ML20066C103
| ML20066C103 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/07/1990 |
| From: | Hambleton R, Sheffel B DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20066C102 | List: |
| References | |
| PROC-901207, NUDOCS 9101090241 | |
| Download: ML20066C103 (515) | |
Text
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Cl-NDE Pr: gram R:v.1 Change O DETR0li EDISON COMPANY 2000 SECOND AVENUE DETROIT, MICHIGAN 48226 INSERVICE INSPECTION-NONDESTi1VCTIVE EXAMINATION (ISI-NDE) PMOGRAM (PLAN)
FOR FERMI 2 POWER PLANT DOCUMENT NO. ISI-NDE PROGRAM FERMI 2 NUCLEAR OPERATONS CENTER S400 N. DIXIC HIGHWAY l NEWPChT. MIC;41aAN 88166 i
i DATE OF COMMERCIAL OPERATION 1-23-88
(~
Approved by:
Prepared by:
_12 7-78 k@ bl% / tt4AO [B. J, ShffelM F / Dele R. M. Hambleton /Date ISI/ PEP Program Manager Lead ISI Engineer ARMS - INFORMATION SERVICES Release authorized by: _ ,
Date approved:
Change numbers incorporated: , _ ,
,Rev1 ChangeO Date DSN ISI-NDE Program File 1715.04 Recipient DTC TM PLAN 9101090241 901227 F IR ADOCK 0500o34g PDR l
ISI-NDE Program Rev.1 1 Change 0 1
l TABLE OF CONTENTS Page IV .
INTRODUCTION 1 inservice inopeeWon-Nondestructive Enemination A-1 l PART-A (ISI-NDE) Program (Plan) for Piping, Components,'
and integral Attachments A-2 1.0 Applicable Code A-2 1.0 Program Description / Basis Statements A-5 3.0 Exemptions Class - 1 Components A-5 3.1 Class - 2 Components A-7 l 3.2 Class - 3 Components A-8 3.3 Relief Requests A-9 4.0 Rollef Request Description Format A-9 4.1 Rollef Requests A-11 4.2 5.0 Program Support Drawings - ISI isometrics which identify all Class 1 and 2 Components, piping welds, integrell attachments and A-46 tholt supports 6.0 inservice inspection Program (Plan) f
- 09 Tables (NDE)
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ISI-NDE Program Rev.1 Change 0 .
PART-B inservice inspectle9 Program (Plan) for B-1 Component Bappcets 1.0 Applicable Code B-2 B-2 2.0 Program Description Support to be Examined B-2 2.1 B-3 3.0 Corrective Action B-4 4.0 Rollef Requests Relief Request Description (Format) B-4 4.1 Relief Requests B-5 4.2 5.0 inservice inspection Program (Plan) Tables B-9 (Component Supports)
Inservice inspection Program (Plan) for Snubbers C-1 PART-C C-2 1.0 Applicable Code C-2 2.0 Program Description C-4 3.0 Exceptions Rollef Requests C-4 4.0 Rollef Request Description Format C-4 4.1 Relief Request C-5 4.2 1
5.0 Inservice inspection Program (Plan) Tables C-10
($nubbers)
PART-D inservice inspection Program (Plan) for Class MC Components D-1 1.0 Applicable Code
ISI-NDE Program 1 Cev.1 Change O PART E Appendices App endix- A - Sample Selection Document for ISI Class 1 Piping Wolds, Category B-J.
Appendix-b - Sample Selection Document for ISI Class 2 Piping Welds, Category C-F.
Appendix-C - Ctess 1,2, and 3 Loop Selections for Component Supports.
Appendix-D - EF-2 Technical Specificottons, Section 3/4.7,5, Snubbers -
For information Only.
Appendix-E - References Appendix-F - Adopted Code Coses
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ISI-NDE Program Rev.1 Change 0 INTRODUCT60N The inservica inspection (ISI Program (Plan)) contained herein describes the Nondestructive Examinations to be applied to Detroit Edison's Fermi 2 Power Plant (EF-2) for the first ten year (120 month) inspection interval. EF-2 is an 1164 MW Boiling Water Reactor (BWR). This progrem (plan) complies with the applicable requirements set forth in 10CFR50 and Section XI of the ASME Boller and Pressure Vessel Code, ' Rules for Inservice inspection of Nuclear Power Plant Components *.
As stated in 1DCFR50.55s(g)(4), throughout the servics life of EF-2, components (including supports), which are classified as ASME Code Class 1. 2, and 3, shall meet the requirements, except design and eccess provisions, set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code, that subsequently become effective and are incorporated by reference 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 Forml-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.
The first 120-month inspection interval began with the start of commercial operation in January 1988 and will be completed in 1998.
This document is a summary of the Fermi 2 Inservice Inspection Program (Plan) and has been submitted to the Nuclear Regulatory Commission 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 request 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 comrnitments.
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ISI-NDE Program Rev 1 Change 0 This ISI - NDE Program (Flen) is intended to be a reference document and includes all those components and their essociated supports selected for inspection and testing. The items in each category will be scheduled for inspection in accordance with the rules of ASME Section XI and as augmented by specific commitments. Future revisions of this program (plan) shall be issued for each period to show the specific eneminations to be performed during the specific period as well as 21: examinations completed during previous periods.
This document does not include the inservice Testing (IST) Pump and Velve Program (IWP and fWV) commitments.
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lSI-NDE Pregram Rev.1 l
- Change - 0 Page A-1 of 53 t
PART - A INSERVICE INSPECTION-NONDESTRUCTIVE EXAMINATION (ISI-NDE) PROGRAM (PLAN)
POR PIPING, COMPONENTS, AND INTEGRAL ATTACHMENTS i
Cl NDE Pr: gram Rev. i Chengo O Page A 2 cf 63 1.0 Applicable Code The inservice inspection Program (Plan) for Nondestructive Examination (NDE) of Class 1,2 end 3 components is implemented in accordance with the requirements and intent of Subsections lWA, fWB,(WC,(WD, and IWE Section XI Division 1 of the ASME Boller and Proesure Vessel Code,1980 Edition through the Winter 1981 Addenda. All references in thlt document (Part A) to Section XI,- the Code Categories, item Numbers, etc. - refer to the 1960 Edition through the Winter 1981 Addends unless otherwise noted.
