i I
Q1B13V019 and-Q1B13V018 (line No. CCB-36). Reference drawing D351114, Sheet 1 of 3. Requirement from 'l which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test'for all Class 2 pressure-retaining components .) once every 10-year inspection interval, in accordance with paragraph IWC-5222. 3
-: i L Basis for Relief: Performance of a' hydrostatic. test for this -
l system is impractical because pressurization:
- 1 of the flange. seal leakoff line could potentially result.in damage to the' reactor. l vessel flange seals.
Alternate Examination: For,the reactor vessel flange seal leakoff (~' line from the. reactor vessel,,the portion of Class 2 piping up.to valves Q1B13V019 and Q1B13V018 will'be visually examined during l the Class 1 hydrostatic. test. 1' l 1 i q s l 0406I 6-38 REV. O i L____________----___-___
RELIEF REQUEST FNP-1-M-043 FNP-1 RR-26 Component or
. Relief Area: Hydrostatic testing of portions of Class 2
. piping systems isolated from the test boundary by closed check valves. Affected lines are as follows. Reference drawing D351116, Sheet 2 of 4.
A. Charging pump suction piping from the chemical mixing tank between valve Q1E21V186 and check valve Q1E21V187 (line No. HCB-11). B. Hydrogen and nitrogen supply piping to the VCT from check valve Q1E21V201 to ( isolation valves Q1E21V202, Q1E21V583, ' e and Q1G21V260 (line No. HCB-68). C. Charging pump suction piping from volume control tank between check valve Q1E21V211 and locked closed valve Q1E21V212 (Line no. 2" HCB-16). D. Charging pump suction piping from boric 9 acid blender between check valve Q1E21V210 and normally closed valve Q1E21V264. Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test for all Class 2 pressure retaining components once every 10-year inspection interval in accordance with IWC-5222. Basis for Relief: Pressurization of the portions of system piping listed above cannot be assured due to the position of the check valves. The check valves listed prevent flow from the test fill point to the specified boundary valves. Alternate Examination: Portions of the above mentioned Class 2 piping will be visually examined during the Class 2 system functional test. O 0406I 6-39 REV. O
RELIEF REQUEST ENP-1-M-043 FNP-1 \_ ,/ RR-27 Component or Relief Area: Hydrostatic test for the Class 2 waste gas drain filter line to VCT from isolation valve Q1G22V249 through check valve Q1G22V248 (line No. HCB-92). Reference drawing D351119, sheet 5 of 7. Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test of all Class 2 pressure retaining components once every 10-year inspection interval, in accordance with IWC-5222. Basis for Relief: Pressurization of this portion of the waste gas drain filter line would require check , valve Q1G22V248 to hold the hydrostatic test pressure. Leakage through this valve could potentially result in overpressurization and subsequent damage of the waste gas filter. Alternate [~N Examination: The portion of Class 2 piping between valve A Q1G22V249 and check valve Q1G22V248 will be visually examined during the Class 2 system functional test. lO () 0406I 6-40 REV. O
RELIEF REQUEST FNP-1-M-043 FNP-1 ( ( ,f RR-28 ! Component or Relief Area: Volumetric examination of the nozzle inside radius section of the steam outlet nozzle on the Steam Generators. Reference drawing D-351110, sheet 1 of 2. Requirement from which Relief is j Requested: Item No. C2.22, Category C-B, Table IWC-2SOO-1 of ASME Section XI, requires a J volumetric examination of the nozzle inside-radius section for nozzles in pressure-retaining vessels. The required _ examination volume is shown in Figure IWC-2500-4. Relief from this requirement is requested. r Basis for Relief: The flow restrictor assembly appears to be , welded to the nozzle at the location of the inner radius shown on Figure IWC-2500-4. Therefore, the geometry of these nozzles with i the flow restrictor assembly will not allow a l meaningful ultrasonic examination. } g Alternate j
\ Examination None. j l
l l 0 u-l 0406I 6-41 REV. O
1 RELIEF REQUEST FNP-1-M-043 FNP-1 t~'N (,,) RR-29 Component or Relief Area: Hydrostatic testing of Class 2 boron , injection recirculation pump discharge piping between valves Q1E21V006A and B, QlE21V005A and B, and the adjoining drain piping (line No. CCB-62). Reference drawing D351115, sheet 1 of 4. Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test for all Class 2 pressure retaining components once every 10-year inspection interval, in accordance with IWC-5222. Basis for Relief: Performance of a hydrostatic test on the
- 1 portion of the system described above requires the use of check valves which are subject to leakage when used as a hydrostatic J test boundary. Leakage past these valves could potentially pressurize and overstress
,_s the adjoining Class'3 piping.
