ML20205T737
| ML20205T737 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/31/1987 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20205T702 | List: |
| References | |
| NE-5.6-ISI-NDE, NUDOCS 8704070380 | |
| Download: ML20205T737 (426) | |
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NE-5.6-ISI-NDE
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( Change - 1 TABLE OF CONTENTS Page INTRODUCTION iv PART-A Inservice Inspection-Nondestructive Examination (ISI-NDE) A-1 Program (Plan) For Piping, Components, and Integral Attachments 1.0 Applicable Code A-2 2.0 Program Description / Basis Statements A-2
- 3.0 Exemptions A-5 3.1 Class - 1 Components A-5 3.2 Class - 2 Components A-7 3.3 Class - 3 Components A-8 4.0 Relief Requests A-9 4.1 Relief Request Description Format A-9 4.2 Relief Requests A-Il 5.0 Program Support Drawings - ISI Isometrics which identify all Class 1 & 2 Components, piping welds, integral attachments and their supports A-46 l
6.0 Inservice Inspection Program (Plan) Tables (NDE) A-49
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PART-B Inservice Inspection Program (Plan) for Component Supports B-1 1.0 Applicable Code B-2 2.0 Program Description B-2 2.1 Supports to be Examined B-2 3.0 Corrective Action B-3 4.0 Relief Requests B-4 t f 4.1 Relief Request Description (Format) B-4 4.2 Relief Requests B-5
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i I 5.0 In' service Inspection Program (Plan) Tables (Component Supports) B-9 PART-C Inservice Inspection Program (Plan) for Snubbers C-1 1.0 Applicable Code C-2 h 2.0 Program Description C-2 3.0 Exceptions C-4 4.0 Reflief Requests C-4 4.1 Relief Request Description Format C-4 4.2 Relief Requests C-5 5.0 Inservice Inspection Program (Plan) Tables (Snubbers) C-10 PART-D Inservice Inspection Program (Plan) for Class 1
MC Components i 1.0 Applicable Code D-1 1
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NE-5.6-ISI-NDE R2v. O Ch:ng2 - 2
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PART-E Appendices '
Appendix-A - Sample Selection Document for 151 Class 1 Piping Welds , Category B-J.
Appendix-B - Sample Selection Document for ISI Class 2 Piping Welds , Category C-F.
Appendix-C - Class I, 2, and 3 Loop Selections for Component Supports.
Appendix-D - ET-2 Technical Specifications, Section 3/4.7.5, Snubbers - For Information Only.
Appendix-E - References Appendix-F - Adopted Code Cas,es 8
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!O Rev. O iV Change - 1 l INTRODUCTION The Inservice Inspection (ISI) Program (Plan) contained herein describes the Mondestructive Examinations to be applied to Detroit Edison's Termi 2 Power Plant (EF-2) for the first ten year (120 month) inspection interval.
IF-2 is an 1150 MW Boiling Water Reactor (BWR). This program (plan) complies'with the applicable requirements set forth in 10CFR50 and Section XI of the ASME Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components".
As stated in 10CFR50.55a(g)(4), throughout the service life of EF-2, compo-nents (including supports), which are classified as ASME Code Class 1, 2 and 3, shall meet the requirements, except design and access provisions, set forth in Section XI of editions of the ASME B & PV Code that subse-quantly become effective'and are incorporated by reference in 10CFR50.55a(b), to the extent practical within the limitations of design, geometry and materials of construction of the components.
During the initial ten year (120 month) inspection interval for which this program is applicable, inservice examinations must comply with the requirements in the latest edition and addenda of the Code incorporated in 10CFR50.55a(b) on the date 12 months prior to the date of issuance of the operating license. The date of issuance of the Operating License for Fermi-2 is July 15, 1985. The Code in effect 12 months prior to this date
(- is the 1980 Edition, through and including Winter 1981 Addenda.
It is anticipated that the first 120-month inspection interval will begin with the start of consnercial operation
- in early 1986 and be completed in 1996.
This document is a sunusary of the Fermi 2 Inservice Inspection Program (Plan) and is being submitted to the Nuclear Regulatory Consnission for approval in accordance with the requirements of 10CFR50.55a(g)(4)(i).
This ISI - NDE Program (Plan) is subject to change. Changes will be effected via relief requests or document revisions. The EF-2 ISI - NDE Program (Plan) will be updated every ten years, plus or minus one year, per 10CFR50.55a or more frequently to reflect optional owner upgrades or regulatory consnitments.
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s This ISI - NDE Program (Plan) is intended to be a reference document and includesallthosecomponentsandtheirassociatedsupportssubjectto inspection and testing. The items in each category will be scheduled for 5
inspection in accordance with the rules of ASME Section II and as augmented by specific commitments. Future revisions of this program (plan) shall be issued for each period to show the specific examinations to be performed during the specific period as well as all ensuinations completed during previous periods.
This document does not include the Inservice Testing (IST) Pump and Valve Program (IWP and IW) commitments.
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l PART - A INSERVICE INSFECTION-NONDESTRUCTIVE EXAMINATION (ISI-NDE) FR0 CRAM (PLAN)
FOR FIFING, COMPONENTS, AND INTECRAL ATTACHMENTS
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, Change - 1 N Page A-2 of 52 1.0 Applicable Code i The Inservice Inspection Program (Plan) for Nondestructive Examination (NDE) of Class 1, 2 and 3 componento is implemented in accordance with the requirements and intent of Subsections IWA, IW, IWC, IW, and IWE Section XI, Division 1 of the ASME Boller and Pressure vessel Code, 1980 Edition through the Winter 1981 Addenda. All references in this document (Part A) to Section XI, - the Code, Categories, Item Numbers, etc. - refer to the 1980 Edition through the Winter 1981 Addenda unless otherwise noted.
2.0 Program Description The NDE Program (Plan) developed hereiu will utilise Inspection Prog' ram B, (IWA-2420), Tables IkB-2412-1 and IWC-2412-1 for the first 3
120 month inspection interval. Per 10CTR50.55a(s)(5)(fii), where the requirements of the governing Code Edition or Addenda are determined to be impractical, within the limitations of design, geometry and materials of construction of the components, specific relief requests have been written. These are referenced in the appilcable NDE Program Tables and included in section 4.0 of this part. If during the course of implementation the need for additional relief is identified, it will be requested at a later date.
In accordance with 10CTR50.55a (b)(2)(iv), the extent of esamination (the number of welds required to be examined) for Code Class-2 pipe welds included in the Residual Heat Removal System (RHR) Emergency Core Cooling Systems (ECC), and Containment Heat Removal Systems (CHR) was determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, and paragraph IWC-2411 in the 1974 Edition, including Addenda through the Summer 1975, of Section XI of the ASME B of PV Code. For all other class 2 systems either the 1974 Edition, including Addenda through the Summer 1975, or the 1980 Edition, including Addenda through the Winter 1981, of ASME Section XI may be used. For consistency, the 1974 Edition, including Addenda through the Summer 1975 was used. This includes the Head Spray and Standby 1,iquid Control Systems added to the Class-2 Inservice Inspection Program by Detroit Edison 1.etter EF2-$3873, transmitted to the NRC on June 24, 1981.
The selection of the individual welds to be enemined on each Class 2 system is based on the inspection philosophy identified in the 1980 Edition, Winter 1981 Addenda of ASME Section XI. The selection philosophy contained in the 1975 Summer Addenda is based on a random selection of welds and results in examining a particular veld only once in the plants 40-year operational lif e. No trending of data is possible under the 1975 Sussner rules. The 1981 Winter Addenda identifies a selection of philosophy that concentrates the O
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examinations on those welds that historically have a greater probability of failure; namely, high-stress welds, welds at terminal ends, and dissimilar metal welds. In addition, the 1981 Winter Addenda requires examinations of the same welds in each 10-year interval so that meaningful data trending can be accomplished. There is general agreement in the industry that the 1981 Winter Addenda philosophy is superior to the random selection approach identified in the 1975 summer Addenda.
The criteria used for the selection of specific welds to be examined for the inservice inspection program are based on the following:
2.1 All high stress welds defined as loading stresses greater than 0.8(1.2Sh
- S a) as per the 1981 Winter Addenda.
2.2 All moderately stressed welds defined as loading stresses greater than 0.7(1.2Sh
- 3a ) and less than or equal to 0.8(1.253 + S.). Inclusion of these moderately stressed welds in the Fermi 2, Class 2, Inservice Inspection Program, is an added conservatism that exceeds the requirements of the ASME Section XI, 1980 Edition, Winter 1981 Addenda.
2.3 All dissimilar metal welds. (There are none)
' 2.4 One terminal end of each type of terminal end within a system. (Note: This is a modified version of the ASME Section XI,1980 Edition, Winter 1981 Addenda, Table IWC-2500-1. Category C-F, Footnote (1)(b).) Edison has taken this approach to prevent skewing the weld examination sample to this particular type of weld. For example, the core spray system has four pumps, each with a terminal end at the pump suction and discharge. To examine all eight terminal ends would be redundant. Therefore, to enable a more represent-stive sample to be taken, only one pump suction terminal end weld and one pump discharge terminal end weld would be selected for examination.
2.5 Additional random selections such that the total number of welds examined meets the number required by paragraph IWC-2411 of ASME Section X1,1974 Edition, Summer 1975 Addenda.
The Class-2 examination philosophy described above has previously been presented to the NRC in the EF-2 FSAR and subsequently accepted by the NRC in the SER.
For further details on the Class 1 and Class 2 weld selection process, refer to Part-E of this document, Appendix-A & Appendix-B respectively.
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Section 5.0 contains copies of Feral 2's Inservice Inspection ,
Isometric Drawings which have been developed for all vessels, piping, f pumps and valves which require volumetric and/or surface esamination ,
by this program. l The system inservice inspection classifications, developed specifi-chily to define the extent to which ASME Section II requirements will be applied, differ somewhat from the ASME Section III design classifi-cations. Primarily, these dif ferences occur because systems, or portions of systems, have been optionally upgraded in design. In addition, ISI classifications are limited to systems important to
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safety, which contain water, steam, or radioactive materials.
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l NE-5.6-ISI-NDE J. Rev. O Change - 1 Page A-5 of 52 3.0 Exemptions Certain components (or parts of components) are esempt from the examination requirements of ASME Section XI, Table IWB-2500-1, per provisions contained in the Code. This section lists those " Code Allowed Exemptions" as applicable to the Fermi 2 Inservice Inspection Program.
3.1 Class-1 Components exempt from volumetric and surface esamination I requirements of IWB-2500 of the Codet j Exemption EX-Al-1 ASME Section XI Code Paragraph IWB-1220(a)
" Components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary and that are of such site and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power."
Justification:
The maximum size line break that can be made up by the reactor coolant makeup system has been calculated to be 1.44 inches inside diameter for liquid c.irrying lines and 2.88 inches inside
' diameter for steam carrying lines.
Exemption EX-Al-2 ASME Section XI Code Paragraph IWB-1220(b)(1) & (2)
" Piping of 1 inch nominal pipe size and smaller and components and their connections in piping of 1 inch nominal pipe size and smaller".
Exemption EX-Al-3 ASME Section XI Code Paragraph: IWB-1220(c) j
" Reactor Vessel head connections and associated piping, 2 inches nominal pipe slee and smaller,made inaccessible by control rod drive penetrations".
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- i. Change - 1 Page A-6 of 52 Exemption EX-Al-4 ASME Section XI code Table: 145-2500-1, Emanisation Category B-H, Footnote No. 1.
Integral welded attachments with a base material design thickness 1ess than 5/8 inch and weld butidup on nossles that serve as supports.
Exemption EX-Al-5 ASME Section XI Code Table: I W 2500-1, Examination Category 3-K-1 Footnote No. 3.
Integral welded attachments with a base material design thickness less than 5/8 inch.
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D Change - 1 Page A-7 of 52 3.2 class-2 Components exempt from the inservice examination requirements of IWC-2500 of the Coder Exemption EX-A2-1
! ASME Section XI Code Paranraph: IWC-1220(a)
" Components of systems or portions of systems that during normal plant operating conditions are not required to operate to perform a system function but resala flooded under static conditions at a
- pressure of at least 80% of the pressure that the component or system will be subjected to when required to operate.
Exemption EX-A2-2 ASME Section XI Code Parsaraph: IWC-1220(b)
" Components of systems or portions of systems, other than residual heat removal systems and emergency core cooling systems, that are not required to operate above a pressure of 275 pois or 1 above a temperature of 200 degrees F.
r Exemption EX-A2-3 ASME Section XI Code Paranraph: IWC-1220(c)
" Component connections (including nogales in vessels and pumps),
piping and associated valves, and vessels and their attachments d that are 4 inches nominal pipe size and smaller".
Exception EX-A2-4 i ASME Section XI Code Paragraph: IWC-$222(d) 1 "For open ended portions of discharge lines beyond the last shutof f valve in nonclosed systems, demonstration of an open flow path test shall be performed in lieu of the system hydrostatic 4
test".
Exemption EX-A2-5 1
ASME Section XI Code Table: IWC-2500-1, Examination Category C-C, Footnote No. 1.
Integral welded attachments with a base material design thickness less than 3/4 inch.
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Change - 1 Page A-8 of 32 3.3 Class-3 Components exempt from the inservice inspection requirements of IWD-2600 of the Code:
Exemption EX-A3-1 ASME Section II Code paragraph Ilm-1220.1
" Integral attachments to supports and restraints to components that are 4 inches nominal pipe sine and eneller within the system boundaries of examination categories D-A, D-5, and D-C of Table IWD-2500-1 shall be exempt f rom the visual examination VT-3".
Exemption EX-A3-2 ASME Section XI Code Paragraph: 1WD-1220.2(a) & (b)
- " Integral attachments of supports and restraints to componente exceeding 4 inches nominal pipe size may be exempted from the visual examination VT-3 of Table IWD-2500-1 provided:
(a) The components are located in systems (or portions of system) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling".
(b) The components operate at a pressure of 275 pois or less and at a tenperature of 200 degrees F or less".
Exemption EX-A3-3 ASME Section XI Code Paragraph: IWD-5223(d)
"For open ended portions of discharge lines beyond the last 4 shutof f valve in nonclosed system (e.g., service water systems),
it confirmation of adequate flow during system operation shall be acceptable in lieu of system hydrostatic test".
Exemption EX-A3-4 3
ASME Section XI Code Paragraph IWD-5223(e)
I j "Open ended vent and drain lines from cr.aponente estending beyond the last shutof f valve and open ended safety of relief valve '
discharge lines shall be exempt from hydrostatic test".
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[ Change - 1 A Page A-9 of 52 4.0 Relief Requests i Relief Requests are included where specific requiremente of AgNE
! Section XI are determined to be impractical. Each Relief Request is written in accordance with the format guidelines provided in Section
, 4.1. Individual Relief Requesta are included in Section 4.2. As noted in the INTRODUCTION, Section 4.2 is subject to change throughout the inspection interval. If enasination requirements in this program i plan are determined to be impractical during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10 CTR 50.55a (g) (5) (iii).
4.1 Relief Request Torsat Each Relief Request will include the following sections:
4.1.1 COMPONENT DESCRIPTION: The component description will includes o A general description of the component (s) addressed by the Relief Request, o The applicable Plant Identification System (PIS) number (s) which uniquely identify the plant system and spe:ific component (s) within the system, and i
o A quantity of components if the Relief Request covers mere than ten (10) corponents.
4.1.2 ASME CODE C1. ASS: The 151 classification, Class 1, 2, 3, Et, E2, or E3, as identified on the IS! Classification Boundary Drawings will be listed. i 4.1.3 ASME SECTION XI RECAIREMENT: The impractical ASNE Section XI reqdrement(s) will be listed. To the extent possible, subparagraphs, individual footnotes, or specific Item Numbers will be cited.
1 4.1.0 BASIS FOR RELIEF: Information to support Detroit Edison's determination that the Code requirement is impractical
. will be provided. The following data will be provided, if applicable o A physical sketch if the component (s) are not accessible for examination.
o Detailed technical information (an engineering justification) supporting proposed alternate scope of enamanation, examination method, or acceptance standard.
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\ Change - 1 Page A-10 of 52 o A description of the proposed alternative easeinstion's impact on plant safety and justification of any change in the overall level of plant safety.
o A justification of any change in the overall level of plant safety if it is not possible to perforu alternative esamination(s).
4.1.5 ALTERNATE EXAMINATIONt Any alternate esamination(s) that are proposed will be identified. Both alternate examination (s) that are performed in lieu of the Section XI enemination requirement (s) and alternate enasination(s) that supplement partially completed Section XI examination requirement (s) will be identified. The description of the alternate examination (s) will include a statement describing the entent and frequency of esselnation, the
. acceptance standard, and whether deferral of inspection to the end of the interval is requested.
4.1.6 APPLICABLE TIME PERIOD: A statement identifying the time period during the inspection' interval for which relief is requested will be included.
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The following Relief Request (s) are included in this section:
MLIEF MQUEST NUMBER GENERAL DESCRIPTION RR-Al RpV ehe11 and head welds are only partially accessible to mechanteed onesination equipment.
RR-A2 RPV bottom head welde in the center of the head are inaccessible due to CRD housing interferences.
RR-A3 A Clase 1 moderate strees circumferential piping weld (pipe to flued head weld SW-PS-2-X7D-WI) in the guard pipe is inaccessible.
RR-A4 Reactor recirculation pump internal visual eneminatione solely for the purpose of entietying the requirements of Enseinstion Category 5-M-2 are impractical. If the pusy is disassembled for maintenance, the enemination will be performed.
AR-A$ Class 1 valve internal visual eneminatione solely for the purpose of estisfying the requirements of Emasination Category 5-L-2 are impractical. If a Class 1 valve is disassembled for saintenance, the enemination will be performed.
RR-A6 RPV feedwater nogales N4A and N4D are partially inaccessible etnce instrument nossles M11A and N!!B are too close to feedwater noestes N4A and N4D.
RR-A7 Control rod drive and instrumentation nossle partial penetration welds are inaccessible to direct visual esamination.
PR-A8 Main steam piping luge near the inboard sein etese isolation valve are impractical to eassine.
RR-A9 Integrally wided attachmente (piping luge) Class 1.
RR-A10 Integrally wided attachmente (piping luge) Primary Containment Penetrations.
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i RR-All Reactor recirculation pump integrally welded attachments are impractical to esamine.
i RR-A12 Integrally welded attachments (piping lugs) Class 2.
RR-A13 The design of component supports E11-3146-C30 and
- E11-3151-C20 makes the integretly welded attacheents associated with these guides inaccessible. ,
The weld on the bottom side of the RNR heat eschenger 4
RR-A14 support ring is surrounded by structural steel and is inaccessible to examination.
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Q Page A-13 of $2 RELIEF REQUEST - RR-Al i i
COMPONENT DESCRIPTION:
Reactor Pressure vessel (RPV), See Table 1 (attached) l ASME CODE CLASS l
4 Class ! Vessel ASME CODE SECTION X1 REQt'IRIMENTS: Subsection IWB. Table IWB- 2500-1 Examination Category B-A, Ites No's. 51.10 and 51.20, require voluestric examination of the regions described in figures 1WB-2500-1 through 3 f or i
- pressure retaining welds in the reactor pressure vessel each inspection interval.