2.0 Program Deseviption The NDE Program (Plan) developed herein will utiltre Inspection Program B.
(IWA-2420), Tables IWB-2412-1 and fWC 2412-1 for the first 120 month inspection interval Per 10CFR50.55e(g)(5)(lli), where the requirements of the governing Codt Edition or Addenda are determined to be impractical, within the limitations of design, geometry ent, materials of construction of the components, specific relief requests have been written, These era referenced in the applicable NDE Program Tables and included in section 4,0 of this part. If during the courte of implementation the need for edditional relief is identified,it will be requested at a later date.
In accordance with 10CFR50.55a (b)(2)(iv), the extent of examination (the number of welds required to be exernined) for Code Class-2 pipe welds included in the Residual Heat Removal System (RHR), Emergency Core Cooling Systems (ECC), and Containment Heat Removal Systerns (CHR) was determined by the requirements of paragraph IWC-1220. Table IWC-2520 Caten,?y C-F and C-0, and paragrsph IWC-2411 in the 1974 Edition, including Addenda through the Summer 1976, 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 1976, 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 1976 was used. This includes the Head Spray and Standby Liquid Control Systems added to the Class-2 inservice inspection Program by Detroit Edison Letter EF2-53873, transmitted to the NRC on June 24,1981.
The selection of the individual welds to be examined 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 wolds and results in examining a particular weld only once in the plants 40-year operationallife, No trending of data is possible under the 1975' Summer rules. The 1981 Winter Addenda identifies a l
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Cl NDE Prrgram -
Rev.1 i Change 0 Pege A-3 cf 53 4
4 4
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selection philosophy that concentrates the examinations on those welds that historically j
have a prester probability of failure; namely, high-stress welds, welds et terminal ends, and dissimilar metal welds. In eddition, the 1981 Winter Addenda requires examinations of the same welds in each 10-year interval so that meaningful date 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 criterie 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 def6ned as loading stresses greater than 0.8(1.2Sh + Sa) as per the 1981 Winter Addends.
2.2 All moderately stressed welds defined as loading stresses greater then 0.7(1.2Sh + Sa) and less then or equel to 0.8(1.2Sh + Sa). Inclusion of these moderately stressed welds in the Formi 2 Class 2, inservice inspection Program,is en added conservatism that exceeds the requirements of the ASME i Section XI,1980 Edition, Winter 1981 Addenda.
2.3 All dissimilar metsi welds. (There are none) 2.4 One terminal and 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, Toble IWC-2500-1, Category C-F, Footnote (1)(b).) Edison has taken this opproach to prevent skewing the weld enemination semple to this particular e
type of wold. 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 woul6 be redundant. Therefore, to enable a more representative 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 skomined meets the number required by peregraph IWC-2411 of ASME Section XI,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 and Appendix-8 respectively.
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ISI-NDE Pregram Rev.1 Chango O Page A-4 of 53 Section 5.0 contains copies of Fermi 2's inservice inspection isometric Drawings '
which have been developed for all vessels, piping pumps and volves which require volumetric and/or surface examination by this program.
The system inservice inspection classifications, developed specifically to define the extent to which ASME Section XI requirements will be appfled, differ somewhat from the ASME Section lit design classifications. Primarily, thess differences occur because systems, or portions of systems, have been optionally upgraded in des!gn. In addition,ISI classifications are limited to systems important to safety, which contain water, steam, or radioactive materials.
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Cl-NDTM7; gram Mov.1 Changa O Page A-5 of 53 e
3.0 Exemptions Certain components (or parts of components) are exempt 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. ,
I 3.1 Class-1 Components exempt from volumetric and surface examination '
requirements of hvB-2500 of the Code:
Exemption EX-A1-1 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 size 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 carrying lines and 2.88 inches inside diameter for steam carrying lines.
Exemption EX-Al-2 ASME Section XI Code Paragraph: IWB-1220(b)(1) and (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.'
Exemistion EX- A1-3 ASMF Section XI Code Paragraph: IWB-1220(c)
- Reactor Vassel head connections and associated piping. 2 inches nominal pipe size and smaller, made inaccassible by control rod drive penetrations.'
ISI-NDE Program Rev.1 Change 0 Pope A-6 cf 53 Exemption EX-A1-4 ASME Section XI Code Table: IW8-2500-1 Examination Category 8-H Footnote No.1.
Integral weldeti attachments with a base material design thickness less than 5/8 inch and weld buildup on norries that serve as supports.
Exemption EX-A1-5 ASME Section XI Code Toble: IWB-2500-1, Examination Category 8-K-), Footnote No. 3.
Integral welded attachments with a base material design thickness less than 5/8 inch.
M:v.1 Change O P;ge A-7 cf 53 3.2 Class-2 Components exempt from the inservice examination requirements of (WC-2500 of the Code:
Exemption EX-A2-1 ASME Section XI Code Peregraph: 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 remain 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 J l
operate.
Exemption EX-A2-2 !
ASME Section XI Code Peregraph: 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 psig or above a temperature of 200 degrees F.
Exemption EX-A2-3 ASME Section XI Code Paragraph: IWC-1220(c)
- Component connections (including nozzles in vessels and pumps), piping and associated valves, end vessels and their attachments that are 4 inches nominal pipe size and smaller."
Exemption EX-A2-4 ASME Section XI Code Paragraph: IWC-5222(d)
- For open ended portions of discharge lines beyond the last shutoff valve in nonclosed systems, demonstration of ca open flow path test shall be performed in lieu of the system hydrostatic test.*
Exemption EX-A2-5 fWC-2500-1. Examination Category ASME Section XI Code Table:
C-C, Footnote No.1.
Integral welded attachments with a base material design thickness less than 3/4 inch.
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Cl-NDE Pr: gram Rev.1 Change O Pege A-8 cf 53 3.3 Class-3 Components exempt from the intervice inspection requirements of IWD-2600 of the Code:
Exemption EX-AS-1 ASME Section XI Cnde Paragraph: FWD-1220.1
- integral attachments to supports and restraints to components that are 4 inches nominal pipe size and smaller within the system boundaries of examination categories D-A, D-8, and D-C of Table IWD-2500-1 shall be exempt from the visual examination VT-3.*
Exemption EX-AS-2 ASME Section XI Code Paragraph: FWD-1220.2(a) and (b)
- lntegral attachments of supports and restraints to components exceeding 4 inches nominal pipe size may be exempted from the visual examination VT-3 of Table LWD-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 psig or less and at a temperature of 200 degrees F or less?