%- Alternate Examination: These lines will be visually examined during operation as a part of the adjoining Class 3 system leakage test. 0406I 6-42 REV. 0
RELIEF REQUEST FNP-1-M-043 FNP-1 RR-30 Component or Relief Area: Hydrostatic testing of the Class 2 portion of the steam generators and associated piping. Reference drawings D351110, sheet 1 of 2 and D351122, sheet 1 of 3. Requirement from which Relief is Requested: Item No. C7.10, Category C-H, Table IWC-2500-1 of ASME Section XI, requires a system hydrostatic test of Class 2 pressure retaining pressure vessel once every 10-year inspection interval, in accordance with IWC-5222. Also, paragraph IWA-5213(d) requires a 4-hour holding time for hydrotest : of the insulated system. ^ Basis for Relief: In order to prevent undue stress on the steam generators, Westinghouse recommends that the hydrostatic test of the secondary side of the steam generators be conducted at 1.25 P for a minimum of 10 minutes and a maximum of 30 minutes, and then reduced to operating S pressure, 1.0 P , for the balance of the 4-hour holding period. The related Class 2 piping is hydrostatically tested along with the steam generator. Alternate Examination: The Class 2 portions of the steam generator and related piping will be hydrostatically tested at 1.25 P for a minimum of 10 minutes and a maximum of 30 minutes. The test pressure will then be reduced to 1.0 P for the remainder of the required 4-hour holding time. O 0406I 6-43 REV. O
RELIEF REQUEST FNP-1-M-043 FNP-1 A ( ,) RR-31 Component or Relief Area: Visual (VT-2) examination for leakage of Class 3 service water pumps. Reference drawings D351130, sheet 1. Requirement from which Relief is Requested: Paragraph IWD-2510 and Table IWD-2500-1 of ASME Section XI require that all Class 3 pressure retaining components be subjected to visual examinations (VT-2) in conjunction with the system pressure tests required by paragraph IWD-5000. Basis for Relief: Due to component design and mounting details, , the visual inspection of this vertical centrifugal pump is impractical except at the , pump discharge nozzle. Alternate Examination: Visual inspection of the discharge nozzles will be performed while the pumps are operating. The pump casings will be visually 8
# inspected each time the pumps are removed for
\ ))
% maintenance.
i (, 0406I 6-44 REV. O l
RELIEF REQUEST FNP-1-M-043 FNP-1 RR-32 Component or Relief Area: Visual (VT-2) examination of Class 3 pressure retaining piping which is encased in concrete in the spent-fuel pool cooling system. Reference drawing D351120, Sheet 1 (line Nos. HCC-105, HCC-107, and HCC-108). Requirement from which Relief is Requested: Paragraph IWD-2510 and Table IWD-2500-1 of ASME Section XI require that all Class 3 pressure retaining components be subjected to visual examination (VT-2) in conjunction with the system pressure test requirements of , IWD-5000. Basis for Relief: The design of the piping system does not . provide any means to visually access the encased portions. Visual examination for leakage at ground level is also not possible. Alternate Examination: Integrity of the encased piping will be G demonstrated during normal system functional testing. l l O 0406I 6-45 REV. 0
7
. RELIEF REQUEST' FNP-1-M-043' FNP O(ss/ RR-33 L -Component or Relief. Area: Hydrostatic. testing of portions >of Class'3' piping and' components in theLfollowing systems:which operateLeontinuously during all-modes.of plant operation:
o Service water? . reference drawings D-351128, sheet 1,.D351130, Sheets-1,-_2,- and 3 of-11;. ' a n d .D 3 5 1 1 0 4 ,.. sheets 11,.2,.and 3. o Componenticooling-water;- reference
, drawing D351103, sheets 1, 2, and 3.