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- BAS!$ TOR Stt1EF
- Due to mechanized esamination equipment limitations and nosale interferences, a 100% volumetric examination is not possible for
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certain shell and lower head welds. Coverage of the effected enemination areas will be reduced depending on the physical liettations of the equipment and interferences encountered on a given examination.
l The Fermi 2 RPV Preservice (PS1) nondestructive amasinations were conducted in accordance with ASME Code section XI,1971 Edition with Addenda through Winter 1971, and Section 111, 1968 Edition "with Addenda" through Summer i 1969. Subsequent to the BPV PSI, a pole track system was designed to allow remote ultrasonic (sechanised) en..ninstion of the RPV Walde. The design allowed for manimum weld coverage possible with the equipment available at i that time. The code in effect at that time,Section XI 1974 Edition required that 10% of the length of each longitudinal weld and 5% of the ,
length of each circumferential weld be esamined, the designed pole track ,
system escoeded the esamination requirements in effect at that time.
O Performance of the limited ultrasonic esaminations and the leakage teste j will provide the maximurs soeurance practicable that the vessel is structurally sound for plant operation.
< ALTERNATE EXAMINATION! No alternative enseinstions are proposed at this time. However, each listed weld will be enasined to the entent indicated j .
with possible Mditional coverage when equipment design allows. In i addition to these esaminations, leakage testing will be conducted at each
- refueling outage in accordance with Section XI, Enemination Category B P Ites No. 81$.10 and once every ten years in accordance with section X1 Enamination Category 5-P, item No.115.11.
APPLICAlt! TIME PERIOD: pelief le requested for the first 120 month !
l-interval.
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RR-Al Cont'd EWRICO FERN! 2 Weld Coverage Using Mechanised Ultrasonic Esamination Source - Southwest Research Institute i
! Weld Identification ! Coverste
- Circumferential Welds:
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- 6-306 '
100 9-307 26 j 1-313 35 4-3085 25 4-308A 22
- 13-308a* ,
17 I Longitudiust Welds:
2-307A 14 ,
2-3078 62 i 2-307C 73 f
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IS-305A 100 '
15-3088 100 15-308C 100 .
'. IS-308D 100 i
! 2-308A 100 j 2-308B 100 i 2 308C 100 .
I I l-308A 72 l-3088 72
]4 1-308C 72 i, 1-308D 72 Meridional Welds:
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I l-306A 76 i 1-3068 76 i !=306C 76 I' l-306D 76 l-306E 76 -
! l-306T 76
!=3060 76 l l-306H 76 l
! l-306J 76 ;
1 1-306K 76
. etaselnation covera 8e of less than 100% due to nosele interference and j examination device mechanical limitations.
- A supplemental Manual ultrasonle esamination will be conducted for weld 13-308, shell to flan 8e. This esamination will be conducted from the flan 8e seat surface and will include 100% of the weld.
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i, ut-5.6-151-NDE O Rev. O I (d Change - 1 Page A-16 of 52 1
RELIEF REQUEST RR-A2 i
l COMPONENT DESCRIPTION!
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l i Reactor Pressure Vessel (RPV) - Botton Read Walde 1
i Weld Identification M I 5-306 circumferential 1 2-306 A thru C Meridional
- ASME CODE CLASS:
1 Clase ! - Vessel ASME SECTION X1 REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Esselna-a tion Category B-A, Item No. 51.20 requires Volueetric enemination of the i regione described in figure IWB-2500-3. Examination of these pressure retaining welds in the reactor pressure vessel are required each inspection interval.
' balls FOR ptLIEF Control Rod Drive (CRD) housings in the lower head prevent access to vessel welde in this area. See figure 1.
i Due to the cluster of CRD drive housings in the lower head, access to the 7 l* seridional we1Je and I circumferential weld depicted in figure 1 is not possible. Voluestric eneminatione can not be conducted. ;
l Performance of the leakage tests will provide assurance to the entent practicable, that the vessel is structurally sound for plant operation.
l ALTERNATE EXAMINATION: No alternative eneminatione are proposed at thie However, leakage testing will be conducted each refueling outage in time.
jj ', accordance with ASME 5ection X1, Table IWh-2500-1 Examination Category B-P.
' Ites No. 315.10 and once every ten years in accordance with Section X1, I Esasination Category 5 P, Ites No. 815.11.
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} APPLICABLE TIME PERIOD: Relief is requested for the first 120 month i interval.
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( Change - 1 s Page A-17 of $2 RR-A2 Cont'd O*
2-306A
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, NE-5.6-181-NDE g
Rev. 0 l
( Change - 1 i Page A-10 of 52 RELItr REQUEST Ra-A3 COMPONENT DESCRIPTION:
Circumferential Piping Wold i BW-PS-2-X7D-W1 Fire-to-Flued Need ASME CODE CLASS Class 1, piping ASME SECTION XI REQUIREMENTSt Subsection IWB Table IWB-2500-1, saamination i Category S-J, Ites No. 89.!!, requires surface and valuestric eassinations of Welds where the stress level exceeds 2.4 5,. In addition to this requirement The Detroit Edison Company has supplemented this requirement
. to include those Welds which exceed 2.1 S,. Welds which meet this stress level, between 2.15, and 2.4 5,, are designated moderate stress Welds.
BASIS FOR REL1tFI Due to the design of the primary containment penetration assemblies, the circumferential weld at the process pipe-to-flued head (See figure 1) is not accessible. The clearance available between the process pipe and guard pipe is not large enough to allow emaninetton equipment access to the Weld area. In addition the open end side of the penetration assembly is obstructed by construction centering lugs, as shown in the figure, and the installed ineutetton. -
The esamination of the subject weld is a self imposed requirement beyond the requirements of the code. Due to the design limitations which prevent reasonable access to the weld area, a significant design and development ,
program would be required to fabricate the required onssination equipment. (
A program of this nature is not feasible. Only one selected Weld is L affected by this situation, locause of these factors and the fact that the !
code does not require the enemination of this weld, relief is requestwd i f rom the commitment made by Detroit Edison to esamine this moderate stress weld. !
performance of the leakage tests will provide assurance that the piping is l structurally sound for plant operation. j A1.TERNATT EXAMINATION No alternative eneminations are proposed at this time. Mowever, leakage testing will be conducted each refueling outage in accordance with Section X1, tassination Category B F, Ites No. 31$.$0 and once every ten years in accordance with Section X1 Esselnation Category 8 7, Ites No. 51$.11.
APPLICA81.t TIME PERIOD: Relief is requested for the first 120 month interval.
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- NE-5.6-ISI-NDE 3 Rev. O Change - 1 Page A-20 of 52 RELIEF REQUEST RR-A4 I COMPONENT DESCRIPTION
Recirkulation Pumps (33101C001A & 33101C0018)
Pump Casings ASME CODE CLASS i
Class 1, Pumps 1
ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Examina-tion Category B-L-2, Item No. B12.20 requires that the internal surfaces of one recirculation pump casing be visually examined (VT-3) each inspection interval. Specifically, the area of examination includes all pump casing internal pressure boundary surfaces.
BASIS FOR RELIEF: Access to the recirculation pump casing internal surfaces can only be accomplished when the pump has been disassembled. At this time, there are no other requirements to disassemble the pump on a scheduled basis. Disassembly of a recirculation pump for performance of a
! VT-3 visual examination would require significant labor and radiation l
exposure. It is expected that approximately 1000 man-hours and 50 man-rem t
esposure would be required to disassemble, inspect, and reassemble one pump. Performing this visual examination under adverse conditions such as high dose rate (30-40 R/hr) and poor as-cast surf ace condition, realisti-cally provides little additional information as to pump casing integrity.
The recirculation pumps at Termi 2 are Byron Jackson, type DVSS. The pump casing is primarily a single piece design of cast stainless steel (ASTM A-351, grade CF8H) and is widely used in the nuclear industry. Operating histories of recirculation pumps do not warrant concern for easing failure or inservice growth of manufacturing flaws. The presence of some delta
! ferrite (typically 5% or more) imparts substantially increased resistance l to integranular stress corrosion cracking. The delta ferrite also results in improved pitting corrosion resistance in chloride containing
) environments.
Detroit Edison Company feels that adequate safety margins are inherent in the basic pump design and that the health and safety of the public will not be adversely affected by performing the visual emanination of the pump internal pressure boundary surf aces only when the pumps are required to be disassembled for saintenance. In addition both pumps will be VT-2 examined every refueling outage during leakage tests and once in the interval during hydrostatic testing.
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NE-5.6-ISI-NDE
[ Rev. 0
- k. Change - 1 Page A-21 of 52 RR-A4 Cont'd ALTERNATE EXAMINATION: No alternative examinations are proposed at this time. In accordance with Section XI, Examination Category B-F. Ites No's.
B15.60 and B15.61, a system leakage test will be conducted each refueling outage and a system hydrostatic test conducted once during the interval.
Also, whenever these pumps are disassembled for maintenance or for any other reason which would provide access to the internal surfaces, a visual examination of the internal surfaces shall be performed.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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J NE-5.6-ISI-NDE
}q Rev. O s (,,/ Change - 1 Page A-22 of 52 REl.IEF REQUEST RR-A5 COMPONENT DESCRIPTION:
The Ferai-2 unit Class-1 systems contain 63 valves which are greater than l
four (4) inches nominal pipe size. These valves very in size, design and manufacturer but all are manufactured from either cast or forged stainless steel or carbon steel. None of the valve bodies are welded. Of these 63 valves, 23 are subject to visual examination (VT-3) per Table IWB-2500-1, Category B-M-2 Item B12.50. The 63 valves to which this Relief Request applies are listed below:
521 F022A (V17-2003) Ell F008 (V8-2092) C33 F001 (V8-2252)
B21 F0225 (V17-2001) Ell F009 (V8-2091)~ C33 F004 (V8-2253)
B21 F022C (V17-2002) Ell F015A (V8-2161) C33 F100 (V8-2250)
B21 F022D (V17-2004) Ell F015B (V8-2162) C33 F102 (V8-2251)
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B21 F028A (V17-2007) Ell F019 (V8-2173) C33 F106 (V8-2249)
I B21 F028B (V17-2005) Ell F022 (V8-2172)
B21 F028C (V17-2006) Ell F023 (V8-2171) N21 F010A (V8-2008)
B21 F028D (V17-2008) Ell F050A (V8-2163) N21 F0108 (v12-2007)
Ell F050B (V8-2164) N21 F0ll A (V12-2006)
B21 F013A (V22-2071) Ell F060A (V8-2165) N21 F0llB (V12-2005)
B21 F013B (V22-2068) Ell F060B (V8-2166) N21 F032A (V12-2004)
B21 F013C (V22-2060) Ell F067 (V8-2090) N21 F032B (V12-2003)
B21 F013D (V22-2054) Ell F608 (V8-3407) N21 F076A (V12-2002)
B21 F013E (V22-2056) N21 F076B (V12-2001)
B21 F013F (V22-2050) E21 F005A (V8-2021)
B21 F013G (V22-2066) E21 F005B (v8-2022) i B21 F013H (V22-2058) E21 F006A (V8-2023)
B21 F013J (V22-2064) E21 F006B (V8-2024)
B21 F013K (V22-2062) E21 F007A (V8-2025)
B21 F013L (V22-2052) E21 F007B (V8-2026)
B21 F013M (V22-2046)
- B21 F0135 (V22-2047) E41 F002 (V17-2020)
B21 F013P (V22-2070) E41 F003 (V17-2021)
B21 F013R (V22-2048) E41 F006 (V8-2194)
B31 F031 A (V8-2003) E51 F013 (V8-2228) 531 F031B (V8-2004)
B31 F023A (V8-2001)
B31 F023B (V8-2002) 1 0
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I p NE-5.6-ISI-NDE Rev. 0 l Change - 1 Page A-23 of 52 RR-A5 Cont'd ASME CODE CLASS Class 1, Valves ASME SECTION TI REQUIREMENTS: Subsection IWB, Table IWB-2500-1 Category B-M-2, Item B12.50, requires that the internal surfaces of valve bodies exceeding 4 inches nominal pipe size be visually examined (VT-3). Per Table IWB-2500-1 Examination Category B-M-2, Note 3, one valve within each group of valves that are of the same constructional design will be examined each inspection interval.
BASIS FOR RELIEF: Access to valve internal surfaces can only be accomplished when the valve is disassembled. Disessembly of valves for reasons other than required maintenance will require additional labor and associated radiation exposure.
Disassembly of valves for visual examination with no other requirement for maintenance, will increase exposure to plant personnel. In some cases, radiation fields as high as 10 R/hr could be experienced. In addition, further labor and radiation exposure would occur for those valves which can
~
not be isolated from reactor fluid. This is the case for approximately 20%
of the subject valves (12 total) and would require unloading of the RPV i
core and vessel draining.
Performing these visual examinations on poor as-cast surfaces provides little additional information as to valve body integrity.
The valves at Termi 2 are cast stainless steel and cast or forged carbon steel. Historically these materials have excellent service records and there is little reason to expect service related flaws in these valve
. bodies.
ALTERNATE EXAMINATION: No alternate examinations are proposed at this time.
In accordance with Section XI, Category B-P, Items B15.60 and B15.61, a system leakage test will be conducted at each refueling outage and a system hydrostatic test will be conducted once during the interval. Also, when-ever these valves are disassembled for maintenance, or for any other reason which would provide access to the internal surfaces, a visual examination of the internal surfaces shall be performed.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
NE-5.6-ISI-NDE
- [~' Rev. 0 Change - 1
[' Page A-24 of 52 RELIEF REQUEST RR-A6 COMPONENT DESCRIPTION:
Reactor Pressure Vessel (RPV) 4-316A, Feedwater nossle at 30' 4-316D, Feedwater nozzle at 210' ASME CODE CLASS Class 1 ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Category B-D, Item B3.90, requires volumetric examination of the nozzle-to-vessel welds. The required examination volume is shown in figure IWB-2500-7(b).
BASIS FOR RELIEF: As shown in the attached figure 1, two N4 (feedwater) nozzle penetrations have adjacent N11 (Instrumentation) nozzle penetrations which will interfere with the mechanized ultrasonic scanning of the required examination volume. The limitations will prevent examination of 12.8* of the nozzle-to-vessel weld.
The relative location of the N11 instrumentation nozzles prevent the positioning of the mechanized ultrasonic search unit between the azimuth locations shown in figure 1. Because of the equipment's design, only the area outside of the limited area can be scanned.
Performance of the limited ultrasonic examinations and the leakage tests will provide the maximum assurance practicable that the vessel is structurally sound for plant operation.
ALTERNATE EKAMINATION: No alternative examinations are proposed at this time. However, each listed weld will be examined to the maximum extent possible. In addition, leakage testing will be conducted each refueling outage in accordance with Section XI, Examination Category B-P, Item B15.10 and once every ten years in accordance with Section XI Examination Category B-P, Item No. 515.11.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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l NE-5.6-I SI-NDE Rev. O ff Change - 1
\; Page A-25 of 52 RR-A6 Cont'd
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FEEDWATER NO22LES N4A & D FEEDWATER N0ZZLE EXAMINATION LIMITATIONS 1
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NE-5.6-ISI-NDE 7
Rev. 0 J
) Change - 1 Page A-26 of 52 RELIEF REQUEST RR-A7 COMPONENT DESCRIPTION:
Reactor Pressure Vessel (Control Rod Drives)
All codtrol rod drive and instrumentation nozzles. (240 nossles total)
ASME CODE CLASS Class 1 ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Category B-E, Items 4.12 and 4.13, requires visual (VT-2) examination of the control rod drive nozzles and instrumentation nozzle external surfaces. 25% of the nozzles are to be examined during each inspection interval.
BASIS FOR RELIEF: Due to the location of these components, these partial penetration welds are not accessible for direct visual examination. The welds, located in the tightly clustered instrumentation and control rod drive housings inside the vessel, can not be directly accessed inside or outside the vessel.
The physical location of these nozzles prevent access for direct visual examination.
Visual (VT-2) examination for evidence of leakage will insure the integrity of these components.
ALTERNATE EXAMINATION: A visual (VT-2) examination will be conducted from below the housing location under the vessel lower head during the system leakage test and the hydrostatic test performed once every ten years.
i APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
NE-5.6-ISI-NDE f/~ Rev. O
{y Change - 1 Page A-27 of 52 1
l RELIEF REQUEST RR-A8 l COMPONENT DESCRIPTION:
Integrally Welded Attachments (Main Steam Piping Lugs)
Lug / Weld Ident FW- PS-2-A4-GA l
-GA2
-GA3
-GA4 FW-PS-2-B4-CB I
-GB2
-GB3
-GB4 ,
FW-PS-2-C4-GCl
-CC2
-GC3
-GC4 FW-PS-2-D4-GDI w -GD2
-GD3
-GDL ASME CODE CLASS Class 1
- , ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB 2500-1, Category e B-K-1, item B10.10, requires a surf ace examination of integrally welded attachments for piping. Attachments whose base material design thickness is 5/8 in, and greater will be examined.
BASIS FOR RELIEF: The guide lugs located on main steam piping immediately preceding the inboard isolation valves are surrounded by support components.
These support components require considerable labor to remove in order to allow examination access to these lugs.
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a NE-5.6-ISI-NDE
('N
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Rev. 0
' Change - 1 Page A-28 of 52 RR-AB Cont'd Access to the examination areas require that significant labor be expended in the removal of the associated support components. The estimated time for removal of one support is 112 man-hours.
The significant labor required along with the accompanying radiation exposure can not be justified. No structural changes to the welds is anticipated due to inservice operation.
A1. TERNATE EXAMINATION: No alternative test methods are proposed at this time. However, should the support component be removed for any reason, the required examination will be conducted on the exposed lugs.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month
. interval.
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1 NE-5.6-ISI-NDE p Rev. 0 4 Change - 1 Page A-29 of 52 RELIEF REQUEST RR-A9 COMPONENT DESCRIPTION Integrally Welded Attachments (Piping Lugs)
FW- RS-2-A2-At t SW- RD-2-B2-W16
-AL2 -W17
-AL3 -W18
-AL4 -W19 F W- RD-2-A2-W16 SW- RD-2-B2-W8
-W17 -W9
-W18 -W12
-W19 -W13 F W- RD-2-A2-W8
-W9
-W12
-W13 ASME CODE CLASS Class 1 ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Category B-K-1, Item B10.10, requires a surface examination of integrally welded attachments for piping. Attachments whose base material design thickness is 5/8 in, and greater will be examined.
BASIS FOR RELIEF: Various abandoned lugs exist on piping components within the class I system boundaries. There are no support components associated with these lugs and the lugs are not required for any function.
. Exa .ination of these lugs will increase radiation exposure without benefit to plant safety.