Exemption EX-A3-3 ASMd Section XI code Paragraph: FWD-5223(d)
- For open ended portions of discharge lines beyond the last shutoff valve in nonclosed system (e.g., service water systems), confirmation of adequate flow during system operation shall be acceptable in lieu of system eydrostatic test.*
Exemption EX-A3-4 ASME section XI Code Paragraph: IWD-5223(e)
- Open ended vent and drain lines from components extending beyond the last shutoff valve and open onded safety of relief valve discharge lines shall be exempt from hydrostatic test?
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Rev.1 Change O Page A-g cf 53 4.0 Rollef Roguests Rollef Requests are included where specific requirements of ASME Section XI are determined to be impractical. E6ch Relief Request is written in accordance with the format guidelines provided in Section 4.1. Individual Relief Requests are included in Section 4.2. As noted in the INTRDDUCTION, Section 4.2 is subject to change throughout the inspection interval. If examination requirements in this program plan are determined to be impractical during the course of the interval, additional or modified Relief Requests will be submitted in accordance with 10 CFR 50.55a (g) (5)
(111).
4.1 Relief Request Format Each Rollef Request willinclude the following sections:
4.1.1 COMPONENT DESCRIPTION: The component description will include:
o A general description of the component (s) addressed by the Rollef Request, o The applicable Plant identification System (PIS) number (s) which uniquely identWy the plant system and specific component (s) within the system, and o A quantity of components if the Rollef Request covers more than ten (10) components.
4.1.2 ASME CODE CLASS: The ISI classification, Class 1,2,3, E1, E2, or E3, as identified on the ISI Classificatlan Boundary Drawings wl!I be listed.
4.1.3 ASME SECTION XI REQUIREMENT: The impractical ASME Section XI requirement (s) will be listed. To the extent possible, subparagraphs, individual footnotes, or specific item Numbers will be cited.
4.1.4 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 examination, examination method, or acceptance standard.
Cl-NDE Program
' Mov.1 ChangeO P;ge A-10 cf 53 1 I
o A description of the proposed siternative examination's impact on l plant safety and justification of any change in the overall level of )
plant safety. l l
o A justification of any change in the overall level of plant safety if it Is not possible to perform siternative examination (s).
4.1.5 ALTERNATE EXAMINATION: Any shornate examination (s) that are proposed will be identified. Both thernate examination (s) that are periormed in lieu of the Section XI examination requirement (s) and atternate examination (s) that supplement partially completed Section XI enemination requirement (s) will be klentified. The description of the I alternate examination (s) will include a statement describing the extent and frequency of examination, the acceptance standard, and whether deferrral of inspection to the end of the intervalis requested.
A statement identifying the time period 4.1.6 APPLICABLE TIME PERIOD:
during the inspection interval for which relief is requested will be included.
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Cl-NDE Program Cev.1 Change O Page A-11 cf 53 4.2 Rollef Request (s)
The following Rollef Request (s) are included in this section:
RE!.lEF REQUEST NUMBER OENERAL DESCRIPTION RR-A1 RPV shell and head welds are only partially accassible to mechanized examination equipment.
RR-A2 RPV bottom head welds in the conter of the head are inaccessible due to CRD housing interferences.
RR-A3 A Class 1 moderate stress circumferential piping weld (pipe 'to flued head wold SW-PS-2-X7D-W1) in the guard pipe is inaccessible RR-A4 Reactor recirculation pump internal visual examinations solely for the purpose of satisfying the requirements of Examination Category B-M-2 are impractical. If the pump is disassembled for maintenance, the examination will be performed.
RR-AS-R1 Class 1 valve internal visual examinations solely for the purpose of satisfying the requirements of Examination Category B-L-2 are impractical. If a Class 1 valve is disassembled for maintenance. the examination will be performed.
RR-A6 RPV feedwater nortles N4A and N4D are pertla!!y inaccessible since instrument nozzles N11A and N118 are too close to feedwater nozzles N4A and N40.
RR-A7 Control rod drive and instrumentation nozzle partial penetration welds are inaccessible to direct visual examination.
RR-A8 Main steam piping lugs near the inboard main steam isolation valve are impractical to examine.
RR-A9-R1 Integrally welded attachments (piping lugs) Class 1.
RR-A10 Integrally welded attachments (piping lugs) Primvy Containment Penetrations.
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" (2I-NDE Pr: gram Rev.1 C.tange 0 Pege A-12 cf 63 RR- All Reactor recirculation pump integrally welded attachments are i l
impractical to examine. l RR-A12 integrally welded attachments (piping lugs) Class 2. I 1
l RR-A13 The design of component supports E11-3146-030 and E11-3151-020 makes the integrally welded attachments associated with these guides inaccessib6e.
I RR-A14 The weld on the bottom side of the RHR heat exchanger support ring is surrounded by structural steel and is inaccessible to I examination. !
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Rev.1 l Chenge O Page A*13 cf 53 a
RELIEF REOUEST ~ RR- Al
! COMPONENT DESCRIPTION:
Reactnr Pressure Vessel (RPV), See Table 1 (aMached)
A&ME CODE CLA$$
Class 1 Vessel ASME CODE SECTION XI REOUIREMENTS: Subsection (WB, Table IWB-2500-1, Examination Category B A, ttom No's. B1,10 and 81.20, require volumetric examination of the regions described in figures (WB-2500-1 through 3 for pressure retalning welds in the reactor pressure vessel each inspection interval.
RAll$ FOR RELIEF: Due to mechanized examination equipment limitations and norrie interferences, a 100% volumetric examination is not possible for certain shell and lower head i
welds. Coverage of the effected examination areas will be reduced depending on the i physicallimitations of the equipment and interferences encountered on a given examination.
The Fermi 2 RPV Perservice (PSI) nondestructive examinations were conducted in accordan with ASME Code Section XI,1971 Edition with Addenda through Winter 1971, and Section lil, 1968 Edition *with Addenda
- through Summer 1969. Subsequent to the RPV PSI, a pole track system was designed to allow remote ultrasonic (mechantred) examination of the RPV Welds. The design allowed for maximum weld coverage possible with the equipment available at that time. The code.In effect at the time Section XI 1g74 Edition required that 10% of the length of each longitudinal weld and 5% of the length of each circumferential weld be examined, the designed pole track system exceeded the examination requirements l
in effect at that time.
Performance of the limited ultrasonic examinations and the leakage tests will provide the maximum assurrence practicable that the vesselis structurally sound for plant operation.
ALTERNATE EXAMINATION:
No alternative examinations are proposed at this time.