1 o Chemical and. volume control -' reference " drawings D351116, sheet 3,.and D351115,. sheet.1- . ,7 o Reactor Makeup,- reference drawings. D351313, Sheet 1'and D37G129, sheet'1. o Spent fuel poolfcooling - ' re'ference Requirement from which Relief is Requested: Paragraph.IWD-2510 and Table IWD-2500-1 of l ASME Section XI' require:that all Class 31
~
I
. pressure retaining components'be subjected'to visual examination-(VT-2) in conjunction with the system pressure tests of'IWD-5000
~
Basis for Relief: Hydrostatic testing of.the above systems is. not practical since they operate: continuously during all modes of plant operations. Alternate Examination: Functional operation of theisystems demonstrates structural ~and leaktight integrity. Visual inspection to verify g .leaktightness will-be performed while the systems are at normal operating pressure. 1 0406I 6-46 REV. 01
RELIEF REQUEST FNP-1-M-043 FNP-1 h RR-34 Component or Relief Area: Hydrostatic testing of Class 3 spray additive piping and components in the containment spray system (reference drawing D351115, Sheet 3). Requirement from which Relief is Requested: Paragraph IWD-2510 and Table IWD-2500-1 of ASME Section XI require that all Class 3 pressure retaining components be subjected to visual examination (VT-2) in conjunction with the system pressure test of IWD-5000. Basis for Relief: While in service these spray additive lines : have an operating pressure of 15 psig and ~ temperature of 100 F, which is well below the , design conditions of 210 psig pressure and 300 F temperature. Therefore, a system hydrostatic test at 1.25 P would not provide a meaningful test. In addition, the hydrostatic test will involve handling of highly corrosive sodium hydroxide, which is undesirable and hazardous to personnel safety. Alternate Examination: A measured flow test in accordance with plant Technical Specification paragraph 4.6.2.2d will be conducted periodically to assure the leaktightness of these Class 3 components. l O 0406I 6-47 REV. O i
RELIEF REQUEST FNP-1-M-043 FNP-1
/s
( ,) RR-35 Component or Relief Area: Hydrostatic testing of Class 3 portions of buried piping in the following system: l o Service water - reference drawing D351130, Sheet 2, virtually all of the lines on this drawing. Requirement from which Relief is Requested: Paragraph IWD-2510 and Table'IWD-2500-1 of ASME Section XI require that all Class 3 pressure-retaining components be subjected to visual examination (VT-2) in conjunction with the system pressure tests of IWA-5000. r Paragraph IWA-5244 describes the detailed requirements for buried components. , Basis for Relief: The design of this system does not allow access for visual examination as required by IWA-5244. l Alternate
/~ Examination: Buried piping will be inspected by conducting
( a visual observation of the ground (at ground elevation) for wet spots while the systems are at operating pressure. This is in accordance with the Final Safety Analysis Report, paragraphs 3.1.41 and 9.2.1.4. 7~
^t-)
0406I 6-48 REV. O 1
; ~,I
' RELIEF REQUEST FNP-1-M-043 FNP-1 RR-36 NJ -
' Component or . ..
Relief Area: Visual (VT-2) examination of heat exchanger tubes of. Class 3' pressure retaining safety-related' heat exchangers, o- Three each component cooling water HX-Q1P17 H001A-B, H001B-AB and H001C-A - reference drawing D351103, sheet 11of 3. Requirement from which Relief is Requested: Paragraph IWD-2510 and'Tabie IWD-2500-1 of ASME Section XI require that all Class 3 pressure retaining components'be.subjectedLto a visual examination (VT-2) in conjunction' r with the' system pressure' tests of IWD-5000. ~ Basis for Relief: Due to. component-design and limited accessibility,'theseLheatl exchanger. tubes cannot be visually inspected under high pressure hydrostatic test conditions. Integrity of the component is assured by testing the component as a unit. Alternate Examination: Tube side inspection will be performed by isolating the heat exchanger, removing the waterbox-covers,.and pressurizing the shell side with water. Tube-leakage is indicated if there is any flow fromLthe tubes while in this configuration. This type. inspection i will be performed at least once per ; inspection interval. y 1 i i
)
l r 1 0406I 6-49 REV. O ____u-.__w-_.-.----- - + - - - - - - - - - - - -
1 RELIEF REQUEST FNP-1-M-043 FNP-1 I r~s k- RR-37 Component or Relief Area: Visual (VT-2) examination of the cooling coils for the following Class 3 pressure retaining safety-related coolers: o Four units containment coolers - Q1E12-H001A-A, H001B-A, H001C-B and H001D-B. : o Two units control room air-conditioning condensers - QSV491-K001A-A and K001B-B. Reference drawing D351104, sheet 1 of 3. j j o Two units auxiliary feedwater pump room i coolers - Q1E16-H005A-A and H005B-B. I l l o Two units component cooling water. pump , l room coolers Q1E16-H004A-A and H004B-B. I o Two units containment spray pump room j coolers Q1E16-H002A-A and H002B-B. o Two units RHR/LHSI pump room coolers
) Q1E16-H003A-A and H003B-B.