- Access to these examination areas will increase radiation exposure to plant personnel. The attachment welds are not full penetration welds and their integrity is not required as they serve no functional purpose. The lugs
, are not loaded and no structural change in the welds are expected due to inservice operation. In addition ASME Code Case N-343, paragraph 2.0,
" Examination Category B-K-1, sub item (b), allows this exemption.
ALTERNATE EKAMINATION: None proposed.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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NE-5.6-ISI-NDE n Rev. 0
[]
(
Change - 1 Page A-30 of 52 RELIEF REQUEST RR-A10 COMPONENT DESCRIPTION:
Integrally Welded Attachments (Piping Lugs) Primary Containment Penetrations.
SW-E51-2192-X10-W2A SW-E21-3053-116A-W2A SW-E51-2192-X10-W2B SW-E21-3053-116A-W2B SW-E51-2192-X10-W2C SW-E21-3053-X16A-W2C SW-E41-2297-X11-W2A SW-Ell-3519-117-W2A SW-E41-2297-X11-W2B SW-E11-3519-X17-W2B SW-E41-2297-X11-W2C SW-Ell-3519-X17-W2C SW-El l-2298-X13 B-W2 A SW-X7A-W2A SW-E11-2298-X13B-W2B SW-X7A-W2B SW- Ell-2298-X13 B-W2 C SW-X7A-W2C SW-Ell-2299-X12-W2A SW-X7B-W2A SW-Ell-2299-X12-W2B SW-X7B-W2B SW-Ell-2299-X12-W2C SW-X7C-W2C SW-Ell-2327-X13A-W2A SW-X7C-W2A V SW-Ell-2327-X13A-W2B SW-X7C-W2B SW-Ell-2327-X13A-W2C SW-X7C-W2C SW-E21-3052-X16B-W2A SW-X7 D-W2 A SW-E21-3052-X16B-W2B SW-X7D-W2B SW-E21-3052-X16B-W2C SW-X7D-W2C SW-N21-2336-X9A-W2A SW-N21-2336-X9A-W2B SW-521-23 36-X 9 A-W2 C SW-N21-2336-X9B-W2A SW-N21-2336-X9B-W2B SW-N21-2336-X9B-W2C ASME CODE CLASS:
Class 1 ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Category B-K-1, Item B10.10, requires a surf ace examination of integrally welded I
attachments for piping. Attachments whose base material design thickness is 5/8 in. and greater will be examined.
l
NE-5.6-IsI-NDE g ,, Rev. O Change - 1 Page A-31 of 52 RR-A10 Cont'd. J l
BASIS FOR RELIEF: Due to the design of the Primary Containment Penetration Assemblies, the centering lugs installed in the penetrations are not accessible for examination. The clearance between the guard pipe and process pipe is not large enough to allow for inspection of these areas.
The lugs are installed inside the penetrations and examinations can not be performed. The attachment welds are not full penetration velds and their integrity is not required as they serve no functional purpose. The lugs are not loaded, and no structural change in the welds are expected due to inservice operation. In addition, ASME Code Case N-343, paragraph 2.0,
" Examination Category B-K-1, sub ites (B), allows this exemption.
ALTERNATE EXAMINATION: None proposed.
APPLICABLE TIME P'ERIOD: Relief is requested for the first 120 month interval.
I.
NE-5. 6-ISI-NDE C) Rev. 0 1
'ks / Change - 1 l Page A-32 of 52 RELIEF REQUEST RR-All l
COMPONENT:
Integrally Welded Attachments (Pumps)
Insulation Lugs Ranger Brackets Pump A: Pump A:
SW-B31-5365-FUMP A-WA
-WB
-WC Pump B: Pump B:
SW-B31-5365-PUMPB-WA
-WB
-WC ASME CODE CLASS:
Class 1 ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Category B-K-1, Item B10.20, requires a surf ace examination of integrally welded attachments for pumps. Attachments whose base material design thickness is 5/8 in, and greater will be examined.
BASIS FOR RELIEF: The reactor recirculation pump insulation lugs and hanger brackets are covered by insulation. To gain access to the examination areas, the pump insulation requires removal.
AFFECTED EXAMINATION AREAS:
Removal and replacement of the recirculation pump insulation will result in an excessive amount of radiation exposure for plant personnel. A
' significant amount of labor would be required to remove the insulation needed to provide access to the examination areas.
Based upon discussions with the contract personnel responsible for the installation of the mirror insulation, a calculation of radiation exposure was made. It was estimated that a total of 12,800 Mr would be expected for this task. This assumes a radiation field of 100 Mr and 9 san-days for removal and replacement of insulation. The operating records of other plants do not show thet pump lugs have a record of significant problems.
In additional industry field data does not indicate that cast stainless steel pump casings are susceptible to service induced flaws. Also ASME Code Case N343, paragraph 2.0, " Examination Category B-K-1", sub ites (b),
allows this exemption.
ALTERNATE EXAMINATION: No alternative test methods are proposed at this time. However, should the insulation be removed for other reasons, the required examinations will be conducted.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
NE-5.6-ISI-NDE jfN Rev. O
.V
(
Change - 1 i
Page A-33 of 52 RELIEF REQUEST RR-A12 COMPONENT DESCRIPTION: Integrally Welded Attachments (Piping Lugs)
SW-E11-3146-2WE SW-E11-3158-1WC SW-E11-3158-2WM
- 2WF IWD 2WN 2WG IWE 2WO 2WH IWF 2WP 2WJ IWG 2WQ 2WK IWH 2WR SW-Ell-3146-7WO SW-N30-3259-10WB SW-E11-3158-5WC 7WH 10WC SWD 7WJ 10WD 5WE 7WK 10WE SWF 7WL 10WF SWG 7WM 10WG 5WH 10WH
! PSFW-E11-3146-255A 10WJ 10WK SW-Ell-3157-5W3 10WL SW-E21-3148-EXPJT-WS 10WM W9
(\ 5WE 5WF 5WG 10WN SW-E21-3149-EXPJT-W8 5WH W9 5WJ ASME CODE CLASS: Class 2 ASME SECTIOS XI REQUIREMENTS:
! Subsection IWC, Table IWC-2500-1, Category C-C, Item C5.30, requires a surface examination of integrally velded attachments for piping.
Attachments whose base material thickness is 3/4" and greater will be examined.
BASIS FOR RELIEF:
Various abandoned lugs exist on piping components within the class 2 system boundaries. There are no support components associated with these lugs and the lugs are not required for any function. Examination of these lugs will increase radiation exposure without benefit to plant safety.
Access to these examination areas will increase radiation exposure to plant personnel. The attachment welds are not full penetration welds and their integrity is not required as they serve no functional purpose. The lugs are non load bearing and no structural change in the welds is anticipated due to inservice operation. Also ASME Code Case N343, paragraph 2.0,
" Examination Category B-K-1", sub item (b), allows this exemption.
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4 NE-5. 6-ISI-NDE f Rev. 0
, ( '
Change - 1 Page A-34 of 52 4
RR-Al2 Cont'd ALTERNATE EXAMINATION: No alternative examinations are proposed at this time. However, leakage testing will be conducted in accordance with i Section II, Category C-H, Ites C7.30 & C7.04 i -
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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i NE-5. 6-ISI-NDE Rev. 0 f( Change - 1 1
(' Page A-35 of 52 I
RELIEF REQUEST RR-A13 i
e COMPONENT DESCRIPTION:
i, f Integrally Welded Attachments (Piping Lugs)
\ PSFW-E11-3151-145A PSFW-E11-3146-148A I PSFW-E11-3146-1485 PSFW-E11-3151-1455 PSFW-E11-314 6-148C PSFW-E11-3151-145C l
PSFW-E11-3146-148D PSFW-E11-3151-145D
! ASME CODE CLASS Class 2 l ASME SECTION II REQUIREMENTS:
Subsection IWC, Table IWC-2500-1, Category C-C, Item C5.30, requires a i
I surface examination of integrally welded attachments for piping.
Attachments whose base material thickness is 3/4" ar.d greater will be ,
examined.
I j g- BASIS FOR RELIEF:
N Several pads installed on Class 2 piping are inaccessible for examination.
) The pads are located in floor penetrations sad serve to restrict movement of the process pipe in the penetration. Clearance between the welded pads a-d the floor penetration pipe is approx 1/16". Examination of these pads is not possible due to their location in the floor penetrations. See
, attached sketch.
Access to the area of the pads is extremely limited. Clearances between process pipe and floor penetration are not sufficient to allow for examination of pads. The pads are not under constant loading and no i' structural change in the welds is anticipated due to operation.
I i ALTERNATE EKAMINATION:
No alternative examinations are proposed at this time. However, leakage j
testing will be conducted in accordance with Section XI, Category C-H, Item C7.30 4 C7.40.
APPLICABLE TIME PERIOD:
l Relief is requested for the first 120 month interval. ,
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NE-5.6-ISI-NDE Rev. 0 Change - 1
( Page A-37 of 52 RELIEF REQUEST A14 COMPONENT COMPONENT: Integrally Welded Attachments (Vessels)
SW-E11-D2-HXS-08 ASME CODE CLASS: Class 2 ASME SECTION XI REQUIREMENTS: Subsection IWC, Table IWC-2500-1, category C-C, Item C3.10, Requires a surface examination of integrally welded
' attachments for vessels. Attachments whose base material design thickness is 3/4" and greater will be examined.
BASIS FOR RELIEF: The RHR Heat Exchanger has two 1" thick support rings welded to the heat exchanger shell. The bottom support ring rests on, and is bolted to, the . structural support steel for the heat exchanger. The weld on the bottom side of the support ring is encased by structural steel making the weld inaccessible for examination.
- The lower support ring is bolted to the structural steel support member for the hest exchanger. Access to the weld area is obscured by structural steel. The weld is a fillet veld and as such not a full penetration weld.
The fillet veld on the top side of the lower support ring (SW-E11-D2-HXS-07) will receive a surf ace examination.
ALTERNATE EXAMINATION: No alternative examinations are proposed at this time. However, the fillet welds on both sides of the top support ring, the stif fener plates connecting the top & bottom support rings, and the weld on the top side of the lower support ring will be examined. In addition, l
1eakage testing will be conducted in accordance with Section XI, Category C-H, Item C7.10 & C 7.20.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
l
NE-5.6-ISI-NDE fr~ Rev. O
\ Change - I Page A-38 of 52 RR-A14 Cont'd BOLTING l
/ 's STIPTENER PLATE W f (TPP. Of 8) o o O* ,
10 0 - - ) 'O e
's i N UPPER SUPPORT RING 0,O
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e-I HEAT EXCHANGER SHELL UPPER SUPPORT RING STITTENER PLATE SW-I11-D2-HXS-LOWER SUPPORT RING SW-E71-D2-HXS-08 -
I STRUCTURAL SUPPORT
}J [ STEEL O i
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NE-5. 6-Is t-NDE Bev. O i jr-~g Change - 1 Page A-46 of $2 Q
5.0 Proarse support Drawinas-5.1 Inservice Inspection Classification Soundary Drawinas The systems or portions of systems subject to the emanination requirements of the ISI - NDE Progree for Forst-2 and the i
associated Class 1, 2, and 3 boundaries are documented os color coded Piping and Instrument Diagrams (P& ids). The ISI Classification Roundary Drawinas, which form a part of the ISI - NDE Program are listed in Table A-5-5.1.
l The system Inservice Inspection classifications, developed specifically to define the extent to which Section XI require-1 ments will be applied, differ somewhat from the ASME Section III l design classifications. These differences occur because systems, i or portions of systems, have been optionally upgraded in design and because 1st classifications are limited to safety related systems which contain water, steam, or radioactive materials.
NUREG '0800, Regulatory Guide 1.26, and 10CTR50 were the document s 1 used in identifying these boundaries.
j 1 5.2 Inservice Inspection (ISI) Isometric Drawinas for Class 1 & 2 i Components and their Supports I l
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NE-5.6-ISI-NDE Rev. 0 t,eg Change - 1
, i(j Fase A-47 of 52 TABLE A-5-5.1 FERMI-2 ISI CLASSIFICATION BOUNDARY DRAWINGS PIS No's Associated ISI Drawing Title Dvs. No. With Dwa. Code Class Sample Line Tle-In And 61721-2400-10 F34 1 2
i Return Diagram Post Accident Sampling Sys Diagram Main and 6M721-2002 B21 1 N11 2 i
Reheat Steam Systems Diagram Feedwater Sys 6M721-2023 N21 1 Diagram Core Spray 6M721-2034 E21 1 2
! System - CSS Diagram High Pressure 6M721-2035 E41 1 2
J Coolant Injection Sys MPSI
! 2 Diagram High Pressure 6M721-2043 E41 Coolant Injection Sys Barometric Condenser I HPCI Reactor Bldg Diagram Reactor Core 6M721-2044 E51 1 l
Isolation Cooling Sys RCIC Diagram Reactor Water 6H721-2046 C33 1 Clean-Up Reactor Bldg 6M721-2048 C41 2
- li Diagram Tuel Pool Cooling and Clean-Up System Diagram Control Rod 6M721-2081 C11 1 2
Drive Hydraulic Sys Diagram Stand-By- 6M721-2082 C41 1 2
Liquid Control Sys 1
l Diagram Residual Heat 6M721-2083 Ell 1 2
Removal (RHR) Division 11 i
Diagram Residual Heat 6M721-2084 Ell 1 2
Removal (RHR) Division I a
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NE-5.6-ISI-NDE Rev. O e, Change - 1 Page A-48 of 52 TABLE A-5-5.1 (cont'd)
PERMI-2 ISI CLASSIPICATION BOUNDARY DRAWINGS PIS No's Associated ISI Drawing Title Dwa. No. With Dws. Code Class (Post Loca) Combustible 6M721-2087 T48 2 Cas Control System Diagram Nuclear Boiler 6M721-2089 B21 1 System 6M721-2090 2 Diagram Reactor 6M721-2833 B31 1 Recirculation System -
Nuclear Boiler System Diagram Main Ste'am 6M721-3045 B21 1 Isolation valve Leakage 2 Control System Diagram Torus Water 6M721-4100 C51 2 Management Systsm P&lD RHR Service Water 6M721N-2052 P45 3 System Division I Ell R30 P&ID RHR Service Water 6M721N-2053 P45 3 System Division II Ell R30 P&ID Service Water 6H721N-2054 Ell 3 Make-Up Decent And P45 Overflow Systems Emergency Equipment 6M721-5357 P44 3 Cooling Water Division II Emergency Equipment 6M721-5444 P44 3 Cooling Water Division I Diagram Control Rod 6M721-5449 Cll 2 Drive Hydraulic System -
Reactor Building O
ME-5.6-ISI-NDE f' Rev. O
\ Change - 1 Page A-49 of 52 6.0 Inservice Inspection Program (Plan) Tables (NDE) j The accompanying table lists the components or areas that are to be examined during the interval. Listed in an order following the items presented in the ASME Section II, Subsections IWB, IWC, and IWD, the tables contain the following information:
Code Class: is the ASME class as defined in accordance with the Code of Federal Regulations (10CFR50.55a) Regulatory Guide 1.26, and NUREG 0800.
Interval: refers to the 120 month inspection interval as discussed in Section 2.0 of this document.
Page/Rev.- indicates the consecutive and total page numbers for the NDE program. Rev. or Revision indicates the revision of the individual page or entire document.
Code Category: is the Examination Category as defined by ASME Section XI, Subarticles IWB-2500, or IWD-2500, or IWD-2500.
Item Number: lists the Item No, as defined by ASME Section XI, Subarticles IWS-2500, IWC-2500, or IWD-2500. Note, all Itee f Numbers are addressed even though they may not be applicable to Fermi 2.
Description and Unique Identification: repeats the generic descriptions listed in tables IhT)-2500-1, IWC-2500-1, and .
IWD-2500-1. The components to be examined are then listed by system and/or specific identification.
Exae Method - Exam Method Selected: identifies the code required method of examination i.e. Volumetric, Surface, or Visual. The specific examination selected is there shown for the component i.e. UT, PT, MT, or VT. (see list of abbreviations for expanded definitions).
Relief Request: if applicable, indicates the request for relief applicable in accordance with 10CFR50.55a (g) (5) (iii). See Section 4.0 of this document.
Augmented Exam Nethod: indicates the specific examination selected to meet any additional examinations required by regulation or licensing commitment.
Se1. Basis: shows the abbreviation for the basis for selection of a component for examination.
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NE-5.6-ISI-NDE Rev. 0 i_/~'T
(~ / Change - 1 Page A-50 of 52 Period: matka the 40 month period within the 120 month interval when the examination is scheduled. (3 periods per interval)
NOTE No attempt has been made to schedule specific examinations at s
this time. All exams will be scheduled for inapection in accordance with the rules of ASME Section - XI, IWA, IWB, IWC, IWD & IWF, and as augmented by specific consitzents (i.e., NUREG 0313). Future revisions to this program (plan) shall be issued for each period to show the specific examinations to be performed during each period as well as all examinations completed during previous periods.
Remarks: is reserved foe additional information to explain, amplify, or orovide adde 6 ' details necessary to clarify the examination requiremen'ts.
6.1 Examination methods delineated in the following tables are intended to be representative of the ISI practice to be used or of preservice methods utilized. In either case, it should be recognized that either UT or RT are acceptable volumetric exams and either PT or MT are acceptable surface exams. Unique weld
-joint parameters may, of ccurse, dictate mort- restrictive
- selection criteria; e.g., high background radiation will preclude RT, stainless materials will preclude MI, etc. It is intended that the process which selects exam methods for' inspections under this plan treat UT and RT as interchangea51e and PT and NT as interchangeable with consideration given to past practice in light of the reproduciDility of results.