However, each listed weld will be examined to the extent indicated with possible additional coverage when equipment design allows, in addition to these examinations, leakage testing will be conducted at each refueling outage in accordance with Section XI, Examination Category B-P ltem No. B15.10 and once overy ten years in accordance with Section XI Examination Category B-P, item No. B15.11.
APPLICAtt,E TiktE PERIOD: Rollef is requested for the first 120 month interval.
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ISI-NDE Program Rev.1 Change O P ge A-14 cf 53 ftR-A1 Cent'd ENRICO PERMI 2 Wold Coverage Using Mechantred Ultrasonic Examination Source - Southwest Rosesrch Institute
% Coverage
- Wold identification Circumferential Wolds:
100 6-306
' 26 9-307 35 1-313 25
'4-308B 22 4-308A 17 13-308 "
Longitudinal Welds:
14 2-307A C2 2-307B 73 2-307C 100 15-308A 100 15-308B 100 15-308C 100 15-308D 100 2-308A 100 2-308B 100 2-308C i 72 1-308A 72 1-308B 72 1-308C 72 1-3080 Meridional Wolds:
76 1-306A 76 1-3068 76 '
1-306C 76 1-3060 76 1-306E 76 1-306F 76 1-3060 76 1-306H 76 1-306J 76 1-306K
- Examination coverage of less than 100% due to nozzle interference and examination device
- mechanical limitations.
- A supplemental Manual ultrasonic examination will be conducted for weld 13-308, shell-to-flange. This examination will be conducted from the flange seat surface and will l
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Include 100% of the weld.
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Cl-NDE Program Rev.1 Change 0
- Page A-16 cf 53 3
REUEF REQUEST RR-A2 COMPONENT DESCRIPTION:
Re6ctor Pressure Vessel (RPV) - Bottom Head Wolds Wold Wentification Type 5-306 Circumferential 2-306 A thru O Meridional ASME CODE CLASS:
ASME SECTION XI REQUIREMENTS: Subsection IWB, Table 'WB-2500-1, Examination Category B-A, ttom No. B1.20 requires volumetric examination of the regions described in figure IWB-2500-3. Examination of these pressure retalning welds in the reactor pressur:
vessel are required sech inspection interval.
BASl5 FOR REUEF: Control Rod Drive (CRD) housings in the lower head prevent access to vessel welds in this ares. See f!gure 1.
Due to the cluster of CRD drive housings in the lower head, access to the 7 meridional welds and 1 circumferential weld depicted in figure 1 is not possible. Volumstric examinations can not be conducted.
Performance of the leakage tests will provide assurance to the extent practicable, that the vessel is structurally sound for plant operation.
No alternative examinations are proposed at tnis time.
ALTERNATE EXAMINATION:
However,leaknge testing will be conducted each refueling outage in accordance with ASME Section XI, Toble IWb-2500-1 Examination Category B-P, item No. B15.10 and once every ten years in accordance with secuon XI, Examination Category B-P, item No. B15.11.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
ISI-NDE Program j
Rev.1 Change D Page A-17 Gf $3 1
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MOURE 1 LOWER HEAD WELDS AND CRD PENETRATIONS l
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' Cl-QLRr:gDa 7 Mev.1 Chango 0 Page 918 Cf 53 RELIEF REQUEST RR-A3 COMPONENT DESCRIPTION:
Circumferential Piping Wold SW-PS-2-X70-W1, Pipe to Flued Head ASME CODE CLASS Class 1, Mping Subsection IWb Table (WB 2$00-1, Examination ASME SECTION XI REQUIREMENTS:
Category B-J, item No. Bg.11, requires surface and volutnetric examinations of Welds where the stress level exceeds 2.4 Sm. In addition to this requirement, The Detroit Edison Company has supplemented this requirement to include those Welds which exceed 2.1 Sm. Welds which meet this stress level, between 2.1 Sm and 2.4 Sm. are designated moderate stress' Welds.
BASIS FOR RELIEF: 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 examination equipment access to the Wold ar6;;, in addition, the open end side of the penetration assembly is obstructed by construction centering lugs, as shown in the figure, and the installed insulation.
The examination 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 progrom would be required to fabricate the required examination equipment. A program of this nature is not feasible. Only one selected Wold is affected by this situation. Because of these factors and the fact that the code does not require the exam 6 nation of this weld, relief is requested from the commitment made by Detroit Edison to examine this moderate stress weld, Performance of the leakage tests will provide assurance that the piping is structurally sound for plant operation.
No attemative examinations are proposed at this time.
ALTERNATE EXAMINATION:
However, leakage testing will be conducted each refueling outage in accordance with Section XI, Examination Category B-P, ttom No. B15.50 and once every ten years in
( accordance with Section XI Examination Category B-P, item No. B15.11.
APPLICABLE TIME PERIOD: Rollet is requested for the first 120 month interval.
i.
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Cl-NDE Program Cev.1 Change 0 Page A-20 of 53 RElJEF REQUEST RR-A4 COMPONENT DESCRIPT60N:
Recirculation Pumps (B3101C001A and 8310100018) ,
Pump Casings l ASME CODE C1. ASS Class 1, Pumps ASME SECTION XI REQUIREMENTS: Subsection IWB, Table IWB-2500-1, Examination Category B-L-2, item No. B12.20 requires that the internal surfaces of one recirculation j
pump casing be visually er.amined (VT-3) each inspection interval. Specifically, the area of examination includes all pump casing internal pressure boundary surfaces. 1 BASIS FOR RELIEF: Access to the recirculation pump casim; 'nternal surfaces can only be i accomplished when the pump has been disassembled. At tnis time, there are no other requirements to dMassemble 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 exposure. It is expected that approximately 1000 man-hours and 50 man-rem exposure 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 surface condition, realistically provides little additional Information as to pump casing integrity.
The recirculation pumps at Fermi 2 are Byron Jackson, type DVSS. The pump casing is primarily a single piece design of cast stainless steel (ASTM A-351, grade CF8M) and is widely used in the nuclear Industry. Operating histories of recirculation pumps do not warrant concern for casing failure or inservice growth of manufacturing flaws. The presence of some delta ferrite (typically 5% or more) Imparts substantistly increased resistance 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 examination of the pump internal pressure boundary surfaces only when the pumps are required to be disassembled for maintenance, in addition both pumps will be VT-2 examined overy refueling outage during leakage tests and once in the interval during hydrostatic testing.
