ML20151U407
| ML20151U407 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/06/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20151U402 | List: |
| References | |
| (0326M), (326M), PROC-860206, NUDOCS 8602110012 | |
| Download: ML20151U407 (425) | |
Text
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. . BYRON NUCLEAR POWER STATION UNIT 1 INSERVICE INSPECTION AND TESTING PROGRAM PLAN let INSPECTION INTERVAL .
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e _ s , * . '. t, : , - .i. Revision la TABLE OF CONTENTS Byron Nuclear Power Station, Unit 1, Inservice Inspection and Testing Program, 1st Interval - Face Summa ry , iii Section 1.0 - Inservice Inspection and Testing Program Plan Introduction (Revistcn 1) 1-i l Table of Contents, Section 1.0 1-il Section 2.0 - Inservice Inspection Program Plan for Nondestructive Examination (Revision 1) 2-i Table of Contents, Section 2.0 '2-il Oc0hion 3.0 - Preservice/ Inservice Testing Program Plan for Purps (Revision 4 ) 3-i Table of Contents, Section 3.0 3-11 Section 4.0 - Preservice/I:servic'e Testing Program Plan for Valvec (Revision 5) 4-i Table of Contents, Section 4.0 4- ; 1 Oect ico 5.0 - Inservice Inspection Program Plan for Coeponent Supports (Revision 2) 5-i l Table of Conttats, Section 5.6 5-ii Section 6.0 - It ervice Ihrp+: tion and Tasting Progres Plan for Snubbers (Revi. ion 3) 6-i Table of Conten";, S-2ction 6.0 6-il (:32E:') 1
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. SIN ARY Inservice Inspection (ISI) of Class 1, Class 2, and Class 3 nuclear components in Unit 1 of Commonwealth Edison's Byron Nuclear.-Power Station will be performed in accordance with the requirements of the 1980 Edition and addenda through the Winter I981 Addenda of-Section XI of the ASME Boiler ~and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear power Plant Components".
This inspection and testing program de'acribes the areas to be examined, examination categories, examination methods, extent and schedules to be - e followed during the 1st ten-year inspcetion interval together'with operational testing requirements. The first 120-month inspection interval comtrenced with '
- the start of comercial operation
- on September 16, 1985.
- This document is a surmary of the Byron Unit 1 ISI Program. It~is being submitted to the Nuclear Regulatory Comission for approval in accordance with the requirements of 10 CFR 50.55a (g)(4)(i).
- The Coceercial Operation Date as defined by Federal Powcr Cornission l
(, regulations,18 CFR 101', Chapter 1, paragraph 9.D. , b e
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t-Revision la t SECTION 1.0 INSERVICE INSPECTION AND TESTING PROGRAM Pt.AN INTRODUv~IICfl I, 9 1-1 ( 0326:')
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'~Section 1.0 - ' Inservice Inspection and Testing Program ,
Plan Introduction. 1.1 ' General Information , 1-1 1.2' system Classification 1-3 9 4 e 4 1-il (0326M)
R:,vicion 1 e 4 4 1.1 GDERAL I!EORMATION e 1-1 (0326M)
l Revision la General Information The Inservice Inspection and Testing Program Plans for Byron Nuclear Power Station, Unit 1 are developed in compliance with the rules and regulations of Title 10, Part 50.55a of the Code of Federal Regulations, and Section XI,
" Rules for Inservice Inspection of Nuclear Power Plant Components" of the ASSE Boiler and Pressure Vessel Code,1980 Edition and addenda through the Winter 1981 Addenda. Where specific requircmcnts are determined to be impractical, '
relief has been requested.
. The Inservice Programs for Class 1, 2, and 3 components shall be applicable for a one hundred twenty (120) month interval coincident Fith the start of commercial' operation on September 16, 1985. The docket number for Byron Unit 1 is 50-454.
In add. tion to the ASME Section XI requirements for inspection, certain augmented inspections were requirel by the Nuclear Regulatory Commission. The
, augmented requirements include High Energy Lines, Reactor Coolant Pa.mp Flywheels, Steam Generator U-Tubes, and Turbine Rotors. The augmented requirements are included in these programs.