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NE-5.6-ISI-NDE Rev. 0 n)
,, Change - 1 Page A-51 of 52 6.2 List of Abbreviations: The following abbreviations are used:
Plant Identification System (PIS) - Codes for Plant Systems B21 - PIS Number for the Nvalear Boiler System B31 - PIS Number for the Reactor Recirculation System Cll - PIS Number for the Control Rod Drive System C41 - PIS Number for the Standby Liquid Control System Ell - PIS Number for the Residual Heat Removal System E21 - PIS Number for the Core Spray System E41 - PIS Number for the High Pressure Coolakh Injection System E51 - PIS Number for the Reactor Core Isolation Cooling System G33 - PIS Number for the Reactor Water Cleanup System G41 - PIS Nurber for the Fuel Pool Cooling System N21 - PIS Number for the Feedwater System N30 - PIS Number for the Main Steam System T48 - PlS Number for the Combustible Gas Control System Acronyms Used to Identify Plant Systems CGC - Combustible Gas Control
, CRD - Control Rod Drive CS - Core Spray FPC - Fuel Pool Cleanup HPCI- High Pressure Coolant Injection RCIC- Reactor Core Isolation Cooling RHR - Residual Heat Removal RRC - Reactor Recirculation RWCU- Reactor Water Cleanup SDV - Scram Discharge Volume SLC - Standby Liquid Control Non-Destructive Examination Method Abbreviations MT -
Magnetic Particle Examination PT - Liquid Penetrant Examination UT - Ultrasonic Examination VT -
Visual Examination VT Visual Examination per IWA-2211 VT Visual Examination per IWA-2212 VT Visual Examination per IWA-2213 VT Visual Examination per IWA-2214 UT Hech. - UT Mechanized i
i t h G
V
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NE-5.6-ISI-NDE Rev. 0 lr s Change - 1
. ,(
Page A-52 of 52 Weld Selection Basis Abbreviations HCU - High Cumulative Usage MS - High Stress MS -
Moderate Stress R - Randoa TE - Terminal End Plant Component and Weld Terminology Abbreviations CRDH - Control Rod Drive Housing EXPJT - Pipe Expansion Joint FBC - Flange Bolted Connection FW -
Field Weld HX - Heat Exchanger HKS - Heat Exchanger Shell IBR - Inner Bore Regian (Nozzle)
IRS - Inner Radius Section (Nozzle)
IIH - Incore Instrumentation Housing LD - Longitudinal Downstress (Seam Weld)
LU - Longitudinal Upstream (Seam Weld)
PAD - Integral Attachment Weld Directly onto the Pressure Boundary of the Pipe PSFW - Piping Support Field Weld PS - Primary Steam (Nuclear Steam Supply System)
RD - Recirculation Discharge RS - Recirculation Suction SDV - Scram Discharge Volume SW - Shop Weld TRUNION - Hanger Support Welded Directly onto the Pressure Boundary of the Pipe VBB - Valve Body and Bonnet Housing
!l
. Generic Miscellaneous Abbreviations BWR - Boiling Water Reactor DWG - Drawing EF2 - Enrico Fermi 2 in. - Inches N/A - Not Applicable NU REG- Nuclear Regulatory Guide 4 PWR -
Pressurised Water Reactor l RR - Relief Request RPV -
Reactor Pressure Vessel Comp.9nent Support Abbreviations 1 i
A - Anchor C - Constant Support
' G -
Guide j k R - Rigid Support s_, SP - Spring Hanger l
-- - - - .- . . . . _ , . . . , . . .\
NE-5.6-ISI-NDE Rev. 0
' Change 1 Page A-6-1 of 106 ISI-CLASS 1 COMPONENTS TABLES ,
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I LBP/100/NE57A/1.0 091965 i
o 6 o FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-2 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS ~ l l I NTERV AI.:
l l I@2C3C4C l Rev. 1 Change i l
Code l I t em l Code Category Descript son Exam Req'dl Retiefl Augmented l Se t . l PERIOD l Cat egory l Number { Code Item No. Description l Exam Method l l Exam i REMARKS I l tinique Identification Selected l Requent l Method l Basis l I nti 2nd 3rd ,
i I I I ii .
B-A l l PRESSifRE RETAINING WELDS IN l l l l l .l l l REACTOR VESSEL l l l l l l l I I l l 1 l l i l Bl.10 l Shell Welds l l l l l l All welds - 1st interval '
l l l l l l l l l B1.11 l Circumferential l Volumetric ,1 l l l l Dwg. 6M721-5360-5 I I I l l l l l 1 i 4-308 A l UT Mech. lRR-IA l l l l 4 l l 4-3085 l UT Mech. . l RR-I A l l l l .
I l l-313 l UT Mech. lRR-lA l l l l l l 9-307 l UT Mech. l RR-l A I I l l 1 l l l l l l l l Bl .12 l Longitudinal l Volumet ric l l l l l ,
I l l l 1 l l l l l l-308A l UT Mech. l RR-l A l l l l l l l-3088 l UT Mech. l RR-I A l l l l l l l-308C l UT Mech. lRR-IA l l l l l l l-308D I UT Mech. l RR lA l l l l l l 2-308A l IIT Mech. l l l l l l l 2-3085 l UT Mech. l l l l l l l 2-308C l UT Mech. l l l l l l l 15-308A l UT Mech. l l l l l l l 15-3088 l UT Mech. l l l l l l l 15-308C l UT Mech. l l l l l l l 15-308D l UT Mech. I l l l l 1 l 2-307A l UT Mech. l RR-l A l l l l l l 2-3075 l UT Mech. IRR-IA l l l l l l 2-307C l UT Mech. l RR-l A l l l l l I I l 1 I l l l Bl .20 l Head Welds l l l l l l l l l l l 1 l l l 51.21 l Circumferential - l Volumetric l l l l l l l Closure Head l l l l l l l l l 1 l l l l 1 l 5-319 i UT l l l l l l l 4-319 l UT l l l l l l l l l l 1 NE-5.6-ISI-NDE
o 6 0 FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-3 of 106 PROGRAM (PLAN) TABLES (MDE) l CLASS I l INTERVAL:
I I @ 2l] 3 C 4 C l Rev. 1 Change 1 I
Code l I t em l Code Category Description Exam Req 1 Rei se t l Augment ed l Sel . l PERIOD l Cat egory I Numhed Code item No. Descript inn l Exam Method l Exam l REMARKS l I linique Identification l Selected Requent 1 Method 1 Rasin Int] 2nd 3rd I l B-A l Bl .21 i Circumferential - l Volumet ric l l l l J Dwg. 6M521-5360-5 (Cont'd) l Cont'd Bott. Head l 1 l l l l l l l l l l l l l l 6-306 l UT Mech. l l l l l l l 5-306 l LIT l RR-2A l l l l 1 I l 1 I i 1 l l Bl .22 l Meriodional - Closure Ileadl Volumetric l l l l l l 1 l l l l l l 1 l 2-319A I IIT l l l 1 l l l 2-319s l UT l l l l l l I 2-319C l tT I I l l l l l 2-319D l UT l l l l l 1 l 2-319E l UT l l l l l l l l-319A I UT l l l l l l l l-3198 l UT l l l l 1 l l l-319C l uT l l l l l l l l-319D l UT l l l l 1 I I l-319E l UT l 1 l l l 1 l l-319 F l UT l l l l l 1 l l-319c I UT l l l l l l l l-319n I uT l l l l l 1 l 1 I l l l l l I Meriodional - Bott. Head l Volumetric l l l l l I I I I I I l I l l I-306A l UT Mech. l RR-IA I I l l l l I-3068 l UT Mech. l RR-lA l l 1 I i l l-306C I UT Mech. iRR-la l l l l l l 1-306D I UT Mech. l RR-I A I l l 1 I I l-306E l UT Mech. l RR-I A l l l 1 l l l-306 F 1 UT Mech. l RR-l A l l l l l l l-306G l UT Mech. l RR-l A l l l l l l l-306n i UT Mech. IRR-lA l l l l l I 1-306J l UT Mech, iRR-IA l 1 l l l I l-306E l tir Mech. lRR-IA l l l l l l 2-306A I Ifr iRR-2A l l l l l 1 2-3068 l UT l RR-2A l l l 1 l l NE-5.6-ISI-NDE
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FERMI 2 INSERVICE INSPECTION l CODE l 1 Page A-6-4 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I l INTERVAL: 1 9 2 C_ 3 C 4 U
- -- - l Rev. _O Change _I Cod e l I t em l Code Category Description i Exam Req l Relie f l Augm. nted l Sel . l PERIOD l Car egory l Number l Code Item No. Description l Exam Met had l Exam l REMARKS l l Unique Identification I Selected Requent I Method l Bagin 1 Intl 2nd 3rd i I I i i B-A l Bl.221 2-306C l ITT 1RR-2A l l l l (Cont'd) l Con t ' d 2-306D l LIT l RR-2A l l l l l l 2-306E l IIT lRR-2A l l l l l l 2-306 F l ifT l RR-2A l l l l l l 2-306G l IIT IRR-2A I l l l l l l 1 I l 1 l l Bl.30 lShell-to-Flange Weld l Volumet ric I l 1 l l l 1 I I I l 1 l l l 13-308 l UT Mech. l RR-1A l l l l l l l 1 I I l l l Bl .40 l Head-to-Flange Weld i Volumetric &l l l l l l l l Surface l l l l l 1 l ! l I l 1 l l l 3-319 l UT l l l l l l 1 l m I l l l l l I I I I I I l l Bl.50 l Repair Welds l Volumet ric l l l l lN/A I l 1 1 I I I I l Bl .51 l Beltline region l Volumetric l l l 1 iNo Repair Welds
! I l l l l l l currently exist l l l 1 l l l 1 B-B l l PRESSURE RETAINING WELDS l l l l l l No Components (BWR) l l IN VESSELS OTHER THAN I l l l l l l 1 REACTOR VESSELS l 1 l l l l l l 1 I I I I I B-D -l l FULL PENETRATION WELDS OF l l l l l l Fermi-2 is on Inspection l l NOZZLES IN VESSELS - l l l l l l Progree B l l INSPECTION PROGRAM B 1 l l l l l Dwg.6M721-5361-5 I I l l l l l l l l Reactor Vessel l l l l l l l I I I I I I l l B3.90 l Nozzle-to-Vessel Weldt l Volumet ric l l l 1 l l l l l l l 1 l l l 8-316A l UT Mech. l l l l l l l 8-3168 I UT Mech. l l l l l l l 8-316C l UT Mech. l l l l l 8-316D l UT Mech, l l 1 NE-5.6-ISI-NDE
FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-5 of_106 FROGRAM (PLAN) TABLES (NDE) l CLASS I l INTERVAL, 1@ 2 4 C_
- l Rev. _O Change _1 Cale l Item l Code Category Descript inn l Exam Req l Relief l Augmented l Sel.l PERIOD l Category l Numhed Code Item No. Descriptinn l Exam Met hod l Exam l REMARKS I I Unique identification Selected I Requent 8 Methnd lRasin I atlt 2nd 3rd i 1 .
1 I I I R-D l 83.90 l 4-316A l In Mech. l RR-6A l l l 1 (Cont'd) l Cont'd 4-3165 l UT Mech. l l l l l l l 4-316C l LIT Mech. l l l l l l l 4-316D l UT Mech. l RR-6A l l l l l l 4-316E l IIT Mech. l l l l l l l 4-316F l UY Mech. l l l l l l l 14-316 A l UT Mech. l l l l l
, I l 14-3165 l UT Mech. l l l l l l l 15-315 l UT l l l l l l l 13-314 A l ffT Mech. l l l l l l l 13-314n l UT Mech. l l l l l l l 13-314C l UT Mech. l l l l l l l 13-314D l UT Mech. l l l l l l l 13-314E l UT Mech. I l l l l l l 13-3147 l UT Mech. l l l l l l l 13-314C l UT Mech. l l l l l l l 13-314tl l UT Mech. l l l l l l l 13-3143 l UT Mech. l l l l l l l 13-314K l UT Mech. I l l l l l l 5-314 A l UT Mech. l l l l l l l 5-314 n l uT Mech. l l l l l l l 19-314 A l ITT l l l l l l l 19-3148 l UT l l l l l l l 2-318 l UT l l l l l l l 4-318A l UT l l l l l l l 4-31ss l irY l l l l l l l l l l l l l l B3.10d Nozzle Inside Radius l Volume t r ic l l Surface l l l l l Section l l l l l l l l l l l l l l l l 8-316A IRS l UT Mech. l l l l l l l 8-3168 IRS l UT Mech. l l l l l l l 8-316C IRS l UT Mech. l l l l l l l 8-316D IRS l UT Mech. l l l l l l l 4-316A IRS l UT Mech. l l l l l l l l l l PT l l l NmtEG-0619 l l l l l l 1 I NE-5.6-ISI-NDE
e Cs FERMI 2 INSERVICE INSPECTION I CODE l l Page A-6-6 of 106 PROGRAM (PLAN) TABLES (NDE) I CLASS I l INTERV AI.: 1 R_ 2 R_ 3 R_ 4 C_ l Rev. _O ChanRe _I Code l It em l Code Cat egory Descript inn l _ Exam Req'dl Relief l Augmented l Sel . l PERIOD l Cat egcry l Number! Code Ites No. Description l Exam Method l Exam I l REMARKS l l tfniouc Identification i Selected l Request Methnd Basin l Intl 2nd 3rd i I l l i
B-D I B3.loal 4-316B IRS I UT Mech. I l l l 1 (Cont'd) l Cont 'a l i I PT l l lNUREG-0619 l l 4-316C IRS I UT Mech. l l l l l l l l l l PT I 1 l NUREG-0619 I I 4-316D IRS I t1T Mech. l l l l l l 1 I I I PT I I lNUREG-0619 l l 4-316E IRS l UT Mech. l l l l l l l 1 l i PT l l lNUREG-0619 I I 4-316F IRS l UT Mech. l l l l l l 1 I l 1 rr l l lNuREG-0619 I I I4-316A IRS l UT Mech. l l l 1 l l l 14-3168 IRS I UT Mech. l l l l l l l 15-315 IRS I UT l l l l l l l 13-314A IRS l UT Mech. l l l l l l l 13-314B IRS l UT Mech. l l l 1 l l l 13-314C IRS I UT Mech. l l l l l 1 l 13-314D IRS l UT Mech. l l l l l l l 13-314E IRS l UT Mech. l l l l l l l 13-314F IRS l UT Mech. I l l l l 1 1 13-314C IRS I UT Mech. l l l l l l l 13-314H IRS l UT Mech. l l l l l 1 l 13-314J IRS l UT Mech. l l l l l l l 13-314K IRS l UT Mech. l l l l l l l 5-314A IRS I UT Mech. l l l l l l 1 5-3145 IRS l UT Mech. l l l l l l l 19-314A IRS l UT l l l l l l l 19-314B IRS l UT l l l l l 1 1 2-318 (R3 l UT I l 1 l l l l 4-318A IRS l UT l l l l l l l 4-318B IRS 1 trr l l l l l 1 l 1 l l l l l N/A IN/A l Nozzle Inner Bore Region l I l Volumetric l l l 1 1 I l 1 1 I I I l 4-316A IBR I l l UT l l l NUREG-0519 l l 4-316B IBR I l l UT l l l NUREG-0619 l l 4-316C IBR l l l TIT l ] l NUREG-0619 l l 1 l l l l 1 NE-5.6-ISI-NDE
6 6 -
o FERMI 2 INSERVICE INSPECTION l Cone l l Page A-6-7 of 106 PRtW; RAM (PLAN) TABLES (NDE) I CLASS I I INTERVAL: 1 R_ 217_ 3 R_ 4 R_ l Rev. _O Change _i Cole i Item l Code Category Descriptinn i Exam Req'd Relie f I Augment ed l Se t . I PERIOD l Cat egory l Numbert Code Item No. Descriptinn l Exam Net hod . I Extem I ll REMARKS I I Unique identification I Selected i Request Method 1 Rasis Int! 2nd 3rd i I i i i l l Nozzle Inner Bore Region l l l l l 1 I l (Cont'd) l l l l l I I I I I l I I l l l 4-316D IBR I l l IIT l l 1NUREC-0619 l l 4-316E IRR l l l IIT I I lNUREC-0619 I I 4-316F IRR I l l UT l l 1NUREC-0619 I I I I l 1 I l l l Pressurizer i I l l l 1No Components (BWR) i I I I I I I I I B3.1101 Nozzle-to-Vessel Welds i I I I l l l l l t i I I I I R3.1201 Nozzle Inside Radium l l l l 1 l l l Section l l l l l l l l I I l l l l l l Steam Cenerators l 1 l l l 1No Components (BWR) l I(Primary Side) l l l l \ l l 1 I I I I I I I B3.1301 Nozzle-to-Vessel Weldt l l l l l l l 1 I I I I l l l B3.1401 Nozzle Inside Radius i I l l 1 l l l Section l I I I I I l l l l l l 1 1 I INeat Exchangers l I l l l 1No Components (BWR) l 1(Primary Side) l l l l I I I I I I l 1 I I l B3.1501 Nozzle-to-Vessel Welds i I l l 1 l l l 1 1 I I I I I B3.160l Nozzle Inside Radius ! l 1 I l l 1 l Section l I l l l l 1 1 1 1 I I I I B-E I IPRESSURE RETAINING PARTTAL I l l l I l l 1 PENETRATION WELDS IN VESSELSI l 1 l 1 I I I I I I l 1 I l 84.10 i Partial Penetration Welds- l Visual VT-2 l l l l l l 1 l 1 I I I I I I I I l l 1 I l l I I I I l l NE-5.6-ISI-NDE
f D Q b
FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-8 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I I INTERVAL: 1 O_ 2 C_ 3 C_ 4 C_ l Rev. _O Change _I Code l Item l Code Category Descriptson i Exam Re<jl Relief l Augmented l Se t . l PERIOD l Category l Numbert Code Item No. Descript ion l Exam Met hod l l Extem l l REMARKS I I Ifnique identification l Selected l Request I Method i Basis ! Istl2nd 3rd l 1 l l l l 1.