Reference drawing D351104, sheet 2 of 3. o Three units battery charging room coolers Q1E16-H006A-A, H006B-B, and H006C-AB. l o Three units charging pump room coolers Q1E16-H001A-A, H001B-AB, and H001C-B. o Two units 600-V load center coolers Q1E16-H009-A and H010-B. o Three units motor control center room coolers Q1E16-H007-A, H008A-B, and H008B-B. Reference drawing D351104, sheet 3 of 3. Requirement from which Relief is Requested: Paragraph IWD-2510 and Table IWD-2500-1 of ASME Section XI require that all Class 3 pressure retaining components be subjected to visual examination (VT-2) in conjunction with the system pressure tests of IWA-5000. 1 p~ V 0406I 6-50 REV. 0
RELIEF REQUEST FNP-1-M-043 FNP-1 b d~ RR-37 (Continued)
' Basis for' Relief: Due to the component design, the.' cooling.
coils (heat. exchanger tubes)'cannot be. visually inspected.during the conductLof-system pressure test. Alternate Examination: The normal operation of these cooling. units
' demonstrates their' structural and:leaktight.
; integrity. VisualL. inspection to verifyg leaktightness will=be: performed'while.the.
system is.'at normal operating pressure.: i Also, the coolers provided with the drain L basin will be. inspected.by observing:.for I abnormal flow-(other.-than. normal-condensation). ,
?
O l , -l i i j l 0406I 6--51 REV. 0-
il RELIEF REQUEST ENP-1-M-043 1 FNP-1 :
-'g !
(d RR-38 Component or Relief Area: Hydrostatic testing of Class 3 pressure retaining piping of the auxiliary steam system. Reference drawing D351110, sheet 2 of 2 (all class 3 portion). Requirement from ! which Relief is Requested: Paragraph IND-2510 and Table IND-2500-1 of ASME Section XI require that all Class 3 pressure retaining components be subjected to 1 visual examination (VT-2) in conjunction with I the system pressure test described in IWD-5000. l .- ; l Basis for Relief: There is no practical means of isolating the above portions of the auxiliary' steam system , and, therefore, hydrostatic testing cannot be conducted on these lines. Alternate Examination: Visual inspection to verify leaktightness f- will be performed while these lines are at ()g normal operating pressure. I
\
l l l 1 l. b d 0406I 6-52 REV. 0
..r
. . I RELIEF REQUEST:. FNP il-M-043-
-FNP-1.
RR-39 Component or Relief. Area: '! Hydrostatic-testing of Class 3 pressure. L retaining auxiliary feedwater' pump minimum; flow piping. Reference drawing D351106, sheet 1. o Line No. 2"DBC /between: valve 1 9 Q1N23V019A and; flow' orifice'FC3214A. o Line'No. 2"DCB-4 -'between valve Q1N23V019B-and flow orifice'F03214B. o 'Line'No.~2"DBC-4 and~3"DBC between- .; I 1 valve Q1N23V010 and flow ! orifice F03219'. , .
-,']
^ i l
Requirement from ' 1 l
'which Relief is .'
Requested: Paragraph.IWD-2510.and Table;IWD-2500-1 of
- q. 3 l ASME Section1XI require that'all Class 3 '
)
pressure retaining components be subjectedi-to. j a visual examination (VT-2) in conjunction i with the system pressure tests of IWD-5000. (' Basis for Relief: Performance of a hydrostatic test on the portions of the' piping system listed'above-could overpressurize'the lower' pressure,' noncode piping downstream of;these. flow. orifices. Alternate Examination: These lines will receive a visual examination-during normal operation at system operating temperature and pressure. J I 0406I 6 REV. 0'
]
1 o__u- .