Cl NDE Program Rev.1 Change O Pope A-21 of 53 RR-A4 Cont'd ALTERNATE EXAM 6 NATION: No alternative saaminettons are proposed at this time, in accordance with Sect 6on XI, Examination Category B-P, item No's. 815.60 and 815.61, 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 whic. would provide access to the internal surfaces, a visual examination of the internal surf aces shell be performed.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
I
ISI-NDE Program Rev.1 Change 0 Page A-23 of 63 RELIEF REGUEST RR-A5-R1 COMPONENT DESCRIPTION:
The Formi 2 unit Class-1 systems contain 62 valves which are greater than four (4) inches nominal pipe size. These valves vary in site, design and manufacturer but all are manufactured from either cast or forged stelnless steel or carbon steel. None of the valve bodies are welded. Of these 62 valves,22 are subloct to visual examination (VT-3) per Table IWB-2500-1, Category B-M-2, ttom B12.50. The 62 valves to which this Relief Request applies are listed below:
B21 F022A (V17-2003) Eli F008 (V8-2092) 033 F001 (V8-2252)
B21 F022 ' (V17-2001) E11 F009 (V8-2091) 033 F004 (V8-2253)
B2' F022C (V17-2002) E11 F015A (V8-2161) 033 F100 (V8-2250)
B't F0220 (V17-2004) E11 F015B (V8-2162) 033 F102 (V8-2251) I B21 F028A (V17-2007) E11 F022 (V8-2172) 033 F106 (VB-2249)
B21 FC28B (V17-2005) E11 F023 (V8-2171) 821 F028C (V17-2006) E'1 F0s0A (V8-2163) N21 F010A (V8-2008)
B21 F0280 (V17-2008) E11 F0500 (V8-2164) N21 F0100 (V12-2007)
E11 F060A (V8-2165) N21 F011 A (V12-2006)
B21 F013A (V22-2071) E11 F0600 (V8-2166) N21 F011B (V12-2005)
E11 F067 (V8-2090) N21 R,32A (V12-2004) 821 F013B (V22-2068)
C21 F013C (V22-2060) E11 F608 (V8-3407) N21 F032B (V12-2003) 821 F0130 (V2;c-2054) N21 F076A (V12-2002) 821 F013E (V22-2056) N21 F076B (V12-2001)
B21 F013F (V22-2050)- E21 F005A (V8-2021)
B21 F013G (V22-2066) E21 F005B (VB-2022) 821 F013Fi (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) 621 F013N (V22-2047) E4 ' (CO2 (V17-2020)
B21 F015F (V22-2070) E4) F003 (V17-2021) 821 F013R (V22-2048) . E41 F006 (V8-2194)
B31 F031 A (V8-2003) F"i l'013 (V8-2228)
B31 F031B (V8-2004)
B31 F023A (V8-2001) 831 F023B (V8-2002)
Rev.1 Change 0 .
Page A-23 cf 53 <
RR-A5 Cont'd .
ASME CODE Clf.SS Class 1, Valves ASME SECTION XI REQUIREMENTS: Subsection (WB, Table IWB-2500-1. Category B-M-2, hem 812.50, rerluires 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.
SASIS FOR RELIEF: Access to valve internal surfaces can only be accoriiplished when the valve is disassembled. Disassembly 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 so plant personnel, in scme cases, radiation fields at high as 10 R/hr could be experienced. In addition, further lator 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 core and vessel draining.
Performing these visual examinations on poor as-cast surfaces provides littio additional information as to valve body integrity.
The valves at Fermi 2 are cast stainless steel and cast or forged carbon steel. Historically these materials have excellet.1 service records and there is little reason to expect service related flaws in these valve bodin.
ALTERNATE EXAMINATION: No alternate examinations are proposed at this time. In accordance with Section XI, Category B-P, ttoms B15.60 and B15.61, a system ieskoge test tilli be conducted at each refueling outage and a system hydrostatic test will be conducted once during the interval. Also, whenever these valves are disassembled for maintenance, or for any other reason which would provide access to the internal surfaces, a visuct
- examination of the internal surf aces shall be performed.
APPUCABLE TIME PERIOD: Rollef is requested for the first 120 month interval.
IS!=NDE Pr: gram 0;v.1 ChangeO Page A-24 of 53 RELIEF REQUEST RR-A8 T'OMPONENT DESCRIPTION:
Af tor Pressure Vessel (RPV) -
4-316A, Feedwater nozzle at 30 0 4-3160, Feedwater nozzle at 2100 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 attache.' 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 liraltations 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 azi muth 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 leake;;; tc ts will provide the maximum sssurance practicable that the vessel is structurally sound for plant operation.
ALTERNATE EXAMINATION:
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 L XI Examination Category B-P, item No. B15.11.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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Cl-NDE Program Rev.1 Change 0 Page A-25 of 53 RR-A4 Cent'd C -
332 INST RU ME NTATI O N WELDS 4-316A & D NO22LES NilA&B y N\'N 9
2 86' E +
b'O f ., \
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N NO EXAMINATION BETWEEN , j 286*& 332* j/
WE LD LENGT H = 106.8" L lH I TAT 10 N = 13,7 " l
- /o t I MI T E D = 12.8 % STALE = 75
\WN FEEDWATER N0ZZLES N4A & D PEEDWATER NOZZLE EXAMINATION LIMITATIONS
1 Rev.1 Change O P;ge A-26 Cf 53 RELIEF REOUEST RR-A7 COMPONENT DESCRIPTION:
. Reactor Pressure Vessel (Control Rod Drives) all control rod drive and instrumentation nozzles. (240 nozzles total)
A8ME CODE CLASS Class 1 Subsection IWB, Table IWB-2500-1, Category B-E, ASME SECTION XI REQUIREMENTS:
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 intern)
BA51S FOR RELIEF: Due to the location of these components, these partial penetration walds 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 ensure the integrity of these components.
ALTERNATE EXAMINATION: A visual (VT-2) examination will be conducted from below th housing location under the vessel lower head during the system leakage test and the hydrostatic test performed once every ten years.
APPLICABLE TIME PERIOD: Rollef is requested for the first 120 month interval.
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ISI-NDE Pr; gram Rev.1 Change 0 ,
Page A-27 of 53 j l
RELIEF REQUEST RR-A4 ]
l COMPONENT DESCRIPTION:
Integrally Welded Attachments (Main Steam Piping Lugs)
Lus/ Weld ident FW-PS A4-GA1 FW-PS-2-A4-GA2 FW-PS-2-A4-GA3 FW-PS-2-A4-G A4 FW-PS-2-B4-O B 1 FW-PS-2-B4-OB2 FW-PS-2-B4-O B3 FW-PS-2-84-OB4 FW-PS-2-04-OC 1 FW-PS-2-C4-OC2 FW-PS-2-C4-OC3 FW-PS-2-C4-OC4 FW-PS-2-04-OD1 FW-PS-2-D4-O D2 FW-PS-2-D4-O D3 FW-PS-2-04-OD4 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 'ign 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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ISl-NDE Program Rev.1 Change O Page A-28 of 53 RR-A4 Cent'd 1
Access to the examination areas require the 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 enticipated due to inservice operation.