l l l l J Dwg. 6M721-5361-5 B-E l 84.11 l Vessel Mozzles l (Coat'd) l l l l l l l l25% Nozzles-external l I 7-315 i VT-2 l l l l l Surfaces - Note 4 I i 17-315 i VT-2 l 1 l l l l l 1 I I I l l
Control Rod Drive Nozzles l l l l IDwg. 6M721-5363-5 l 54.12 l 1 l l Vessel to Stub Tube (1R5) l l l l l l 25% Nozzles-external l l l-310-X__-Y__ l VT-2 lRR-7A l l l l Surf aces - Note 4 I I I I I I I I l Control Rod Drive Nozzles l 1 l l l l l
l l Stub Tube to CRD Housing l I l l l l l l CRDH-Y__-Y__ (185) l VT-2 lRR-7A l l l l 1 l l 1 I l 1 l Instrumentation Nozzles l l l l l Dwg. 6M721-5361-5 l B4.13 l l l 1 Vessel Level & Pressure l l l l l l25% Nozzles-external
< l l l l l l l l Surfaces - Note 4 I I 2-315A I VT-2 l l l l l l l 2-3155 l VT-2 l l l l l l l 2-315C l VT-2 l l l l l i
l l 2-315D I VT-2 l l l l l l 2-315E l VT-2 l l l l l l
I 1 2-315F l vi-2 I l l l 1 l 1 l 1 l l l 1
, I l Incore Instrue ntation l I l l l l Dvs. 6M721-5363-5 I I IIH-X_-Y__ (55) l VT-2 lRR-7A l l l l 25% Nozzles-external l l l l l l 1 l Surfaces - Note 4 l l Pressurizer i l l l l l 1 I I I I I l 1 Heater Penetration Welds l l l l l lNo Components (BWR)
I B4.20 l l l l 1 l 1 l l B-F l l PRESSURE RETAINING l l l l l l Category B-F welds will
! l DISSIMILAR METAL WELDS l l l 1 l 1also be considered as l l l l 1 l Category B-J welds l l l I Reactor vessel l ! ! l l l l l 1 l l l l 1
, I I I I I I I I d
NE-5.6-ISI-NDE i
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FERMI 2 INSERVICE INSPECTION l Cone I l Page A-6-9 of 106 PRT. RAM (Pl.AN) TABLES (NDE) I CLASS I I INTERVAL: I 1]4 21]l 3 l[I 4 C l Rev. 1 Change 1 I
I l l
Corte l item l Code Category Description l Exam Req'd l Relief l Auge *nt ed l Set.l PERIOD l CategnryiNumbert Code Item No. Descripting l Exam Method i I Exam I I I REMARKS I l Unique Identification l Selected l Request l Method l Basis I leti2nd 3rd i l i i i 1 l B-F I B5.10 i Nominal Pipe Size > 4 in. I Volumetric I I l l l Note No. 1 (Cont'd) l l Nozzle-to-Safe End~ land Surfaral l l l [
l l Butt Welds ! I I I l I I I I I l l 1 I I I NS-A l IIT Mech. l l lTE,DMi lDwg. 6M721-3053-5 I l l PT l l l MS I I I I NS-S I tfT Mech. l l l TE,DM l l Dwg. 6M721-3052-5 I I I PT I I I MS I I I l N-9 -
l LIT l l l l lDwg. 6M721-5361-5 I I I n i I I I I I I 2-303 A l UT Mech. I I I l lDwg. 6M721-5358-5 I I I PT I I I I I l l 2-3035 I t!T Mech. I l I l lDwg. 6M721-5358-5 I I I n i I I I I I I 2-303C I uT Mech. I I I I IDvs. 6M721-5358-5 I I I n i I I I I
! I I 2-303D i trT Mech. I I l l tDvs. 6M721-5358-5
' PT l l I I I l l l
, I i 101-304E I UT Mech. l l l I lDwg. 6M721-5358-5 i
i I I n i I I I I l l 2-303 F l UT Mech. l l l l lDwg. 6M721-5356-5 I I I n i I I I I I I 2-303c I ur Mech. I I I I l Dvs. 6M721-5356-5 l l I PT I l t l I I I 2-303n I iri Mech.- 1 I I I IDvs. 6M721-5356-5 I I I n i I I I I I I 2-303J l uT Mech. I i 1 1 IDvs. 6M721-5356-5 I I I n i I l l l 1 1 2-303E I UT Mech. I I I l l D g. 6M721-5356-5 I I I n i l l l I
, I l 4-303 A l UT Mech. I l l l lDwg. 6M721-5356-5 I I I n I I I i 1 1 1 4-30 3s I uT Mech. I I I I Ides. 6M721-535s-5 I I I n l l l 1 l l l 102-304A l UT I I I l lDwg. 6M721-5356-5 I I I n i I I l l I I I l- 1 I l 1 NE-5.6-TSI-NDE
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FERMI 2 INSERVICE INSPECTION l ODDE I l Page A-6-10 of 106 PROGRA'l (PLAN) TABLES (NDE) l CLASS I I INTERVAL: 1 O_ 2 U_ 3 C_ 4 C_ I Rev. _O Change _I Cota i Item l Code Category Description i Exam Req'd Reliefi Augmented l Se t .1 PERIOD l Category i Numbed Code trem No. Description l Exam Method l l Exam l l REMARKS l I Unique Identification I Selected 1 Requent i Methnd IBasial letl 2nd 3rd l l l l l R-F l B5.10 I 102-3045 l trT l l l l LDwg. 6M721-5361-5 (Cont'd) l Cont'd l FT I I l l l I I I I I I I I l B5.20 l Nominal Pipe Size < 4 in. l l l l l l No Nozzle-to-Safe End l I Nozzle-to-Safe End l I l l l 1 Butt Welds < 4 in.
l l Butt Weld i I I l l l l l l 1 l l l l l 85.30 i Nozzle-to-Safe End I l I l l l No Nozzle-to-Safe End l l Socket Welds l l l l l l Socket welds.
I l l 1 I I I l l l Pressurizer I l l l l l No Components (BWR)
I I I I I I I I I B5.40 i Nominal Pipe Size > 4 in. I I I I I I l l Nozzle-to-Safe End~ l l l l l l l 1 Butt Welds l l l l l l 1 I I I I I I I l 55.50 i Nominal Pipe Size < 4 in. I l I I I I l l Nozzle-to-Safe End I l l l l l l l Butt Welds l I l l l l l l l 1 l 1 I I I B5.60 i Nozzle-to-Safe End l l l l l l l l Socket Welds l l l l l l l l 1 1 I I I I I ISteam Generators ! I l l l l No Components (BWR) l l l l l l l 1
-l 55.70 1 Nominal Pipe Size > 4 in. I I I l l l l l Nozzle-to-Safe End' I I l l l l l l Butt Welds I l l l l l 1 1 I I l l 1 I I B5.80 i Nominal Pipe Size < 4 in. l l l l l l l l Nozzle-to-Safe End l I l l l l l l Butt Welds l I I I I I I I I I I I I i l B5.90 l Nozzle-to-Safe End l l l l l l l l Socket Welds l l l l l l l l 1 I I I I I I I l l l 1 NE-5.6-ISt-NDE
FF.RMI 2 INSERVICE INSPECTInN I CODE I l Page A-6-ll of 106 rit0 CRAM (Pl.AM) TABLF.S (NDE) 1 CLASS l I INTE RV At.:
1 I I@2C3C4C l Rev. 1 Change 1 I
code l Item i Code Category Descraptinn i Esam Req'd l ReliefiAugmented i Se t .1 PERIOD l Category i Numbed Code Ites No. Descript ion l Enam Metlanld l Exam i I REMARKS l I Unique identification I selec_t ed Inequest I Nethod IRasig listl 2nd 3rd i i 1 I i l i l Heat Exchangers l l l l l 1 No Components (BWR)
R-F l I I I I I I (Cont'd) I I IB5. lod Nominal Pipe Size 1 4 in. I I I I I l l l Nozzle-to-Safe End i I l l l l l l Butt Welds l I I I I I I I I I I I I I
IB5.lld Nominal Pipe Size < 4 in. I I I l l l l l Nozzle-to-Safe End i I I I I I l
l l Butt Welds I l l l 1 I l
I I I I I I I I
Nozzle-to-Safe End i I I I I l I B5.1201 I Sock et Weld. I I I I l l I
1 1 I I I I I I I IFiping I I I I l l 1 1 I I I I i l l Note No. 1 j lB5.13d Nominal Pipe Size 1 4 in. I I I l l I I Dissimilar Metal Butt Weld 4 l l l l l 1 I I I I I I i l l SW-Ell-2298-6WC l PT l l l l l 1 I I n 1 I I I I l I sW-El l-2299-lW3 i PT I I I I I i
I I I I n i I I I I I I sW-Ell-2327-6We I rr I I I i I i
I I I n i I I I I l l I Sw-E21-3052-4Wox 1 rr I I I i l i
I I i n i I I I I I I sW-E21-3053-4Wot I er i I I I I I I I n i I I I I
, 1 I sW-c33-3096-loWD I er I i i l l l 1 1 I n i I I l l I I sW-c33-3096-12WD 1 Pr I i l i I l
I I I n i I I l l .
I I I I I I I I IB5.14d Nominal Pipe Size < 4 in. l l l l l 1N/A I I Dissimilar Metal Butt Weldd l I i 1 I I I I I I I I I I I I I I I NE-5.6-ISI-NDE ,
FERMI 2 INSERVICE INSPECTION I Cone I l Page A-6-12 of 106 PROCRAM (Pt.AN) TABIES (NDE) l CLASS I I INTERVAL: I R_ 2 R_ 3 O_ 4 O_ l Rev. _O Change _I Cat. [Ites l Code Category Description l Euan Req'dl Rei s e t l Augmen t ed i Se! . i PERIOD l Cat eRnry i Numbed Code Item No. Description i Euam Methodl l Exam l l l REMARKS I Unique Identificatinn I Selected iRequent I Method LBagie Istl2nd 3rd I
i i l i i I B-F IB5.154 Dissimilar Metal Socket l l l l l lNo Dissimilar Metal (Coat"d) l l Welds l l l 1 l l' Socket Welds I I I I I I I I B-C-l l l PRESSURE RETAINING BOLTINC I 1 l l l l '
l lCREATER THAN 2 IN. l l l l l l l IIN DI7 METER l l l I l l ,
I I I I I I I I l l Reactor vessel I I l l l IDug. 6M721-5362-5 '
l l l I l l l All bolts, stude, nuts, l
l B6.10 l Closure Head Nuts ISurface l I I I Ibushings, threads in I I I I I l l flange stud holes.
I I I 326-02, I thru 68 i MT I l l i I i I i l I I I l Examined only when I B6.20 I Closure Head Studs, Ivolumetric l l l l l connections are dis-l I In Place l I I l l l assembled
! 1 l I I I I I I l
I i 326-01, I thru 68 l tfT l l l 1 I I I I I i i I I l B6.30 I Closure Head Studs, ISurface andi I l l l l l When Removed l Volumetric l l l l l 1 I I I I I I I l l 326-01, I thru 68 i MT I I I l l I I I n i I I I I I I I I I I I l 56.40 l Threads in Flange iVntunnetric l l l 1 I I I I I I I I I I I I thru 68 l M I I I I I I I I I I I I I I B6.50 l Closure Washers & Bushings l Visual VT-1l l l l l 1 1 I I I I I I I I 326-03, I thru 68 l VT-1 l l l l l 1 I I I I I I 1 l 1 Pressurizer I l l l l l No Components (BWR) i I I I I I I I l 86.60 i Boltg and Studs I 1 l l l t i I I I I I I I I I I I I I I I Mr.-5.6-ISI-NDr.
o i
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FERMI 2 INSERVICE INSFECTIcel I CODE I I Page A-6-13 of 106 FWty; TAM (Pt.AN) TABLES (NDE) l CLASS I I INTERVAL.:
I I I ] 2 l] 3 0 4 0 i Rev.
I O Change 1 Ost a l Etem l Code Category Descraption i Exam Req'dl Releef l Augmented i Se t . l PERIOD I Cat egory I Nuehed Code Itce No. Description i Exa= Meth M I Euam i I REMARKS I I IMieue ident i ficat ion l Selected I ncouest l Method I Basia l istl 2nd 3rd i I I i i I i n-c-I I B6.70 I Flange Surface, When I l 1 l l J (Cont'd) l l Connection Dissasse.hled i I I I I I I I I I I I I i '
l B6.801 Nuts. Bushings and Washers l I I I I I
, I I I I I I I I l l Steam Generators i I I . l I I No Components (BWR) l 1 I I I I I I I I ss.90 I Bolts and Studs i I I I I I I I I l l 1 1 I lB6. lod Flange Surface When i I I I I I I l Connection Dissassembled l I I I I I I I I I I I I I l 86.114 Nuts. Bushings and Washers l l l l l l l I 1 I I I I I I l West Exchangers l l l I l 1No Components (BWR) 1 I I I I I I l l 56.124 Bolts and Stads l I I I I I I I I I I I I I I B6.13d Flange Surface, When i I l l I l l l Connection Dissassembled i I l l l l l 1 I I I I I I l 86.14d Nuts, Bushings and Washers l I I I I I I I I I I I I I I IFiping l I I I l 1No Bolts, Stude. Nuts, I I l l l l l l Etc. Creater than 2 in.
I B6.lsal Botes .d Studs i I I I I I I I I I I I I I l 96.16d Flange surface, When i I I l l l t 1 Connection Dissassembled l I I l l l 1 1 I I I I I I I B6.17d Nuts, Bushings and Washers l I I I I I I I I I I I I I I IPumps l l l 1 I I I I I I I I I I l B6.18d Bolts and Studs Ivolumetric l l l l IDwg. 6M721-5365-5 I I I I I I I I i 1 1 I I I ME-5.6-tSt-wnE
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FEP*tt 2 INSERVICE INSPECTION I CODE l l Page A-6-14 of 106 F#tW'. RAM (Pt.AN) TAst.ES (MDE) 1 CLASS I I INTERVAt.: I 3_ 2 C_ 3 C_ 4 C_ l Rev. _O Change _I Code i tree l Code Category Descript son l Ezam Req'd Retsell Augmented l Sel . l PERIOD l Categnty l Number! Code Itee No. Deseript ion l Exam Method i Esse l l l REMARKS I I tinique identificatinn 1 Selected I Request l Method I sasis 1 Int! 2nd 3rd i I I i i i i .I s-c-l l86.184 RRC Pump A Studs I tTT l l l l J Dvs. 6M721-5365-5 (Coat'd) l Cent 'd I thru 16 I I I I l 1 i I I i I I I i I l l RRc ru= , s Stads I trT I I I I I I I I thru 16 I I I I I I I I I I I .
I I l l s6.19f11 Flange Surface, When Ivisual I l l l l l l Connection Dissassembled l I I I l l 1 I I I I I I I l 1 RRC Pump A, Flange l VT-l l l l l l I l RRC Pump s, Flagge l vT-1 1 I l l l 1 1 I I I I I I I e6.204 Nuts, sushings and Washers l Visual l I I I I I I I I I I I I I I RRC Pump A .l VT-l I ! I I I I I RRC ru-p a i vT-l i I I I I I I I I I I I I I Ivatwes Ivisual l I I I l No sotte, Studs, Nuts, l 1 I I I I I I Etc. creater than 2 in.
Iss.214 notts and Stads I VT-1 1 1 l 1 1 I I I I I I I i is6.221 Flange Surface, When I vT-l l I I I I I I Connection Dissassembled I l i I I l 1 1 I I I I I I ls6.23d Nuts, sushings and Washers l VT-l l l l l 1 1 I I I I I I I R-C-2 I IFRESSURE RETAININC sOLTING l l I I I l solting may be examined:
l l2 IN. AND LESS IN DIAMETER I I l l l I a) in place under ten-1 I I l 1 l I I sion.
I I I i 1 I I l b) when connection is l I I I I l l I disassembled.
I I I I I i l I e) when the bolting is
! I I I I I I I re= owed.
I I l 1 I l I I I I I I I I I I I I I I I I I l l I I I I I l NE-s.6-ISt-NDE
O C' -
O FERMI 2 INSERVICE INSPECTION l CotiE I I Page A-6-15 of 106 PROGRAM (PI.AN) TABIES (NDE) l CLASS I I INTE RV AI. - I32C3C4C l Rev. O - Change - 1 Cale i Item l Code Category Description Enam Req'd l Rei sef l Augmented l Set.l PERIOD l Category l Nomher! Code item No. Description l Fuam Met hod l l Enam I l l REMARKS I I linique identification l Selected l Request I Method lEssig l I n t] 2nd 3 rd i I I I I I I B-c-2 I t reactor vessel l I I I I I (Cont d) 1 I I I I I I I I B7.10 I Bolt s , St uds and Nuts 1 I I l l l 180 Bolts, Studs, and l l I I I I I I Nuts < 2 in.
~
~
l l Pressurizer I l l l l 1 l I I I I - 1 I I I B7.20 i Bolts. Studs and Nuts ! I I I l lNo Componentn (BWR) l I I I I I I I l
l l Steam Cenerators l l l l l lNo Components (BWR)
, I I I I I I I I i l B7.10 I Bolts. Stods and Nuts l l l l l I I I I I I I I I I IHeat Exchangers i I I I I INo Camponents (BWR) l I I I I I I l l 87.40 l Bolts. Stads and Nuts l I I I I I I I I I I I I I I Iriping I I l l l l 1
l I I I I I I i I B7.50 i Bolts. Stads and Nute ! Visual I l l l l i I I I I I I I l l Flange Bolted l I I I I l 1 l Connections l I l l l i I I I I I I I l l l FBC-Ell-3519-01 l VT-1 ! l I l l Dwg. 6as721-3519-5 l l FBC-E41-2297-01 i VT-1 i I i l l Dug. 6M721-2297-5 l l FBC-E5I-2192-01 1 VT-I I I I I lDwg. 6M721-2192-5 I I I I I I I I I Ir==,s I l l 1 1 I I I I I I I I I I BT.60 I Bolts, Stude and Nuts l Visual VT-1l l l l lDwg. 6M721-5365-5 I I I I I I I I I I Seal Botting RRC Pinop J( VT-t- l l l l l l l Seal Bolting RRC Pump Il VT-! I l l l l l I I I I I I I I IValves l I I I I I I I I I I I I l Visual VT-1l l 87.70 l Bolts, Stads and Nuts l l l NE-5.6-ISI-NDE
- ~
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i I I I I I I I l 1 I rsC-s21-5353-ott i vT-1 I I I I I I I m21-ro3E-vss I vT-t i I I I I I I I I I I I I
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1 1 l rsC-s21-5354-otC 1 VT-1 l l l l l l l 1 s21-rol3C-vss I vT-1 1 I I l l 1 I I I I I I I I I rPC-s21 -53%-o E I VT-1 l I I I I I I s21-rot 3K-vss I vi-t i I I I I I I I I I I I I l l rac-s21-53%-olJ l vT-1 l l I l l i I s21-rol33-vss I vT-1 1 I I I I 1 I I I I I I I I I rsC-s21-53%-ot s I vT-t i I l l l l l s21-rot 3s-vss i vT-t i I I i l I I I i i l I i I i rsc-s21-53%-ot c I vT-t i I I I I '
l l s21-rot 3C-vss I vT-1 1 I I I I I I I I I I I I I I s21-ro22C-vss I vT-t i I I I I I I I I I I I l l l s21-ro28C-vss ! VT-t l l l l l l l I I I I I I l l s21-Nuclear sailer Systen l l l 1 l lDus. 6M721-5355-5 l l Loop D l l l l l l 1 1 I I I l i I I I rsC-s21-5355-01A I VT-1 I I I I I I I s21-rot 3A-Vas l VT-t 1 1 I I l l l I I I I I I I I FsC-s21-5355-oIP I VT-t l I l l l 1 i s21-rol3r-vss i vT-1 I I I I I I I I I I I i 1 1 I s21-ro220-vss I vT-1 1 I l l l l 1 1 I I I I I I I s21-ro2so-vns I vT-1 I I l l l I I I I I I I I I I I I I I I I I I I I I I Nr-5.6-t S t-ND E
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l Rev. O - Change i -
Gode i tree l Code Categosy Descraptson , _ Exam Req'dl Reiset iAugmented i Se t i PERIOD l Category 1Numbert Code Ites No. Description i P,maan Method i I Enam l I l REMARKS Unique Identifiestion L Selected I Wequest I Methg i Ra si e ! I o tl 7nd led l l l 4 l l B-C-2 I 87.70 1 831-Reactor Recirculation I l l l l 1Dwg. 6M721-5357-5 (Cont'd) ICant'd Loop A I l l l 1 l l I I I I i
i l B31-7023A-vs5 l VT-l l l 1 l l I 1 I I I I I l l l R31-F03tA-VBB I VT-3 l l . I I I l i I I I l 331-Reactor Recircostation I I l ;Dvs. 6M721-5359-5 I I toop n i I l l I l t i I l l i I I m31-F023s-vns I vT-I I l l l l l l 1 1 l l l !