t-RELIEF REQUEST- FNP-1-M-043 FNP-1 (_/ RR-40 Component or ! Relief Area: Hydrostatic testing of all Class 2 branch pipe lines from the volume. control tank (VCT) j to the first valve. Affected lines are ; listed below: o Reference drawings D351116, sheet 2 of 4, lines from VCT to valves Q1E21V260, Q1E21V209, Q1E21V356, Q1E21V152, Q1E21V201, Q1E21V196, Q1E21V262, Q1E21V261, Q1E21V193, Q1E21V376A, l Q1E21V337, and Q1E21V423. o Reference drawing D351117, sheet 1 of 1, line from VCT to valve-Q1G12V029. , 2 o Reference drawing D351119, sheet 5 of 7, , , line from VCT to valve Q1G22V249, and line i from VCT to' valve Q1G22V189. l o Reference drawing D351119, sheet 6 of 7, j line from VCT to valve Q1G22V081. ! [~h o Reference drawing D351107,. sheet 1 of 3, (.) line from VCT to valve Q1P15HV3117. j Requirement from which Relief is Requested: Category C-H, Table IWC-2500-1 of ASME Section XI, requires a hydrostatic test for all ClEss 2 pressure retaining components once every 10-year inspection interval, in accordance with IWC-5222. Basis for Relief: The Class 2 portion of piping as referenced above cannot be isolated from the tank. The ; VCT tank is designed to 75 psig and the associated piping is designed to 150 psig. Therefore, the only practical means to hydrotest the tank associated piping is based on the VCT design pressure. Alternate Examination: None. The connecting lines to the VCT tank will be hydrostatically tested to the same pressure as the tank.
/T L1 0406I 6-54 REV. 0
1 1 RELIEF REQUEST FNP-1-M-043 FNP-1 p) (,, RR-41 Component or I Relief Area: Break away drag test for hydraulic snubbers. Requirement from which Relief is Requested: Paragraph IWF-5400(b)(1) of ASME Section XI requires test verification of snubbers for maximum drag during low velocity displacements. Basis for Relief: Hydraulic snubbers are inherently inconsistent when this particular test is i considered. The load required to initiate l movement will vary considerably between identical snubbers. The break-away force required to initiate movement would be - determined by a number of variables , (viscosity of hydraulic fluid, valve spring , rates, temperature, etc.), all of which have i i no relevancy to snubber integrity. While l l break-away force for mechanical snubbers is a . relatively consistent value whose increase'is I related to snubber integrity, this is not the ! (~} (,/ case with hydraulic snubbers. The manufacturers of hydraulic snubbers have not l recognized break-away force as a test variable that is relevant to snubber integrity in that they have not addressed this parameter in their technical information. 1 Alternate Examination: None. l r\ 0406I 6-55 REV. 0
4 RELIEF REQUEST FNP-1-M-043 h FNP-1 1 f-RR-42 Component or ; Relief Area: Additional sample testing requirements for j snubbers. l Requirement-from which Relief.is, l
' Requested: Paragraph IWF-5400(c) of ASME Section XI- )
requires an additional sampling of 10 percent-of the total number of snubbers to be tested l if the initial 10-percent representative I sample has failed inservice testing. ! Additional'sampleitesting,is to continue 1 ' until all units within the sample have passed inservice testing. -
~
Basis for Relief: The additional' sampling' plan 1 required by , IWF-5400(c) is more restrictive than the .. existing expansion plan detailed in Farley I l Technical Specification 3/4.7.9c. The existing expansion-plan detailed in 3/4.7.9c meets the following statistical goals set y forth as the Bases in Farley Technical 1 fg Specifications B 3/4.7.9: To provide assurance of snubber functional reliability, a representative sample-of.the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. Selection of a representative l sample ~according to the expression 35(1+c/2)- l provides a confidence. level of approximately l 95 percent that 90 percent to 100 percent of the snubbers in the plant will be' OPERABLE p within acceptance limits, where c is the allowable number of snubbers-not meeting the acceptance criteria. Observed failures of these sample snubbers shall require functional. testing of additional units. l Alternate Examination: Snubber surveillance. testing will'be performed in accordance with the Farley Technical ~ Specifications. O V 0406I 6-56 REV. 0
l 1
. RELIEF. REQUEST FNP-1-M-043 j FNP l f3
( ,/ RR-43 Component or-Relief Area: Hydrostatic testing of; Class 2 portions of the RCS head vent lines. Reference drawing ] D351114, sheet 1 of 3, line No. 1" CCB-63 i between solenoid valves-Q1B13HV-2.to i Q1B13HV-1.and Q1B13HV-4 to Q1B13HV-3.- Requirement from which Relief is ,. Requested: Item No. C7.40, Category C-H, Table
'IWC-2500-1 of ASME Section XI, requires a
, hydrostatic test of all Class 2 pressure ) retaining components.once every 10-year l- inspection 11nterval, in accordance with l paragraph IWC-5222. r Basis for Relief: Hydrostatic testing of the RCS is performed , in mode 2 of the. reactor plant shutdown. In this mode the plant Technical Specifications require that all solenoid valves on-the RCS-head vent be maintained closed. This being the case, hydrostatic testing of the portion between these valves at this time would be a violation of the Technical Specifications.