No atternative test methods are proposed at this time.
ALTEMNATE EXAMINATION:
However, should the support component be removed for any reason, the required exsmination will be conducted on the exposed lugs.
APPLICABLE TIME PERIOD: Rollet is requested for the first 120 month interval.
- = .
ISI-NDE Program Rev.1 ChangeO Page A-2g of 53 RELIEF REQUEST RR-AS-R1 COMPONI'.NT DESCRIPTION:
Integrally Walded Attachments (Piping Lugs)
FW-RS-2-A2-AL1 SW-RD-2-B2-W16 FW-RS-2-A2-AL2 SW-RD-2-B2-W17 FW-RS-2-A2-AL3 SW-RD-2-B2-W18 FW-RS-2-A2-AL4 SW-RD-2-B2-W19 SW-RD A2-W16 SW-RD-2-A2-W17 SW-RD A2-W18 SW-RD-2-A2-W19 ASME CODE OLASS Class 1 ASME SECTION XI REQUIREMENTS: Subsection lWB, 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 clasa 1 system bounderles. There are no support components associated with these lugs and the lugs are not required for any function. Examination of these lugs willincrease 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 la 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 Casa N-343, paragraph 2.0,
- Examination Category B-K-1, sub item (b), allows this exemption, ALTERNATE EXAMINATION: None proposed.
APPLICABLE TIME PERIOD: Rollef is requested for the first 120 month interval.
Cl-NDE PrTgram Mov.1 Change O Page A-30 of 53 REllEF REOUEST RR-A10 COMPONENT DESCRIPTION:
Integrally Wolded Atachments (Pipin9 t.ugs) Primary Containment Penetrations.
SW-E51-2192-X10-W2A SW-E21-3053-X16A-W2A SW-E51-2192-X10-W2B SW421-3053-X16A-W2B SW-E51-2192-X10-W2 C SW-E21-3053-X16A-W2C SW-E41-2297 .X11-W2A SW-E21-3519-X17-W2A SW-E41-2297-X11-W2B SW-E21-3519-X17-W2B SW-E41-2297-X11-W2C SW-E21-3519-X17-W2C SW-E11-2298-X138-W2 A SW-X7A-W2A SW-E11-2298-X13B-W2B SW-X7A-W2B SW-X7A-W2C SW-E11-2298-X13D-W2C SW-E11-2299-X12-W2 A SW-X78-W2A SW-X78-W2B SW-E11-2299-X12-W2B SW-X78-W2C SW-E11-2299-X12-W2C SW-E11-2327-X13A-W2A SW-X7C-W2A SW-E11-2327-X13A-W2B SW-X7C-W2B SW-E11-2327-X13A-W2C SW-X7C-W2C SW-E21-30$2-X16B-W2 A SW-X7D-W2A SW-E21-3052-X168-W2B SW-X70-W2B SW-E21-3052-X16B-W2C SW-X70-W2C SW-N21-2336-X9A-W2A SW-N21-2336-X9 A-W2B SW-N21-2336-X9A-W2C SW-N21-2336-X9B-W2A SW-N21-2336-X9B-W2B SW-N21-2336-X98-W2B ASME CODE CLASS:
Class 1 ASME SECTION XI REQUIREMENTS: Subsection (WB, Table IWB-2500-1 Category B-K-1, item D10.10, 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.
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031-hDE Prtgram Rev.1 Change 0 Page A-31 of 53 RR-A10 Cont'd BA518 POR RELIEF: Due to the design of the Primary Containment Penetration Assemblies, the contering lugs installed in the penetrations are not accessible far 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 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 N343, paragraph 2.0,
" Examination Category B-K-1, sub hem (B), allows this exemption.
ALTERNATE EXAMINATION: None proposed.
APPLICABLE TIME PERIOD: Rollef is requested for the: first 120 month interval.
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ISI-NDE Program Rev.1 Change O Page A-32 cf 53 RELIEF REQUEST RR-A11 COMPONENT DESCRIPTION:
-Integrelly Welded Attachments (Pumps)-
insulation Lugs Hanger Brackets Pump A:
Pump A:
SW-831-5365-PUMPA-WA SW-831-5365-PUMPA-WS SW-831-5365-PUMPA-WC Pump B:
PumpB: .
SW-B31-5365-PUMPB-WA SW-B31-5365-PUMPB-WB SW-B31-5365-PUMPB-WC ASME CODE CLASS:
Class 1 ASME SECTION XI REQUIREMENTS: Subsection lWB, Table IWB-2500-1, Category B-K-1, item 810.20, requires a surface 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 man-days for removal and replacement of insulation. ' The operating records of other
. plants do not show that pump lugs have a record of significant problems, in - /dition industry field data does not indicate that cast stainless steel pump casings era ,Jsceptible to service induced flaws. Also ASME Code Case N343, paragraph 2.0, " Examination Category-
- B-K-1*, sub item (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: Rollef is requested for the first 120 month interval.
m F
_-._ A - N __-- -.-___--_ _ __.-. -_ _.._ _ _ -- --- - ----- . - - e - - - - - -
. . . _ _ . _ _ _ _ . _ - _ _ _ _ _ , -~_ _ _ _ _ _ _ - _ . _ .
ISI-NDE Program .