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- - - l Rev. _O Cha9ge _I Co.t e l Ites l Code C*tegory Deser o pt son l Eman Req'dl Re t s e l l Auge.-nt ed i Se t . l ItRIOD l CategoryiNumbert Code Itege No. Descriptinn i Euag Method 1 I Eu== I I i REMARKS I I 19nique ident i f icat ion Selected Weguest ! Method l Rasis I latl 2nd 3rd i l i I i l I s-C-2 l a7.70 I Ell-roSon-vsa l VT-l l I l 1 4 (Cont *d) I Coat'd i I l l l l 1 I til-ro60s-van i vT-l l l l l l l l I I I I I I I I Ell-3519 R11R I I l l l IDwg. 6M721-3519-5 I I I I I - I I I I l Ell-ro23-78s l VT-l l I I l l l 1 1 I I I I I I I til-ro22-vsa i vr-l l I 1 l l l l I I I I I I I I Ell-rol9-vss I vT-l i I I I I I I I I I I I I I I E21-3052 Care Spray l l l l l lDwg. 6M721-3052-5 I I I I I I I I I I E21-rooSA-Yss ! VT-1 1 I I I I I I I i 1 1 I I I I E21-roo6A-vsa I vi-l i I I I I I I I I I I I I I I E21-roo7A-Vas ! VT-1 I I I I !
I I I I I I I I I I E21-3053 Core spray i I I I I Io.a. en721-3053-5 I I I I I I I I I I E21-roo5s-vss I vT-l I I I I I I I I l i I I I I I E21-roo6s-y s I n-1 1 I I I I I I I I I I I I I I E21-roors-vns I vr-l i I I I I I I I I I I I I I I E41-2297 nrCI I I I I I I ovg. ese721-2297-5 I I I I I I I I I I sal-roo2-vns I VT-l I I I i 1 I I I I I I I 1
E41-roo3-vss I n-1 I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I l !
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I l 1 1 I I I I I I Integrally Welded l I I I l l I I Attache *ats I I I l l l 1 1 I I I I I I R-J l i PRESStitE RETAININC WELDS I I I I I lAll welds in these Itce i I IM FIP!NC i I I I I INo.s subject to examina-I I I I I I I Itica= are sto= Ped tose-1 I I I I I I Ither by syste. on the
! I I I I I I Ifollowing pases. Each I I I I I I I IIte. no. is repeated for I I I I I I I I each weld for coatinaity i I I I I I I I I I I I I I I I See Part-E, Appendix-A, I I I I I I I I for additionat infor -
1 I I I I I I Itien on Category s-J l i I I I I i 1. eld selection I I I I I I I I I I I I I I I I I I I i 1 I I
'l I I I I I I I I B9.10 I Nominal Pipe Size > & in. I l l l l I I I 1 I I I I I I 59.11 I Circonferential Welds I Surface andI l l I I I I I Volumat r ic I l l l l t i I I I I I I I s9.12 l Longitediaat Welds l Surface and l l l l l 12" of each intersect-l l lVotemetric l l l l ling seem weld will be i I I I I I I Ie=amined I 89.20 I Itaminat Pipe Size < 4 in. I I I I I I l l l l 1 I I I NE-$.6-ISI-WDE
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FEmatt 2 INSERVICE INSPECTIost I CLM l l Page A-6-23 of 106 FROCRAM (Ft.A4) TA31.ES (NDE) l CLASS I I INTERVAL: I R_ 217 3 O_ 417_
_ I Rev. _O Change _!
Comte i tree l Code Cat egory Descr e pt e.we l Fsan Req'dl Rel e e f l Aarguent ed i %1. l FERIOD l Cat enary l Namnber{ Code Itee No. Descript ine 17.ma= Mettnad i I Eman I l I REMAtttS I I t% itoe identificotion ! Selected I acq=== t I Met had I Basis I t er! 2nd 3rd i I l l 1 i i i F-J l 89.21 l Circumferential Welds I surface I I l I I (Cant *d) l l l l l l I I l 1 89.22 i Longitisoimal Welds l Sur f ace i I l l l l 1 I I I l l 1 I I I R9.301 Branch Connectice Welds ! I I l l l l 1 1 I I . I I I l 89.31 i Nominal Pipe Size > 4 in. I Surface and l l l l l l l l Volisamat ric I I l l l l I I I I I I I I so.12 I scaiaat ripe Size < 4 i=. I S=rface i I I I I I I I I I I I I
. I s9.so I Socket Wetas i S rface i I I I I I I I I I I I I I Im21-a.ctear soiter Syste= I I I I I Iown. 9t72t-5352-5 I ILoop A l l I I I I I I I I I I I I l 89.11 1 7-316A I MT I I l TE I I I I I UT Mech. I I I I I I I I I i 1 1 I I n9.12 i SW-PS-2-A3-Ar.U-0 i MT I l l l l I I I n i I I I I I I I I I I I I I s9.tt I SW-PS-2-Al-A I MT I l l MS I I i I i n i I I I I I I I I I I I I I n9.12 i SW-PS-2-Al-ALD-I I MT I I I I I I I I n i I I I I I I I I I I I I I B9.12 i SW-FS-2-Al-ALD-O I MT I I I l l I I I n i I I I I I I I I I I I i I s9.12 i SW-PS-2-Al-BLD-! I MT l l l l l 1 I I n i I I I I I I I I I I I I I s9.12 i SW-PS-2-Al-Bl.U-O I MT I l I I I I I I n i I . I I I I I I I I I ME-5.6-ISI-NDE
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- s. Iso.t I SW-rS-2-Al-B l MT I I I MS l "l (Cont'd) l l l IfT I I I I l l l l l l I I I I s9.12 i SW-PS-2-Al-51.D l MT I I I I I I I I n i I I I I I I I I I I I I I s9.12 I SW-PS-2-A3LU l MT l l l l l I I I n I I I I i I I i i I i i I I s9.1i I ev-rS A3 I MT l l l RS l l 1 I I l l 1 1 I I s9.12 i SW-PS-2-A3LD-0 i MT I l l l l I I I n i I I I I I I I I I I I I l 89.12 I EW-PS-2-A3-ALU-0 l MT I l l l 1 1 I I n i I I I I I I I I I I i l I n9.11 1 SW-PS-2-A3-A l MT l l l MS I I I I I n i I I I I I I I I I I I l l 89.12 i SW-PS-2-A3-ALD l MT l l l l l I I I n i I I I I I l I I I I I I I l 89.11 l SW-PS-2-A3-C l MT I I I MS l l 1 1 I n i I I I I I I I I I I I I l 89.31 i SW-PS-2-A3-L I MT I I I HS I I I I I w I I I I I I I I I I I I I I so.1 I SW-PS-2-A3-F l MT I l l HS l l 1 I I w I I I I I I I I I I I I I In9.1 1 SW-PS-2-A6LU l MT I I l l l l 1 I n i I I I I I I I I I I I i rW-PS-2-A6 MS l n9.1i l NE-5.6-ISt-Mon
6 G O FERMI 2 INSERVICE INSPECTION 1 CODE l l Pare A-6-25 of 106 PRtMRAM (PLAN) TABLES (NDE) I CLASS l I INTERVAL: IR2C3O4 i Rev. 1 Change 1 I I -
I Code l Item l Code Category Descript ion l Exam Req'd Relief lAugm nted l Se t . I PERIOD l Cat egory i Numberl Code Item No. Description i Exam Method l Ex.im l l l REMARKS I I Unique Identification Selected Request '
Method Basin' intl 2nd 3rd i i B-J l l 821-Nuclear Boiler System l l l 1 l lDwg. 6M721-5353-5 (Cont'd) l l Loop B l l l l l }
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I ur i I 1 l l I 1 I I I I I I I n9. i t I sw-rs-2-s3-F l MT l l l ns i I I I I ur I I I I I I I I I I I I I Is9.3 I sw-rs-2-s3-u l MT l l lR I I I I I m I I I I i 1 1 I l l I I I l 89.it I sw-rs-2-s3-3 l MT I I I ns 1 I I I I ur i I i l l l l I I I I I I I n9. t i i su-rs-2-s3-R I MT I I I ns i I I I I m i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l I I I I I I I I I I I I I l l l l l l 1 I I I I I I I I I I I I I l 1 1 I I l wE-5.6-Ist-wDE
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Code l Item l C$le Category Descript ion _ Exam Req'd Reliel l Augm. nted l Set.l PERIOD l Cat egory l Numbed Code Item No. Description Exam Method l l Exam l l REMARKS l l Unique Identification Selected l Requent l Method l Basin I latl 2nd 3rd i I H I I I n-J l 1 R21-Nuclear Boiler System I l l l l 1 (Cont'd) l l Loop C I l l l l l l l l l l l l 1 I n9.121 7-316C l MT l l l TE I I l l l UT Mech. l l l l 1 l l l l l l l l l 89.I2 l Sw-PS-2-Ci-ALU l MT l l l l l l l I m l l l l l 1 l l l l 1 1 I I B9. t l l SW-PS-2-CI-A l MT l l l MS l l l l l ur I i i l l i i l I I I I I
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l 1 I ur l l 1 l l l l l l l l 1 l l 89.12 l S2-PS-2-Cl-ALD-O I MT I l l l l l l l m I I l i I I I l l l l 1 l l 89.12 i Sw-PS-2-C t -stu-t i MT I l l l l l l I m l l l l l l l l 1 1 I I I l 89.12 l SW-PS-2-CI-BLU-0 l MT l l l l l 1 l l uT l l l l l l 1 1 1 1 1 I l l 89.11 l SW-PS-2-CI-s l MT l l l MS 1 l l l I m i I I l l l l l 1 1 I I I I s9.12 l Sw-PS-2-CI-sto l MT l l l l l 1 1 I m I l I I I l l l l l 1 1 I I B9.12 l Sw-PS-2-C3LU l MT l l l l l l l I m I I l 1 I ~
l l l l l l l l l n9.11 I rw-PS-2-C3 1 MT I I I MS I I I i l m l l l l l l l l l l l l l l l l l l NE-5.6-ISI-NDE
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l Code iItem i Code Category Description Exam Req'd Relict l Augented i Set.l PERIOD l Category i Numbed Code item No. Desc ript ion l Ex.im Method , i Ex.im l l REMARKS l l Unique Identification l Selected l Requent Method I nasis! Int] 2nd 3rd i I I I l l n-J l 89.12 I sw-PS-2-C3Lo-o l MT I I I 1 .I I
(Cont'd) l I I UT l l I I l l l l l l l I l n9.12 I sv- PS-2-C 3- AI.t!-O I MT l i I I I I I I uT l l l l l l l l l l l l l
l n9. i t I sv-PS-2-C3-A l MT I l l MS l l l 1 I t:T l l l l l 1 1 I I I I I I sw-PS-2-C3-AI.n i MT I I I I I I n9.12 I l l I ur I I i l l l I I I I I i i I n9. I t I sw-rS-2-C3-C I MT I 1 I nS I I I I I n i I I I I I I I i l i I i i n9.it I sw-PS-2-C3-0 i MT I I I nCu l l l 1 I n l I I I I I I I I I I I I I n9.II I sw-PS-2-C3-F l MT l l l MS I l l l I n i I I I I I I I I I l I I l 89.Ii i sw-PS-2-C3-J l MT l l l HS I I I l I ur i I I l l l l l 1 1 I l l I n9.11 1 Sw-rS-2-C3-K I MT I I I HCU l 1
-1 I I n i I I I i l l l l 1 1 l l I n9.Ii l Sw-PS-2-C3-M i MT l l 1 HS I l l 1 I n i I I I I 1 I I I I I i 1 l l l l 1 1 l l I I I I I I I I l 1 I I I l l l
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l l I I I I I I l B9.12 l SW-PS-2-DI- ALtl l MT l i I I I i 1 I trr l l 1 l l l l l 1 1 I I l
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I I I I I l l I I B9.11 l SW- PS-2-D I -B i MT I I I HS I I I I I m I I I I I l l l l l l l l I B9.12 l SW-PS-2-D I-BLD 1 MT l l I I I I I I m i l l I I I I I I I I I I l 89.12 i SW-PS-2-D3LU l MT l l l l l l l l m i I I I I I I I I I I I I
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Code l Item l Code Category Description Exam Req'd Relief l Augm. nt ed l Set . l PERIOD l Category l Numbed Code Item No. Description l Exam Nethod l Exam i I REMARKS I l unique Ident i ficat ion Selected Requent I Method Basin Istl 2nd 3rd I l i I B-J l 89.12 i SW-PS-2-D3LD-o l MT l l l l l (Cont'd) I l l uT I I l l l l l l l l l l l SW-PS-2-D3-ALu-0 i MT l l l l l l B9.12 l '
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l B9.11 i SW-PS-2-D3-A I MT l l l IIS l l 1 I I ur i I I I I I I I I I I I i MT l l l l l 89.12 l SW-PS-2-D3-ALD l I l 1 I ur I I i i l l I I I I I I l l 89.31 i SW-PS-2-D3-E I MT l l lR I I I I l uT I I I I l l l l l l l l l 1 B9.11 i SW-PS-2-D3-J l MT l l l MS I l 1 I I ur I i i i l i I I i i l I l l 89.11 l SW-PS-2-X 7D-W I l IIT IRR-3A I l MS l l Inaccessible for I l .I MT l l l l lexaminstion i I I I I I I I lB31-Reactor Recirculation i I I l l lDwg. 6M721-5356-5 l
l l Loop A l l l l l l -5357-5 I I I I I I I I
I B9.121 SW-RS-2-Al-W2Lu-I l PT l l I l l l l l m i I I I I I I I I I I I I I B9.12 i SW-RS-2-Al-W2LII-0 l PT l l l l l l 1 uT I I I I I l
I I I I I I I I I B9.11 l SW-RS-2-Al-W2 1 PT l l Note 2 IR l l l I I m i I I I I I I I I I I I I
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I I I nT I I I I l l l l l l I l l I B9.11 I W-RS-2-A3 l PT l l Note 2* IR l l l l l irr l I l l l l 1 1 I I I I l l 89.12 l SW- RS-2-A5 Lt!- ! I PT l 1 1 I l l 1 I irr i I I I I I l l l 1 l l l l 89.12 i SW-RS-2-A5Lt!-0 1 PT I l l l l l l l m l 1 1 I l l l l l I I l l l 89. I 1 l W-RS-2-A5 l PT l l Not e 2 lR I I l l l UT l l l l l l l l l 1 l l l l n9.11 I W-RD A6 l PT l l Note 2 IR I l l l 1 trr I I l l l l l l l l l l 1 l n9.12 l SW-RD-2-A6LD l PT I l l l l l 1 I UT l l l l l l l l l l l l l l 89.31 l SW-RD-2-Al-WI l PT l l Note 2 lR l 1 1 I I m l I I I I I I I l I I I I l 89.11 l W-RD-2-A l -W 1 l PT l l Note 2 IR I l FSAR 5.2.3.2.1.1 1 I I UT l l l l land 5.2.3.2.1.4 l l 1 l l l l l l 89.11 l m- RD-2-A 2-W2 l PT l l Note 2 lR I IFSAR 5.2.3.2.1.1 I I l UT I I I l land 5.2.3.2.l.4 I I I I I I I I I B9.12 l SW-RD-2-A2-W20-LU l PT I l l l l l l l m l l l l 1 1 I l l i I I I I B9. l l 1 SW-RD-2-A2-W2O l PT l l Note 2 iR I IReference DECO Document l l l UT l I I I l NE-83-842 and Ne-83-863 NE-5.6-ISI-NDE
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B-J l B9.12 i SW-RD-2-A2-W20LD l PT l l l l 1 (cont'd) l I I trT l l l l l ;
I I I I I I I I I B9.12 l SW- RD A 2-W 21.l! l PT I l 1 I I i l l uT l l l l i i I I I i l i I I B9.11 i SW-RD-2-A2-W2 I PT l l Note 2 iR I I Reference DECO Document i I I IIT l l l l l NE-83-842 and NE-83-863 1 1 I I I I I I I B9.12 I SW-RD-2-A2-W2LD-A l IT l l l l l l l l n i I I I I I I I I I I I I I B9.12 i SW-RD-2-A2-W2LD-B I PT l l l l l l l l n i I I I I I I I I I I I I I B9.11 i SW-RD-2-A3-W7 l PT I I Not e 2 iR I i 1 I I uT l l l l l l l l l l l l l l 89.12 l SW- RD A3-W 7 LD I PT I I I I I I I l n l I I I I I I I I I I I I I B9.31 i SW-RD-2-A3-W3 i PT l l Not e 2 iR l l l l 1 m i I I I I I I I I I I I I I B9.12 i SW-RD A3-W 9LU l PT l l l l l 1 I I n i I I I I I I I I I I I I I B9.II I SW-RD-2-A3-W9 l PT l l Mot e 2 IR I I I I I n i I I I I I I I I I I I I I B9.1I I FW-RD-2-AlI I PT l l Not e 2 lR I I I I I n i i I I I I I I I I I I I I B9.12 l SW-RD-2-AllLD l PT I I l l l l l l n i I I I I J ! I I I I I I NE-5.6-ISI-NDE
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- I 59.11 l W-RD-2-52-W2 i PT l l Note 2 IR l l FSAR 5.2.3.2.1.1 I I I ur I I l l land 5.2.3.2.1.4 l l l l l l l 1 I B9.12 i Sk'-RD-2-B2-W20 LU l PT I l l l l l 1 I ur l l l l l l l l l l l l l 1 B9.11 l SW-RD-2-52-W20 i PT l l Not e 2 I I I Reference DECO Document l l l UT l l l l l NE-83-842 and NE-83-863 I I l l l l l l l 1 NE-5.6-ISI-NDE
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(Cont'd) l I I uT l l l l l 1 1 I I I I I l l R9. I2 l SW-RD-2-82-W2Lt! I PT l l l l l l l l ur I i I l l i i l l I I I I I B9.11 l SW-RD-2-B2-W2 l PT I I Note 2 lR l l Reference DECO Document i I I IIT I l l l lNE-83-842 and NE-83-863 I I I I I I I l l 89.12 i SW-RD-2-52-W2LD-A l PT l l l l l l l l ur l l l l l l l l l l l l l l 89.12 l SW-RD-2-32-W2LD-B l PT I I l I I I I I ur I I I I I I I I I I I I I I B9.31 i SW L-RD-2-B 3-W4 l PT I l Note 2 lR l l l l l ur I I I I l l l l I I I I I I n9.12 l SW-RD n4-W2 Lu- r l PT l l l l l l l l W I I I I I I I I I I I I I I B9.ll l SW-RD-2-B4-W2 l PT l l Note 2 l MS l l l l 1 -ur i I l l l l l l l l l l l l 59.12 l SW-RD-2-84-W2LD I PT l l l l l
-l i I ur l l I l l l l l l l l l l l i19.12 l SW-RD-2-55-W2Lu-t i PT l l l l l l l l n I I I I I I I I I I I I l l 89.II l SW-RD-2-BS-W2 i PT l l l MS l l l l l uT l l l l l l l l l l l l i I B9.12 l S'l-RD-2-85-W2LD l PT l l l l l l l l ur I i i l I I I I I I I NE-5.6-tSt-NDE