)
Another way tx) hydrotest these lines would-be to pressurize the line after the head has been removed. This would require actuating sole n~oid valves QB13HV-2 and Q1B13HV-4 with i the aid of a temporary electric power .{ source. The work associated with actuating j these valves, installing test connections, j and performing the hydrostatic test would require excessive radiation exposure (approx. 1.5 man-rem). This level of exposure is unwarranted in view l of the minimal benefits gained-by testing i this relatively'small section of pipe which. ) l is approximately 6 inches long. i Alternate Examination:
~
Functional' operation of this system demonstrates structural integrity. Visual H inspection will be performed:while the system is at normal operating pressure to verify leaktightness. f%
._ j 0406I 6-57 REV. O i
a
RELIEF REQUEST FNP-1-M-043 ; I FNP-1 j (~' l (,)S RR-44 j i Component or i Relief. Area: Visual (VT-2) examination of heat exchanger 1 tubes of Class 3 pressure retaining safety-related heat exchangers. 1 I o Two each spent fuel pool cooling HX-Q1G31 ! H001A-B and H001B-A - reference drawings j D351103, Sheet 1 of 3, and D3511120, ' sheet 1 of 1. 1 1 Requirement from which Relief is . 1 Requested: Paragraph IWD-2510 and Table IWD-2500-1 of j ASME Section XI require that all Class 3 I pressure retaining components be. subjected to '
- )
a visual examination (VT-2) in conjunction I l with the system pressure tests of IWD-5000. ,- Basis for Relief: Due to component design and limited j accessibility, these heat exchanger tubes ) cannot be visually inspected under high pressure hydrostatic test conditions. Integrity of the component'is assured by j normal operation of the system. j f~)h
\_
Alternate Examination: Tube side leakage will be identified by the existing in-line radiation monitoring system and existing periodic sampling of the Component Cooling Water and Spent Fuel Pool Cooling Systems. If a tube leak is indicateM, the water box covers will be removed and a visual examination (VT-2) performed to identify the leaking tubes. The tubes will be plugged prior to returning the heat exchanger to service. I 0406I 6-58 REV. O
'FNP-1-M-043 I
7.0 REFERENCES
c
). '
7.1 Documents , t
- 1. Title 10, Code of Federal Regulations,;Part 50, Section 55a.
- 2. ASME Boiler and Pressure Vessel Code, Section XI, 1974 Edition with Addenda through. Summer, 1975.
- 3. ASME Boiler and Pressure. Vessel Code, Section XI, 1983 Edition with Addenda through Summer,;1983.
- 4. Reg. Guide 1.14: Reactor' Coolant. Pump-Flywheel
~
}
Integrity (Safety Guide 14,. dated
-{
10-27-71). j
- 5. Reg. Guide 1.26: Quality Group Classifications and ,
Standards for. Water-Steam and w Radioactive-Waste Containing
. Components'of. Nuclear Power Plants . I (Safety Guide'26, Dated 3-23-72).
- 6. ~ Reg. Guide 1.65, Materials.and Inspection for J Rev. 0: Reactor Vessel. Closure Studs. 1
- 7. Reg. Guide 1.82, Sumps for Emergency Core Cooling Rev. 0: and Containment: Spray Systems.
- 8. Reg. Guide 1.83, Inservice Inspection of ,
Rev. 1: Pressurized Water Reactor Steam ' Generator Tubes. 9. ! Reg. Guide 1.147, Inservice Inspection Code Case Rev. 4: Acceptability - ASME Section XI Division 1.
- 10. Reg. Guide 1.150, Ultrasonic Testing of Reactor l Rev. 1: Vessel Welds During Preservice and Inservice Examinations. 1 i
- 11. Branch Technical General Information, Required for Positions APCSB 3-1 Consideration of the Effects of a and MEB 3-1 Piping System' Break Outside '
i Containment.