'! Rev.1 Ch ngsO Page A-33 of 53 RELIEF REQUEST RR-As2 COMPONENT DESCRIPTION:
integrally Welded Atachments (Piping Lugs)
SW-E11-3146-2WE SW-E11-3158-1WC SW-E11-3158-2WM SW-E11-3158-1WD SW-E11-3158-2WN SW-E11-3146-2WF SW-E11-3158-1WE SW-E11-3158-2WO SW-E11-3146-2WG SW-E11-3158-1WF SW-E11-3158-2WP SW-E11-3146-2WH SW-E11-3158-1WG SW-E11-3158-2WO SW-E11-3146-2WJ SW-E11-3158-1WH SW-E 11-31ti8-2WR
' SW-E11-3146-2WK SW-N30-3259-10WB SW-E11-3158-5WC SW-E11-3146-7WG SW-N30-3259-10WC SW-E11-3158-5WD SW-E11-3146-7WH SW-N30-3259-10WD SW-E11 -3158-5WE SW-E11-314C-7WJ SW-f * ;-3146-7WK SW-N30-3259-10WE SW-E11-3158-5WF SW-N30-3259-10WF SW-E11-3158-5WG SW-E11-3146-7WL -
SW-N30-3259-10WG SW-E11-3158-5WH SW-E11-3146-7WM SW-N30-3259-10WH PSFW-E11-3146-255A . SW-N30-3259-10WJ SW-N30-3259-10WK SW-N30-3259-10WL SW-E21-3148-EXPJT-W8 SW-E11-3157-5WD SW-N30-3259-10WM SW-E21-3146-EXPJT-W9 SW-E11-3157-5WE SW-E11-3157-5WF SW-N30-3259-10WN SW-E21-3149-EXPJT-W8 SW-E11-3157-5WG SW-E21-3148-EXPJT-W9 SW-E11-3157-5WH SW-E11-3157-5WJ ASME CODE CLASS:
Class 2 Subsection (WC, Table IWC-2500-1, Category C-C, item ASME SECTION XI REQUIREMENTS:
C5.30, requires a surface examination of integrally welded attachments for piping.
Attachments whose base material thickness is 3/4" and greater will be exammed.
BASIS FOR RELIEF: Various abandoned fugs exist on piping components within the Class 2 system boundaries.. There are no support componefits 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.
'I
' 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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ISI-NDE Ptsgram Rev.1-Change O Pege A-34 of 53 RR-A12 Cont'd ALTERNATE EXAMINATION: No alternative examinettons are proposed at this time.
However, leakage testing will be conducted in accordance with Section XI, Category C-H, hem C7.30 and C7.40.
APPUCABLE TIME PERIOD: Relief is requested for the first 120 month Interval.
~. _. _ ._ . _ _ _ - - _ _ _ _ _ . . _ _ _
Rev.1 i
Change 0 Page A-35 cf 53 l i
i RELIEF REQUEST RR-A13 COMPONENT DESCRIPTION:
i Integrally Welded Attachments (Piping Lugs)
PSFW-E11-3146-148A PSFW-E11-3151-145A PSFW-E11-3146-1488 PSFW-E 11-3151-1458 PSFW-E11-3146-148C PSFW-E11-3151-145C
'SFW-E11-3146-148D PSFW-E11-3151-145D ASME CODE Ci. ASS Class 2.
ASME SECTION Cl REQUIREMENTS: Subsection IWC, Table IWC-2500-1, Category C-C, item
' C5.30, requires surface examination of integrally welded attachments for piping.
- Attachments whose base material thickness is 3/4' and greater will be examined.
BASIS FOR RELIEF:- Several pads installed on Class 2 piping are inaccessible for examination. The pads are located in floor penetrations and serve to restrict movement of the process pipe in the penetration Clearance between the welded pads and 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 structural change in the welds is anticipated due to operation.
ALTERNATE EXAMINATION: No alternative examinations are proposed at this time.
However, leakage testing will be conducted in accordance with Section XI, Category C-H,
. Item C7.30 and C7.40.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
I l
Cl-NDE Prcgram l Rev.1 Change 0 l Page A-36 cf 53
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ISI-NDE Program Rev.1 j Change 0 Pag) A-37 cf 53 RELIEF REQUEST A14 1
1 COMPONENT DESCRif' TION:
integrally Welded Attachments (Vessels) SW-E11-D2-PXS-08 ASME CODE CLASS:
l 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* end greater will be examined.
BASIS FOR RELIEF: The RHR Heat Exe. hanger 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 heat exchanger. Access to the weld area is obscured by structural steel. The weld is a fillet weld and as such not a full penetration weld. The fillet weld on the top side of the lower support ring (SW-E11-D2-HXS-07) will receive a sudace examination.
ALTERNATE EXAMINATION: No altomative examinations are proposed at this time.
However, the fillet welds on both sides of the top support ring, the stiffener plates connecting the top and bottom support rings, and the weld on the top side of the lower support ring will be examined in addition, leakage testing will be conducted in accordance with Section XI, Category C-H, item C7.10 and C7.20.
APPLICABLE TIME PERIOD: Relief is requested for the first 120 month interval.
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STRUCTURAL SUPPORT STEEL I
Cl-NDE Program Rev.1 ChangsO Page A-39 cf 53 THIS PAGE INTENTIONALLY LEFT BLANK l
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ISI-NDE Program Rev.1 Change O Page A-44 of 53 l THIS PAGE INTENTIONALLY LEFT BLANK i
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ISI-NDE Pr@ gram Rev.1 ChangeO Page A-46 of 53 l
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5.0 Program Support Drawings-5.1 Inservice inspection Classification Boundary Drawings The systems or portions of systems subject to the examination requirements of the ISI-NDE Program for Fermi 2 and the associated Class 1,2, and 3 l boundaries are documented on (Si Classification Boundary Drawings. The ISI ;
Classification Boundary Drawings, which forrr, a part of the (SI-NDE Program l are listed in Table A-5-5.1.
The system inservice inspection classifications, developed specifically to define the extent to which Section XI requirements will be applied, differ somewhat from the ASME Section ill design classifications. These differences occur because systems, or portions of systems, have been optionally upgraded in design and because ISI classifications are limited to safety related systems which contain water, steam, or radioactive materlats. NUREG 0800, Regulatory Guide 1.26, and 10CFR50 were the documents used in identifying these boundaries. +
5.2 Inservice Inspection (ISI) Isometric Drawings for Class 1 and 2 Components and their Supports The drawings contained in this manualidentit, the ASME Section XI, Class 1 and 2 isometrics which contain components subject to inservice inspection.
Drawing 6M721-2000-5 provides a listing of the piping !sometrics and associated code classifications. Drawings are updated to conform to as-built configuration of Plant following modifications.