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' I ilT l l l l l 1 I I I I I I I I R9.11 l sW-RD-2-R8-WI l PT l l lR l l l l l itT I I I I I I l i I l l I I I n9 , I sW- RD-2-88-W i l.D-l i Pr I l l l l l l l itT I I I l i I I I I I I I l l M9.12 l SW- RD-2-B R-W21.lf- I l PT l l l l l l l l ifr l l l l 1 1 I I I I I I I I n9.ll I sW-RD-2-88-W2 I rT I I I Ms l I I I I trr i l i I I I I I I I I I I I n9.12 I sW-RD-2-B8-W2LD i PT I I I I l l l l itT I I I I l l I I I I I I I I IEl1-2298-RHR I I I l l IDwg. 6M721-2298-5 I I I I I I I I I B9.ll I W-El l-2298-0WI I MT l l l IIS I I I I o I trr l I I I l
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let! 2nd 3rd i I I I B-J l 89.31 l W-El l -229 9-5WF 5 i MT l l l MS I ,1 (Cont'd) l I l IIT I I I I I I I I I I l l I l *t9. l l I W-El l -22 99-5WO I MT I l l IIS l l l 1 I irr I I l l i i i l l I I I I l l Ell-2327-RHR l l l l l lDwg. 6M721-2327-5 I I I I I I I I l R9. l l I W-Ell-2327-0WI I MT I l l IIS l 1 I I I m i I I I I I I I I I I I I I B9.11 I W-El l -232 7-3W4 l MT l l lR I I l l l ur I I I l l l l l l 1 I I I I B9.11 l W-Ell-2327-4WB l MT I I IR I l l l 1 m I I I l i I I I I I I I I I B9.11 l SW-Ell-2327-6WC I PT I l Note 2 I DM i iNote 1 I n5.13nt I iiT l l l l l l l l 1 1 I I I I n9.12 I sW-Ell-2327-6WCLD l PT l l l l l l l l m i I I I I l l l 1 I I I l l 89.12 i SW-Ell-2327-6WOLU l PT I I l l 1 l 1 l UT l l l l l l l l l l 1 l l l 89.11 l W-El l-2 32 7-6WO l PT I I Note 2 I IIS l l l 1 I m i I I l l I I I I I I I I I IEl1-3519-RHR I I I I I l Dwg. 6M721-3519 I I I I I I I I l 89.11 I W-El l-3519-l W2 l MT l l l R I I I I I m i I I I i I l l l l 1 l I I I I I I I I I I I I I I I I I I I I I I I NE-5.6-ISI-NDE
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6 O O FERMI 2 INSERVICE INSPECTION I CODE I I Page A-6-39 of 106 PROGRAM (PLAN) TABLES (NDE) I CLASS I I INTERVAL: I R___ 2 _ 3 R_ 4 R_ l Rev. _O Change _I Crwt e l I t em l Code Cat egory Descr ipt inn l Exam Req'd l Ret ic t l Augment ed l Sel.l PERIOD l Category lNumberj Code Item No. Descript icq j i.:.itat Met hZ l Exam l I REMARKS l l Ifn igue identification Selectcd ! *equent l Method l BasinlIstl 2nd 3rd I i i l i I R-J l l E21-3053-Core Spray l l l l l 1 Dwn. 6M721-3053-5 (Cont'd) l l l l l l l l l B9.11 i SW-E21 -30 5 3-3WP l MT I I l HS I I I I I W I I I l i I l l l l l l l l 89.11 l SW-E21 - 30 5 3-3WN I MT I I I HS I l l l l irr l I I I I I l l l l l l l 1 B9.ii i SW-E21-3053-4WK l MT I l l MS I l l l l ur i l l l l l l l l l l l l l 89.11 l SW- E21 - 305 3-4WF2 i MT I l l MS I I I I I ur I i l I l l l l l l l l l l 89.11 i SW-E21 - 3053-4Wox I MT l l l DM I INote 1 l n5.13ni I trr i I I I I l l l l l l l l l 1E41-2297-HPCI I l i I I IDwn. 6M721-2297-5 I I I I I I I I I B9.11 l W-E41 -229 7-2W 3 l MT l l lR l l l l l n l I I I I l l l l l l l. 1 I B9.11 l W-E41 - 229 7-3Wo l MT l l lR I I I I I m i I I I I I I I I I I l i I B9.11 l W-E41-2297-0W4 I MT l l lR I l l l l m i I I I i l i l i I I I I I I I I I I I I I I I I I I l i I I I I I I I I I I l l l l l l l l l l l l 1 1 I I I I I I I I i i l l I l l I I l I I I I I I l l l l 1 1 I I NE-5.6-ISI-NDE
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"O FERMI 2 INSERVICE INSPECTION I CODE I l Page A-6-40 of 106 PROGRAM (PLAN) TABLES (NDE) I Cl. ASS I I INTERVAL.; 1Il 2 U 3 U 4 -
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Ce=le l Item l Code Category Deseripeion l Exam Req'd l Reliel l Augm. nt ed l Se t . l PERIOD l Cat er,ory i Numhed Code Item No. Descript ion i Ex'am MetfinM i Fuam l l l REMARKS l l tinique identification l Sclerted 1 Request l Method I nasin Inti 2nd 3rd i I I i l l Est-2192 RCIC I l l l l 1 Dwg. 6M721-2192-5 I I I I I I I I n-J l no.Il i SW-Esi-2192-6WJ l MT I I IR I I
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D FERMI 2 INSERVICE INSPECTION I CODE I I Page A-6-41 of 106 PROGRAM (PLAN) Tant,ES (NDE) I CLASS I I INTERVAI.: I R_ 217_ 3 C_ 4 R_ I Rev. _O Change _I Code i Item l Code Cat egory Descript ion i Exam Req'dl Relief l Augmented i Set. I PERIOD l Category i Numbed Code item No. Descriptinn i Exam Meth M i Exam l l REMARKS l l tin i q ue Identificatinn l Selected l Requent l Method I nazis I Intl 2nd 3rd i i i i l I i B-J l n9.ll I W-C3 3-3096-8W i l l MT l l lR I .I l tir I I I I l (cont'd) i I i i l I I i l l I 89.11 l W-C3 3-3096-10WF 3 I PT I I Note 2 l R I I l l l trT l l l l l l l l l 1 I I I I n9.Il I W-G33- 3096-10Wr t i PT l l Note 2 IR I I I I I tit I I I I I I I I I I I I I l 89.11 l SW-G33-3096-10WD l PT l l Note 2 1 DM i iNote !
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C FERMt 2 INSERVICE INSPECTION I CODE I I Page A-6-42 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I I INTERVAL: I R_ 2 R_ 3 R_ 4 C_ l Rev. _O Change _I Cole l Item i Code Categary Descript ion l Exam Req'd i Rei s al l Augmented i Sel .1 PERIOD l CategoryiNiembert Code Item No. Descript inn i Exam Motland i I Exam i I REMARKS l l tin i q ue identificatinn 1 Selected l Request l Method l Basis l Istl 2n13rd i I I I I I i B -J l R9.11 l W-N21 -2 3 36-0W l 3 l HT I l l MS I 1 (Cont 'd) l I I UT l l l l l l l l l l l l l l 89.11 l SW-N21-2336-13WC I MT I I I HS I I I I I W I I I I i i l I I I I i I i 89.11 l W-N21 -23 36-13W l4 I HT l l l 11 S I l l 1 I trT I l l 1 1 I I I I I I l l l 89.11 I W-N21 -2 3 36-14WF i l MT l l l MS l l l l 1 uT l l I I I i l 1 1 I I I I I B9.11 l W-N21 -2336-14W15 l MT l l l IIS l l 1 1 I trT l l l l l l l l l l I 1 1 I B9.11 i SW-N21-2336-15WP l MT l l lR I I I I I m i I I I I I I I I I I I I I B9.11 l W-N 21-2 336-15WO I MT I I lR l l l l l UT l l l l l l 1 1 I I I I I I n9.ll i N4A I MT I I IR l l i I i w I I I I I l I l l I I I I I n9.ll I 3-316A I MT I I I TE I I l l l uT Mech. I l i I I I I l l I I I l l 89.11 1 SW-N21-2316-13WE I MT l l l MS I I I I I m i l l I I I I I I I I I I I n9. I t i 3-316s i MT I I I TE I I I I I IIT Mech. I I I I l i I I I I I I I I I I I I I I I I I I I I l l 1 1 I I I I i 1 1 I I I I l i I I -
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V V FERMI 2 INSERVICE INSPECTION l CODE I I Page A-6-43 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I I INTERVAL:
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Code l I t em l Cod e Cat egory Desc ript inn Exam Req l Re t t e l l Angm. nt ed l Se t . l PERIOD l Category i Numbed Code Item No. Descript ion i Exam Metlood l l Exam l REMARKS l 1 Unianc Identificatinn Selected l Requent l Method l Rania I nt] 2nd 3rd l ,
. l l R-J l 89.11 l W-N21 -2 3 36-16W l 9 l MT I I IR l .I (Cont'd) l I I ur I I I l l l l l l l i I I I R9.ll 1 3-316C l MT l l 1 TE I I I I l TIT Mech, l l l I l l 1 1 I I I I I l l M21-2336-Feedwater Loop B~ l l i l l lDwg. 6M721-3536-5 l l l I I I I I I B9.11 l W-N21 -2 3 36-lWO2 I MT l l l IIS l IRCIC Selection i I I ITT l l l l l l 89.11 i SW-N21-2336-LWR I MT l l l MS I IRCIC Selection i I I trr I i i l l I 59.11 l W-N21 -23 36-lWO 3 I MT l l l IIS l lRWCU Selection -
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' ,7 FERMI 2 INSERVICE INSPECTION I CODE l l Page A-6-44 of 106 PROGRAM (PLAN) TABLES (NDE) l Cf. ASS I I INTERVAL.: I R_ 2 O_ 3 _ 4 C_ l Rev. _O Change - 1 Cole l Item l Cmt e Cat egory Descript ion Exam Reg'di Rel ic t l Augm. nt ed l Sel . l PERIOD l Cat egory I Numbed Code item No. Desc r i pt inn i Exam Meth M i Exam l l REMARKS tin i q ue identificatinn Selected Request Method Basis ' I nt] 2nd 3rd R-J l 89.11 i FW-N21-2336-4W5 l MT l l l HS 1 .I (Cont'd) i I l tlT I I l l l l l l l l l l l l 89.11 1 3-316F l MT I I I TE l l 1 I I UT Mcch. l I I I I l l l l l l l l l BQ.11 1 SW-N21-2336-3WE I MT l l l MS I I I I I ur i I I I I I I I I I I I I I R9.11 1 3-316E I MT I I I TE I I I I I uT Mech. l l l l l I I I I I I I I I B9.11 1 3-3160 l MT l l l TE l l l l l ur Mech. I I I I I I l I I I I I I I I I I I I I I I l Closure Head-Nozzle to Flangel l I l l 1 I I I n l I I I I I I I I l i I I I B9.11 l l-318 l MT I I I TE I l Dwg. 6M721-5361-5 I I I uT I i i i i l i l i I I I I I B9.11 1 3-318A l MT l l l TE I I Dwg. 6M721-5361-5 l' I I ur i I I I I Dwg. 6M721-3519-5 l l l l l l l l l 89.11 1 3-3188 l MT l l l TE I I Dwg. 6M721-5361-5 I I I uT l l l 1 1 I I I I I I l i I IRPV-Jet Pump Instrumentationi I l l I I I ISafe End to Seal Assembly i I I l 1 I I I I I l i I I l89.11lMRA I PT I l l l l Dwg. 6M721-5361-5 I I I n i I I I I IR9.11lNSB I PT l l l l l Dvs. 6M721-5361-5 I I I n i I I I I I l l l l 1 I I I I I I l I I I NE-5.6-rst-NDE
[D d V FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-45 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I l INTERVAI.: IO2R3R4R l Rev. O Change '~~
I i 1 l Code ltrem l Code Category Descriptinn l Exam Req'dl Ret ie f l Augment ed l Sel . I PERIOD l Cat egory l Numhed Code Item No. Description l Exam Met hmt ! l Exam l l REMARKS l l Unique Identificatinn l Selected l Request l Method l Basis l Intl 2nd 3rd l l l l l l l B-K-l l l INTEGRAL ATTACHMENTS FOR l l l l l l l l PIPING, PUMPS AND VALVES; I I l l l l l l l 1 I l I I l l Piping l l l l l l Includes 100% of the l l l l l l l l weld length l B10.10l Integrally Wclded At t achm. nt d l l l l l l l 1 1 I I I I l l B21-Nuclear Boiler System I l l l l l Dwg. 6M721-5352-5 I l Loop A l l l l l l l l l l l I I l l 810.1ol SW-PS-2-A2-AAl l MT l l l l l l l -AA2 l MT l l l l l l l -AA3 l MT l l l l l l l -M4 l MT l l l l l l l l l l l l l l l IV- PS A4-CA 1 l MT l RR-8A l l l l l l -GA2 l MT l RR-8A l l l l l 1 -CA) l MT l RR-8A I l l l l l -CA4 l MT l RR-RA l l l l l l l l l l l 1 l l SW-PS-2-X7A-W2A l MT l RR-10A l l l l l l -W2B l MT l RR-10A l l l l l l -W2C l MT l RR-10 A l l l l l l l l l l l I l l B21-Nuclear Boiler System ~ l l l l l l Dwg. 6M721-5353-5 l l Loop B l l l 1 l l l l l l l l l I I nl0.lol SW- PS-2 AA I l MT l l l l l l l -AA2 l MT l l l l l l l -AA3 l MT l l l l l l l -us l MT l l l l l l l l l l l l l l l PSFW-PS-2-83-556A l MT l l l l l l l -5568 l MT l l l l l l l -556C l MT l l l l l l l -556D l MT l l l l l 1 l l 1 I I NE-5.6-ISI-NDE
e o FERMI 2 INSERVICE INSPECTl0N l CODE l l Page A-6-46 of 106 PROGRAM (PLAN) TABLES (NDE) l Cl. ASS I l INTERVAL: I f_"d 2 ll 3 C_ 4 R-l Rev. O - Change I -
Code l Item l Code Category Descript ion Exam Req'd Re l ie f l Augme n t ed i Sel . l PERIOD l Category l Numbed Cod e Item No. Description l Exam Method l Exam l REMARKS l l tinique Identification '
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Method l Basis I istl 2nd 3rd l l 1 B-K-1 i B10.101 PS N-PS-2-B3-559A l MT l l l l .l (Cont'd) l Con t ' <( -5598 l MT l l l l l l l -559C l MT l l l l l l l -559D l t'T l l l l l l l l l l l l l l l W- PS-2-B4-CB I l MT l RR-8A l l l l 1 l -CB2 l MT l RR-8A l l l l l l -CB3 l MT l RR-8A l l l l l l -GB4 l MT lRR-8A l l l l l 1 l l l l l l l l SW-PS-2-178-W2A l MT IRR-10A l l l l l l -W2B l MT IRR-10A l l l l l l -W2C l MT l RR-10 A l l l l l l l l l l l l l l B21-Nuclear Boiler System l l l l l lDwg. 6M721-5354-5 l l 1.oop C l l l l l l l l I l l l l l l 810.10l SW-PS-2-C2-AAl l MT I l l l l l l -AA2 l MT l l l l l l l -AA3 l MT l 4 l l l l l l -u4 l MT l l l l l l l 1 1 I l l l l l PS W-PS-2-C3-558 A l MT l l l l l l 1 -558B i MT l l l l l l l -558C l MT l l l l l
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FE R$f l 2 INSERVICE INSPECTION I CODE I I Page A-6-47 of 106 PRtr. RAM (PLAN) TABLES (NDE) l CLASS l l INTERVA1.: 19 2 O 3 C 4 C
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Code i Item l Code Category Descript ion l Exam Req'd Relief l Augmented l Sel . I PF.RIOD I Category l Numbed Code Ites No. Descript ion l %? Method l Exam l REMARKS I linione ident i ficat ion I Selected l Request 1 Method 1BasisI istl 2n<( 3rd I i i i l I i n-K-1 l nio.inl SW-RD-2-A2-Wl6 l PT l RR-9A l l l .l (Cont'd) l Cont 'et -Wl7 I PT l RR-9A l l l l l l -WIS l PT l RR-9A l l l l l l -Wl9 l PT l RR-9A l l l l l l l l l l l l l l TV-RD-2-A2-ALI PT l l l l l l l - AI,2 l PT l l I l l l l -AL3 l PT l l l l l l 1 -AI.4 l PT l l l l l l l l l 1 1 I l l l SW-RD-2-A2-W8 l PT lRR-9A l l l l l l -W9 l PT l RR-9A l l l l l 1 -Wl2 1 PT l RR-9A l l l l l l -Wl3 l PT l RR-9A l l l l l 1 l l I I l l l l 831-Reactor Recirculation l l l l l lDvs. 6M721-5359-5 l l Loop n l l l l l l 1 l l 1 l l l l l slo.lol SW-Rs-2-s2-W6A l PT l l l l l l l -W7A l PT l l l l l 1 l -W8A l PT l 1 l l l l l -W9A l PT l l l l l l 1 l l l l l l l ~ l SW-RD-2-B2-Wl6 l PT l RR-9A l l l l l l -Wl7 l PT lRR-9A l l l l l l -Wl8 l PT lRR-9A l l l l l l -Wl9 l PT l RR-9A l l l l l 1 I I l l l l I l FW-RD-2-52-ALI l PT l l l l l l l -AL2 l PT l l l l l l l -AL3 l PT I l l l l l 1 -AL4 l PT l l ! l l l l l l l 1 1 I I I sW-RD-2-52-W8 l PT IRR-9A l l l l l 1 -W9 i PT IRR-9A I l l l l l -W12 l "' T l RR-9A l l l l l l . -Wl3 i PT lRR-9A l l l l NE-5.6-ISI-NDE
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t'**m FERMI 2 INSERVICE INSPECTION I CODE I I Page A-6-49 of 106 PROGRAM (PI,AN) TABT,ES (NDE) I CLASS I I IN1 E1tVAL:
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Cod e l I t em l Code Category Description Exam Req'd l Relief l Augment ed l Sel . l PERIOD l Category i Numbed Code Item No. Descript ion l Exam Method ,
l Exam i l i REMARKS I linique Identificatinn l Selected '