- 12. FSAR-Volume 5 Listing of Codes applicable-to Section 3.2, construction of components. ,
Table 3.2-1 , l
/
6 0404I 7-1 Rev. 0-i w_-___--___-__________-_--____.__-_-__ __ __ _
b g ,A FNP-1-M-043 . j
. kq N
7.2 Letters 3 J
'i,_) ,, n r
,/
1.
letters,h,r(1 I/ ' \[ri Inservice Inspection Program Initial-Subpittul, I" dated July 8, 1977, supplemented on November 21, 1977, ; .y' March 16 and March 30, 1978, from.sF. L. Clayton, APC, to 6 John Stolz, USNRC. \ <#
] ,p 1
- 2. Nuclear Regulatory Commission Notice,of Granting P+11ef, letter dated December 7, 1979, from A. Schwencer/kSNRC, to '
Alan R. Barton, APC.
.i
- 3. Relief Requested from Vessel Cladding Examinations, letter dated April 17, 1981, Supplemented Januaty 1?, '1983, . from '
F. L. Clayton, APC, to S. A. Varge., USNRC.j.f' / r ir , 'I. <t ,
>j
- 4. Relief Requested from Pressu.re Testing Requirements, legtep /<
dated January 28, 1983, supplemented.d January 23, 1984, f F. L. Clayton, APC, to S. A. Vagga(USNRC. y';mm ,} J
- 5. Nuclear Regulatory Commission Notipe of Granting Relief for jj '/
Vessel Cladding Examinations, from S. A. Varga, UeNRC, to F. letter datedAPCAugust L. Clayton, .!- 7 2k,1983, 'y j p'
- 6.
Nuclear Regulatory Commission Notice of Granting Relief k
']p from pressure testing requirements, letter dater' February 10, 1984, from S. A. Varga, USNRCf to F. L. Clagon, APC.
(- n , .4,\ (j'
- 7. Relief Requested from Charging Pump Examinations and Steam Generator Hydrostatic Test Examin g.ons, letter dated August 16, 1984, from R. P. McDoriald) APC, to S. A. Varga, USNRC. I
.k )
- 8. NuclearRegulatorhCcemissionfoticeofGrantingRelieffor g I
i Charging Pump Casing Welds 3.nd, Integrally Welded Supports, and for Hydrostatic Test Prbssur'e*for Steam Gend ators and Class 2 Piping, letter dated January 10)' 1985, fry s[ A. Varga, USNRp, to R. P. ficDoubid 3 APC. G ' g> ) [\ 4 > /
- 9. APC response to the USNRC Generic Letter 83-15 and ^ p g ,/ ',
Regulatory Guide 1.150, Revision 1, for Units 1 and 2 by ; *; l letter from F. L. Clayton, Jr., APC, to S. A. Varga>*(i QO.C , p ,
;y j , i dated October 26, 1983. '
1,j; .
- 10. Relief Requested from Inspection Requirements of ce}:ain /
Reactor Vessel Flange Ligaments, Reactor Coolant Pump h Casing Internal Surfaces and Flange Bolts, letter dated October 14, 1985, from R. P. Mcdonald, APC, to S. A. Varga, h USNRC. p.,
- 11. Nuclear Regulatory Commission Notice of Granting Relief for Reactor Vessel Flange Ligaments, Reactor Coolant Pump Casing Internal Surfaces and Flange Solts, letter dated) p 3 Ci December 27, 1985, from L. S. Rubenstein, USNRC, to R. .
I d Mcdonald, APC, i g i vp[ 'I 0404I 7-2 Rev( 0 4 Jul 4 y ' _ _ _ - - - - __ . - _ _ _ _ _ _ _ _ - . _ _ __.____w
i FNP-1-M-043 l i
'12. Relief Requested from Inspection Requirements for Certain
,/ Pressure-Retaining Valve Body Welds and Internal pressure O- '
Boundary Surfaces, Letter dated March 11, 1986, from R. P.
'w/ ') L a c' Mcdonald, APC, to L. S. Rubenstein, USNRC. i
{
- 13. Nuclear Regulatory Commission Notice of Granting Relief for Pressure-Retaining Valve. Body Welds and. Internal Pressure Boundary Surfaces, letter dated June 19, 1986, from D. G.
Mcdonald, USNRC, to R. P. Mcdonald, APC.
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