Revisions to the progrars presented herein ray be required due to design changes, NRC comments, identification of additiona* relief requests, etc. For instances where the revision involves the deletion of a component examination, in whole or in part, from the examination reguirerents of either the AST , Code or USNRC regulations, such rev:sion will require USNRC approval prior to imp'.er ntation. For instances where the revision involves the addition of a corr'r nt examination, in whole or in part, for exa-ination in accordance with th+ requirerents of either th- ASME Code or US'iC regulations, or where
' inforve. tion is aff+d for clartfication. such r./isions will be implerented w' thout prior USN' C apptov 1. If a minor char:Je is required which only affeels a sc+11 ntaber of pages, those pages may be revised by adding a, lo.-U ca; c*pte dt.ignator to the current ce /is s o: nt:mbc : . For exa ple. a pm, labc'c " Revision 1" wo.~d becoac " Revision la". The alpha de.ignator rei bc inca cc.cnt;d if oth+ r mirar chan;cs af fect that page. In th:s ca!4 the pag +
wouli be labile' " Revision Ib". When a change af fects a signi fi *rt nt. 'c r of pagc or sofficient m r.or changes have been made to warrart a co+pict+ revi< ion, t!e entir. section or sections affected will be revired. In thi:
. cast all pag +s will be revised by increr.:nting the n..r cieel revi s ien nu-P. t r and dropping all alpha deri.grators. Thus, if p>;c 1 was "4 eision 1" and page 2 was " Revision Id", both pages wo 1d now be "RE.irito 2" N ;e, each s+ction of the Inservice Inspection and Testing Pre,rs- Pla" :s revised separ3tely.
1-2 (0225M)
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1.2 SYSTDi CLASSITICAT,ICN e
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S .. , w: , ~- ; . Revision 1 System Classifications ! . Class 1 piping included'in the Reactor Coolant Pressure Boundary is defined by 10CFR50.2(v). Class 2 and 3 piping was classified by Sargent and Lundy Enginaering utilizing the guidelines of US NRC Regulatory Guide 1.26. All ASME piping is installed to the requirements of the ASME Boiler and Pressure vessel Code 1974 Edition and addenda through the Summer 1975 Addenda, Section III, " Nuclear Power' Plant Components". . Specific information with regards to individual component construction codes or materials can be found in the Byron /Braidwood Final Safety Analysis Report. e l i l l O t l l l-4 l (0326M)
- 4 R:vicion 1 6
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- SECTION 2.0 INSERVICE INSPECTICN PROGRAM PLAN FOR NCNDESTRUCTIVE EXAMINATION 4
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Revision la TABLE OF CONTENTS 2.0 Inservice Inspection Program Plan for Nondestructive Examination Page . 2.1 Program Description 2-1 2.2 Program' Tables , 2-3 2.3 Notes 2-7 Note 1 Reactor Vessel Shell Weld, Limited
\ Examination 2-8 Note 2 Class 1 Piping, Limited Examination 2-1S Note 3 Class 2 Compenents and Piping, Limited* .a Examination 2-16 s
Note 4 Main Steam No::le Inner Radii 2-17 , Note 5 Augrented - High Energy Piping 2-19 Note 6 Au;nsnted - Reactor Coolant Pump Flywheels 2-20 Note 7 Augmented - Turbine Rotor 2-21 Note S Integrally Welded Attachments 2-22 2.4 Exe.tpt Components 2-23
, -J 2.5 Eddy Current Inspection of Steam Generator U-Tubs 3 2-26 2.6 Inservice Inspection Isome.tric Dracin Js 2-23 2.7 Relit' Rcquests 2-33 NR-1 Reactor Vessel Shell Welds, Limit (d ,
Exani a'lon 2-34 .. NR-7. Reactor Vessel Hot Lcy Nor.:le- to-Vessel
- Welds, Limited E:.2.-in:tions 2-42 NP;3 Pressurizer and Stur? Cc nc e t.t c- (Primary Side) Nozzle Inner Rt.dii 2-46 NR-1 Steco Scncretor No7:le-to-Eltou, Limited Exaninetion (Cast 'teinless Steel) 2-47 NR-5 Reactor Coolcnt Piping-to-Pittings and Valves, Limited Exe '-n.t'on (Cast Stainics: Steel) 2-52 2-it (03 "