C0v.1 i Change 0 P ge A-47 of $3 TABLE A-5-5.1 PERMI-2 ISI CLASSIFICATION BOUNDARY DRAWINGS PlS No's Associated ISI Dws. No, whh Dwg. Code Class Drewing Title 1
Nuclear Boller System SM721-5808-1 B21 1
6M721-5808-2 Main Steam isolation 6M721-5808-1 B21-06 1 2
Valve Leakage Control System 1
6M721-5808-1 B21 Maln and Reheat Steam 2 Systems tim 721-5822 H11/N30 B31 1 Reactor Recirculation 6M721-5809 System-Nuclear Boller System C11 2 Control Rod Drive 6M721-5810-1 2
System C11 2 CRD Scram Discharge 6M721-5810-2 System C41 1 Stand-By-Liquid Control 6M721-5811 2
System -
1 6M721-5813 E11 Residual Heat Removal 2 (RHR) Division i E11 1 Residual Heat Removal 6M721-5813-1 2
(RHR) Division 11-E11 3 RHR Service Water Make 6M721-5813-3 P45 3 Up Decent and Overflow 3 R30 Systems 1
6M721-5814 E21 Core Spray System - 7.
1 6M721-5815 E41 High Pressure Coolant 2 Injection System (HPCI) 1 6M721-5816 E51 Reactor Core Isolation Cooling System (RCIC) 1 Reactor '/ ator Clean-Up 6M721-5818 033 l
Cl-NDE Program Rev.1 Change O Page A-48 of 53 TABLE A-5-5.1 (Cont'd)
- PERMI-2 ISI CLASSIFICATION BOUNDARY DRAWINGS MS No's N sociated ISI Dwg.No. with Lug. Code Class Drewing Title 041 2 Fuel Pool Cooling end BM721-581g Clean-Up System 0 51 2 Torus Water Management 6M721-5820 System 1
Feedwater System 6M721-5821 N21 1
Sample Line Tie-in And 6M721-5824 P34 2
Return Post Accident Sampling System P44 3 Emergency Equipment 6M721-5825-1 Cooling Water Division i P44 3 Emergency Equipment 6M721-5825-2 Cooling Water Division 11 T48 2 (Post Loca) Combustible 6M721-5830-2 Oss Control System l
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F INDEX ISI SOMETRIC
~~
DESCRIPTION DRAWING NUMBER ISI CL ASS I 6M F21- 2000- 6 N0t t F 0H IN $t RVICE INS PE C TION ISOME TRIC S 6M721-2001-6 LEGEND 8 SYMBOLS FOR IN SE RYlC E IN SPEC TION ISOMETRIC g 6M?212192 5 RCIC STE AM LINE IN ORYWELL EM72F2297 5 HPCI STE AM LINE IN ORYWELL 6M72t+2298 5 Rtel RCTURN LINC Oly.l(NORTH) 6M72t 2299-6 RHR FROM REClRC PUMP SUCTION EMF 212327 6 RHR PETURN LINE DIV I!(SOUTH) s ,,, 6M7213062 S CORE SPRAY PIPING OlV l(NORTH)
EMF 21+30$3 6 CORE SPRAY PIPING OlV ll(SOUTH) 6M '21-3096 *S RE ACTOR WATER CLE AN UP SUCTION FROM THE RPV BOTTOM HE 6MF213 SIS 5 RHR Hi A0 SPRAY 6M721 3536 6 RE ACTOR FEEDWATER PIPING (NORTH) 0 6M7213537 6 RE ACTOR FEt0 WATER PIPIN0(SOUTH) 3 6M721 S=Ji S RE ACTOR WAf tR CLE AN UP SUCTION FROM THE RPV REClRC. LOOi k, CMF21 S352 6 MAIN STE AM LOW A 6M 721-S 353 -S MAIN STE AM LOOP O 6M726-6354 6 MA*N STE AM LOOA C 6MF2163SS S MAIN STEAM LOOP O 6M7216356 6 RE ACTOR RECIRC. LOOP & RING HE ADER 6M721 SSSP-S Rt ACTOR RECIRC. LOOP A PUMP SUCil0N 8 OlSCHARGE SMF215358 5 REACTOR Rit;lRC. LOOP 5 RINU HEADER 6M721-53SS S RE ACTOR RECIRC. LOOP 8 PUMP SUCTION 6 OlSCHARG(
C 4M7215360 5 RE ACYOR VtSSEL'l 6M F21 5341 6 RE ACTOR VE$$tL'2 6MP216362 5 REACTOR VESSEL *3 6M721-5363 5 REACTOR VES$tL%
6M721 S364 +6 fit ACTOR VtSSEL4
[
- 6M7215365 5 RR PUMP 'l ist CLASS 2 EM 721 2005 COMBUSTl0LE GAS CONTROL RETURN HE ADER TO TORUS ( Ol' s 6M 721 2097+ 5 COMBUSTiett G AS CONTROL RETURN HE ADER TO TORUS (Or CMF21-1979 S STAN08Y LIQU10 CONTROL EXPLOSIVE VALVES AND UNE TO C GMF213035 S RHR Hi A0 SPR AY FROM RETURN HE ADER TO ORYwtLL PENETS 6MF21 3i44 6 NCRTH CORE SPRAY R>MP DISCHARGE TO RPV 6M721 3445 6 NOR TH CORE SPRAv MtN, LOW-FLOW BY PASS 6 TEST LINE
- 6MF213846 6 RHR RETURN ( NORTH)FROM RHR HX TO ORTwtLL PENET h 6M F21-314 7 + S CORT SPRAY PUMo (SOUTH) OISCHARGE TO RPV PENET.
d 6MF2!-3446 S CORC SPR AY PUMP (NURTM) SUCTION FROM SU* PRE S S10N CH.
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j 6W7ts 547 9 HPCi PUWP bitCHAR at TO $7/tM RE ACTOR FttOt&f th HE AO(R 1 l
t 6Mftl 349 6 HPCI FRCW PVW8 DitCHARGE 10 CO*CENSatt STORAGL SYlitu 6WFFI Sif t 6 HPCI lit AW SUPPLt FROW 8tPV 10 HPCI TVRDINt STOP VAL %t
$U7tt-$f 77 6 RHR PUMP OttCHARot (90VtH) !
$Wiel Alte*l R**t tf RylCt W Af tli $UPPLY $ R[f yR9810 HRn (Olv tl 6W7tb32$9 b WalN $1t AW FROW ]MystLL 10 TURSINE MANIPOLO 6W7tb3f St 6 6t" WAIN Sit AW WatiFDLC 6 PtPING IN TURDINt $LOS 6W7ti SS66 6 $1 ANDf V LIQVl0 CthtROL PueAP $UCil0N 6MFtbl669 6 RnR SUPPLY Mt Abtit TO PPC SYttL W 5 731 44:1- 6 fitLif f LINE FROW ttHR HE AT thCHANGt h ($0UTHl 6Mftbenit 6 fltuf f LINC FROW hMR Ht AT (XCHANoth (NORTH)
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