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9 FERMI 2 INSERVICE INSPECTION I CODE l l Page A-6-50 of 106 PROGRAM (PLAN) TABI.ES (NDE) l CLASS I I INTERVAL.: 1Q2R3R4R I Rev. O - Change 1-Crwie l I t em l Code Category Descriptson l Exam Re<l'dl Re t i e f l Augm. nt ed l Set.l PERIOD l Category i Numbed Code Ites No. Descript ion i Exam Method l l Enam l l l REMARKS I linique Ident i ficat ion l Selected l Re<inest l Method Basis l Int) 2nd 3rd i I i B-K-l l 810.101 PS FW-El l-229 9-836 A I MT l l l l *l (Cont'd) l Cont'.( -836R l MT I I l l l l l -836C l MT l l l l l l 1 -836n l MT I l l l l l l -836E l MT l l l l 1 I l -836r l MT l l l l l l l l l l l l l l l SW-Ell-2299-X12-W2A l MT l RR-10 A l l l l l 1 -w2R I MT l RR-10 A I l l l l 1 -w2C l MT IRR-10A l l l l l l 1 l l l l I i l El1-2327-RilR I I l l l 1Dwg. 6M721-2327-5 I I l l l l l l l B10.101 Sw-Ell-2327-2wD I HT l l l l l l 1 -2wE I MT l l l l l l 1 -2wr i MT I l l l l l l -2wc I MT I l l l l l 1 -2wH l MT I l l l l l 1 -2wJ l MT l l l 1 l l l l l l l l l l l Sw-Ell-2327-4wD l MT I l l l l l 1 -4ws i MT I l l l l l 1 -4wr i MT I l l l l l l -4wc I MT I l l l l I I -4wH l MT I l l l 1 l l -4wJ l MT l l l l l 1 l l 1 l l l l l l SW-Ell-2327-XI3A-w2A l MT lRR-10A l l l l l 1 -w2n l MT lRR-iOA l l 1 l 1 l -w2c I Mr l RR-10 A I l l l l l l l l l l 1 I nIO.10l Ell-3519-RilR I I I I l l l l l 1 l l 1 1 I I Sw-Ell-3519-Kl7-w2A l MT IRR-10A l l l lDwg. 6M721-3519-5 l l -w2n l MT l RR-10 A l l l l l -w2c I MT lRR-10A l l l l l l l N E-5. 6-I S t -ND F,
FERMI 2 INSERVICE INSPECTION I CODE I l Page A-6-51 of 106 PROGRAM (PLAN) TABLES (NDE) I CLASS I l INTERVAL: I@203040 I ae A ch nae 1 1 I Code l Item l Code Category Deseriptinn Exam Req'd l Retici l Augment ed l Se t . l PERIOD l Cat egory i Numbed Code Item No. Descriptinn l Exam Method i I Exam i I REMARKS I Unique Identification l Selected Request I Method l Basis 1 Intl 2nd 3rd i l i B-K-l l 510.101 E21-3052-Core Spray l l l l l l-Dwg. 6M721-3052-5 (Cont'd) l Cont'd l I I l l l 1 I I l l l l l l l SW-E21-3052-2WN I MT l l l l l l l -2WP l MT l l I l l l 1 -2WQ l HT l l 'l l I i 1 -2WR I MT l l l l l l l l l l 1 1 I l l SW-E21-1052-2WS l MT I I I l l l l -2WT l Mr l l l l l l 1 -2Wu I Mr I I l l l l 1 -2WV I MT I I I I i 1 1 I I I l l l l l PSFW-E21-3052-803A I MT l l l l l l 1 -803n l MT l l l l l 1 1 -803C 1 MT l l l l l l l -803D I HT l l l l l l l l 1 1 I I l l l SW-E21-3052-X168-W2A l MT lRR-10A l l l l l 1 -W2R I MT lRR-10A I I I l l l -W2C l MT lRR-10A I I I I I I l l l l l l l l E21-3053 Core Spray l l l l l lDwg. 6M721-3053-5 I I I I I i 1 I I B10.101 SW-E 21-305 3-2WN I MT l l l l l l 1 -2WP 1 MT l l l l l l 1 -2WQ l MT l l l 1 1 1 1 -2WR I MT I I I I I I I l l 1 l l l l l SW-E21-3053-2WS l MT l l l l l l l -2WT I MT l l 1 1 l l l -2Wu l MT l l l l l I 1 -2WV I MT l l l l l l l l l l l l l l l PS FW-E21 -3053-795 A l MT l l l l 1
-7958 MT
-795C MT
-795D MT NE-5.6-ISI-NDE
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O FERMI 2 INSERVICE INSPECTION I CODE l l Page A-6-52 of 106 PROGRAM (PLAN) TABLES (NDE) I CLASS I l INTERVAI,: I R_ 21_7 3 R_ 4 R_ I Rev. _O Change _i Cod e l Item I Code Category Descript son l Exam Req'd l Relief l Augmented l Se t . I PERIOD l CategoryiNumberl Code Item No. Descript ion i Exam Method l I Exam l l REMARKS tinique Identification Select ed lRequent '
Method Basis 1stl 7nct 3rd l
B-K-l lB10.1d SW-E21 -305 3-K l 6 A-W2 A I MT IRR-10A l l l .I (Cont'd) ICont'd -w2B i MT lRR-10A l l l l l 1 -W2C 1 MT lRR-10A I I I I I I I I I I l l l B10.101 N21-2336-reedwater Loop A l l l l l lDwg. 6M721-3537-5 I l l l 1 l l l 1 l Sw-N21-2336-12wC l MT I I l l l ,
I l -12wo I MT l l l l l l 1 -12WE l MT l 1 I l l l 1 -12wr l MT I I I I l l l -12wc l MT l l l l l l 1 -12 wit i MT l l l l l l l l 1 I l l I l l Sw-N21-2336-12wJ l MT l l l l l l l -12wK l MT l l l l l l l -12wt I MT l l l l l l l -12wM i MT l i I I I I l -12wN I MT l l l l l l l -12WP 1 MT I 1 l l l l l 1 I I I I I I I Sw-N21-2336-9WB l MT l l l l l l l -9wC l MT l l l l l l l -9wo I MT i l l I I I l -9wE l MT l l l 1 I l l l l l l l 1 l 1 Sw-N21-2336-K9A-W2A I MT IRR-10A I l l l l l -w2B l MT I FtR-10A I l l l l 1 -W2C l MT l RR-10A l l l l l l l 1 I I I I I l N21-2336 reedwater Loop B I I I I I Ioug. 6M721-3536-5 I I I l l l l l l B10.101 SW-N21-2336-2wC l MT I l l l l l 1 -2wo I MT I I I I I I l -2wE I MT l l l l l l l -2wr i MT l l l l l l l -2wc I MT l l l 1 -2wn l MT I l NE-5.6-iSt-wns
I us FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-53 of 106 PROCRAM (PLAN) TARI.ES (NDE) I CLASS I l INTERVAL: I R 2 R 3_
- - 4 O_ l Rev. _O Change _1 l
Coste l Item i Code Cat egory Descr ipt inn l Exam Re Q Re t se f l Atigmont ed l Sel . l PERIOD I Category l Number l Coile Item No. Descript ion l Exam Method ,
l Ex im i REMARKS l
Unique Identificat_ ion l Selected iRequestl Method l Basis i stl 2ned 3rd i I I I R-K-1 SW-N21-2336-2WJ l MT l l ,1 l B10.10l I l (Cont'd) l Con t ' <j -2WK I MT I l l l l l l -2WL I MT I I I I I I I -2WM i nr l l l l l l 1 -2WN l MT I l l l l l 1 -2WP I MT I l l l l l l l 1 1 I I I l l SW-N21-2336-19WB l MT l l l l l l l -19WC l MT l l l l l 1 l -19Wo l Mr l l l 1 1 I l -19WE I MT I I I l l
. l l l l l 1 I I I I SW-N21-2336-X98-W2A I MT I RR-10A l l l l l l -W2R l MT l RR-10 A I l l l l l -W2C l MT l RR-10A l l l l l l l l l l l l l l Pumps l l l l l }
l l l l l l l 1 i B10.20l Integrally Welded iVolismetric I I I l lDwg. 6M721-5365-5 l l Attachments I or Surface l l l l l l l l as appli- l l l l l l l l cable 1 l l l l l l l I I I I I l l RRC Pump A l l l l l l l l l l 1 l l 1
-1 I SW-531-5365-Pump A-WA I PT l RR-ll A I I l l l l -WB l PT l RR-ll A l l l l l l -WC l PT lRR-IIA l I I I I l l l l l l l l l RRC PUMP R I I l l l l l l l l l l l l l l SW-531-5365-Pump B-WA I PT lRR-llA l l l l l l -WB l PT l RR-II A I l l l l l -WC l PT l RR-II A l l l l l l l l l l l l NE-5.6-ISI-NDE
3 FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-54 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I l INTERVAL: I@203040 l aev. I caaBe 1 I
I Code l I t em l Code Category Descript inn Exam Recj l Rel i e f l Augmen t ed 1 Sel . l PERIOD l Cod e Item No. Descript inn l Exam Met hod l Exam l l REMARKS Category l Numbed i l l Uninue identificatinn l Selected lRequent l Method IBanin Inti 2n<f 3rd i l I i l 1 B-K-1 I
l Valven l l l l l j l
l l l l l l l l l B10.30l Integrally Welded l l l l l l N/A l Attachments l l l l l l I
l 1 l l l l <
. l l l PRESSifRE RETAINING WELDS l l l l l l i B-L-l l l l l l l l l l l IN PLMP CASINGS 1 l l l l l l l 1 Pump Casing Welds l Volumet ric l l l l lNo Pump Casing Welds I Bl2.10l l l l l l l l ,
l l l l l l l l B-L-2 l l PUMP CASINGS l l l l l l l l l B12.201 Recirculation Pump A l Visual VT-3 l RR-4A l l l l Internal Surfaces 1 l Pump Caning (5310lC001A) l l l l l l l
l l l l l l l l l l B12.20l Recirculation Pump B l Visual VT-3 l RR-4A l l l l Internal Surfaces l Pump Casing (B310lC00lB) l l l l l l l l l l l l l l 1 l .
l PRESStqE RETAINING WELDS l l l l l lNo Valve Body Welds B-M-1 l l l l l l l l IN VALVE BODIES l l l l l l l I I l B12.301 Valves, kominal Pipe Size l Surface l l l l l
< 4 in. Valve Body Welds l l l l l l l l l l l l l l l l l 812.40l Valves, Nominal Pipe Size l Volume t r i e l l l l l l -> 4 in. Valve Body Welds l l l l l l l
1 l l l l l l 1
l l l l l l B-M-2 l l VALVE BODY WELDS l l l l l l l l l 512.501 valve Body. Exceeding l l l l l l Internal Surfaces -
l l 4 in. Nominal Pipe Size l l l l l l Examine one valve in l l l l l l each group of valves l l l l l l l l l l that are of the same l l l l l l constructional design l l l l l l l l and manufacturing l l l l l l l l l l method and that per-l l l l l l l l form similar functions l l l l l l l l in the system.
ME-5.6-IST-NDE
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O FERMI 2 INSERVICE INSPECTION l CODE l l Page A-6-55 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I l INTERVAL:
1 I I@2C304C l Rev.
I O Change 1 Cod e l Item l Code Category Descript ion l Exam Req'd i itcliefIAugm.=ntedi Se l . 1 PERIOD l Cat egory l Numhed Code item No. Descript ion l Exam Met hod l l Exam l l l REMARKS l Unique Identification l Selected l Re<1ue9t Methad l Basin i Int] 2nd 3rd l l l l B-M-2 l l B21-Nuclear Boiler System l l l l l .l (Cont'd) l l l l l l l l l Bl2.50l F022A (Vl7-2003) l VT-3 l RR-5A l l l l Dwg. 6M721-5352-5 l l F0228 (Vl7-2001) l l l l l l Dwg . 6M721-5353-5 l l F022C (Vl7-2002) l l l l l l Dwg. 6M721-5354-5 i l F022D (Vl7-2004) l l l l l l Dwg. 6M721-5355-5 l l F028A (Vl7-2007) l l l l l l Dwg . 6M721-5352-5 l l F028B (Vl7-2005) l l l l l l Dwg. 6M721-5353-5 '
l l F028C (Vl7-2006) l I l l l l Dwg. 6M721-5354-5 l l F0280 (Vl7-2008) l l l l l lDwg. 6M721-5355-5 l l l l l l l l l l F013A (V22-2071) l VT-3 l RR-5A l l l l Dwg. 6M721-5355-5 l l F0135 (V22-2068) l l l l l l Dwg. 6M721-5354-5 l l F013C (V22-2060) l l l l l l Dwg. 6M721-5354-5 l l F013D (V22-2054) l l l l l l Dwg. 6M721-5353-5 l l F013E (V22-2056) l l l l l l Dwg. 6M721-5353-5 l l F013F (V22-2050) l l l l l l Dwg. 6M721-5353-5 l l F013G (V22-2066) l l l l l l Dwg. 6M721-5354-5 l l F013H (V22-2058) l l l l l lDvs. 6M721-5353-5 l l F013J (V22-2064) l l l l l l Dwg. 6M721-5354-5 l l F013K (V22-2062) l l l l l l Dwg. 6M721-5354-5 l l F013L (V22-2052) l l l l l lDwg. 6M721-5353-5 l l F013M (V22-2046) l l l l l l Dwg. 6M712-5352-5 l l F013N (V22-2047) l l l l l l Dwg. 6M721-5352-5 l l F013P (V22-2070) l l l l l l Dwg. 6M721-5355-5 l l F013R (V22-2048) l l l l l l Dwg. 6M721-5352-5 l l l l l l l l l l B31-Reactor Recirculation l l l l l l l l l l l l l 1 l l F03tA (V8-2003) l VT-3 l RR-SA l l l l Dwg. 6M721-5357-5 l l F031B (V8-2004) l l l l l lDwg. 6M721-5359-5 l l F023A (V8-2001) l l l l l l Dwg. 6M721-5357-5 ,
l l F0238 (V8-2002) l l l l l l Dwg. 6M721-5359-5 l l l l l l l l l l Ell-RIIR l l l l l l l l l l l 1 l l l l l
NE-5.6-ISI-NDE
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"C FERMI 2 INSERVICE INSPECTION I CODE I l Page A-6-56 of 106 PROGRAM (PLAN) TABLES (NDE) l CLASS I I INTERVAI.:
I I I @ 2 0 3 0 4 i] l Rev.
l O Chaane 1 Code 1 Item i Code cat egory Descript ion l Exam Re<l'di Relief l Augmented l Sel . l PERIOD l CategoryiNumber! Cod e Item No. Descript inn l Exam Met hod [ l Exam I l REMARKS l 1 ttnione identification I Selected l Requent Method Basis' Istl 2nd 3rd l l l B-M-2 l B12.501 FOISA (V8-2161) l VT-3 IRR-SA l l l 'l Dwg. 6M721-2298-5 (Cont'd) l Con t ' d F0155 (V8-2162) l l l l 1 lDwg. 6M721-2327-5 l l l 1 l l l 1 l l F050A (V8-2163) l VT-3 l RR-5A l l l lDwg. 6M712-2298-5 l l F0508 (V8-2164) l l l l l l Dwg. 6M721-232 7-5 l 1 1 I I I l l l l F060A (v8-2165) l VT-3 l RR-5A l l l IDwg. 6M721-2298-5 l l F0608 (V8-2166) l l l l l l Dwg. 6M721-232 7-5 l 1 I I l l l 1 .
l l F008 (V8-2092) l VT-3 lRR-SA l l l l Dwg. 6M721-2299-5 l l l l l l l l l l F009 (V8-2091) l VT-3 l RR-5A l l l lDwg. 6M721-2299-5 l l F608 (V8-3407) l I l I l l Dwg. 6M721-2299-5 l l l l 1 I l 1 l l F067 (V8-2090) l VT-3 l RR-SA l l l l Dwg. 6M721-2299-5 l l 1 l l l l 1 I I F022 (V8-2172) l VT-3 lRR-5A l l l 1Dwg. 6M721-3519-5 l l F023 (V8-2171) l l l l l 1 l l l l l l 1 -1 l l F019 (V8-2173) l VT-3 l RR-SA l l l IDwg. 6M721-3519-5 l 1 l l l l l l
' E21-Core Spray l l l l l l l
l 1 1 I I 1 I l l l F005A (V8-2021) l VT-3 iRR-SA l l l lDwg. 6M721-3052-5 l l F0055 (V8-2022) l I l l l l Dwg. 6M721-3053-5 l l l l l l l l l l F006A (V8-2023) l VT-3 lRR-5A l l l l Dwg. 6M721-3052-5 l l F0068 (V8-2024) l l l l l l Dwg. 6M721-3053-5 l 1 l l l l l l l l F007A (V8-2025) l VT-3 IRR,-5A l l l l Dwg. 6M721-3052-5 l l F007B (V8-2026) l l l l l lDwg. 6M721-3053-5 I I I l l l l l l l E41-HPCI l l l l l l l l l l l l l l l l F002 (vl7-2020) l VT-3 l RR-5A l l l l Dwg. 6M721-2297-5 lDwg. 6M721-2297-5 l l F003 (Vl7-2021) l l l l l l i F006 (V8-2194) l VT-3 l RR-5 A l 1 l l Dwg. 6M721-3537-5 NE-5.6-ISI-NDE
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V FERMI 2 INSERVICE INSPECTinN l CODE l l Page A-6-57 of 106 PROGRAM (PLAN) TABLES (NDE) l CidSS I l INTERVAL: I R_ 2 R_ 3 R_ 4 R_ l Rev. _O Change _I Cod e l Item l Code Cat egory Descript ion _E x as. Req ' d l Re t ie f l Augment ed l Se t . I PERIOD l Cat egory l Numberl Code item No. Descriptinn l Exam Met hoTl l Exam l l REMARKS Unique Identification Selected Request i Method l Basis! Istl 2ned 3rd j l B-M-2 l B12.501 E51-RCIC l l l l l l-(Cont'd) l Con t ' d l l l l l l l l F013 (V8-2228) l VT-3 l RR-5A l l l l Dvs. 6M721-3536-5 l l l l 1 l l l l c33-mCu l l l l l l l
l l l l l l l l l l F001 (V8-2252) l VT-1 lRR-5A l l l l Dwg. 6M721-3096-5 l l F004 (V8-2253) l l l l l l Dwg. 6M721-3096-5 l l l l l l l l
l l F106 (V8-2249) l VT-3 l RR-SA l l l lDwg. 6M721-5351-5 l l F100 (VR-2250) l l l l l lDwg. 6M721-5351-5 l l l l l 1 1 I l l F102 (V8-2251) l VT-3 l RR-SA l l l l Dwg. 6M721-5351-5 l l l l l l l l .
l l N21-Feedwater l l l l l l l l l l l l l l l l F010A (V12-2008) l VT-3 l RR-5A l l l lDwg. 6M721-3537-5 l l F0105 (V12-2007) l l l l l lDwg. 6M721-3536-5 l l F076A (Vl2-2002) l l l l l lDwg. 6M721-3537-5 l l F0768 (V12-2001) l l l l l l Dwg. 6M721-3536-5 l l l l l l l l l l F032A (Vl2-2004) l VT-3 l RR-5 A l l l l Dwg. 6M721-3537-5 l l F0328 (Vl2-2003) l l l l l l Dwg. 6M721-3536-5 l l l l l l l l l l F011A (V12-2006) l VT-3 l RR-5 A l l l lDwg. 6M721-3537-5 l l F0llB (V12-2005) l l l l l l Dwg. 6M721-3536-5 l 1 l l l l l l B-N-1 l l INTERIOR OF REACTOR VESSEL. l l l l l l l l l l l l l l l l Reactor Vessel l l l l l l l l l l l l l l
l B13.101 Vessel Interior l Visual VT-3 l l l l l Examine that portion of l l l l l l l l of the vessel interior l l l l l l l l made accessible during l l l l l l a normal refueling l l l l l l l outage.
l l l l l NE-5.6-ISI-NDE
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