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. . ,. y Revision la Page NR-6 Reactor Coolant Piping, Fitting-to-Component, Limited Examination (Cast Stainless Steel) 2-59 NR-7 Reactor Vessel No::le Safe End-to-Elbow, Limited Examination (Cast Stainless Steel) 2-66 NR-S Reac.or Coolant Pump Internal Inspection 2-71 ER-9 Clase 1 Valve Internal Inspection 2-72 NR-10 Excess Letdown Heat Exchanger, Limited Examination 2-74 NR-ll Letdown Heat Exchanger, Limited Examination 2-73 NR-12 Steam Generator (Secondary Side) and Residual Heat Removal Heat Exchange No::le Inner Radii 2-80 NR-13 Centrifugal Charging Pump and Residual Heat Removal Pu.p, Inaccessible Attacb.nent Welds 2-84 NR-14 Deleted 2-87 NR-15 Safety Inje: tion. Pipe-to-Valve Weld Inside the Valve Containnent Assembly 2-83 1
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Revisica 1 2.1 PROGRAM DESCRIPTICf! G 4 2-1 (0326M) 1
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R3visica 1 Program Description The Inservice Inspection Program Plan for Nondestructive Examination (NDE) of Class 1, 2, and 3 components is implemented in accordance with the requirements and intent of Subsections IWA, IWB, IWC, and IWD, Section,XI, Division 1 of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1981 Addenda. The NDE program developed herein will utilize Inspection Program B, (IWA-2420), Tables IWB-2412-1 and IWC-2412-1 for the first 120 month inspection interval. Where these requirements are determined to be impractical, specific requests for relief have been written. These are referenced i:ithe applicable NDE program tables and included under subsection 2.7 of this program. Note, relief has been requested for selected components / welds. If additional relief is required, it shall be requested at-a later date. Sub'section 2.2 contains the NDE program tables. These tables are presented in a tabular format consistent with the Section XI examination requirement tables. The NDE program tables include the corresponding code category, item number, and component / weld selection in conformance with Inspection Program B, ASME Section XI, 1980 Edition through the Winter 1981 Addenda. Per 10 CFR 50.55a(b)(2)(iv), Class 2 portions of Emergency Core Cooling Systems (ECCS), Containment Heat Removal Systems, and Residual Heat Removal Systems were selected / exempted based upon the 1974 Edition through the Summer 1975 Addenda of ASME~Section XI. Also included are tables which address Alternate and Augmented Examinations. Alternate examinations are those additional examinations which are referenced in Relief Requests. Augmented examinations include the Reactor Coolant Pump Flywheels, High Energy lines, and Turbine Rotor inspections as required by the Byron /Braidwood Fit'al Safety Analysis
- Report (FSAR). .
Subsection 2.3 contains Notes applicable to the, program tables. Notes are employed in order to convey positions and/or' interpretations of Section XI requirements. Notes'are referenced under the remarks column for.each applicable component / weld affected. ' Code exemptions for ASME Class 1, 2, and 3 components are tabulated under Subsection 2.4. Component numbers, appropriate Piping and' Instrumentation i- Drawing numbers, applicable ASME Section XI exemptions and technical justification for each are presented, i 'Since ASME Section XI requires Steam Generator tubes be inspected in accordance with Plant Technical Specifications, Subsection 2.5 of this program addresses the program for Steam Generator tubing. This program meets the requirements of current plant Technical Specifications and USNRC Regulatory i Guide 1.83, Revision 1, " Inservice Inspection of Pressurized Water Reactor Steen Generator Tubes". Subsection 2.6 contains copies of the Eyron Unit 1 Inservice Inspection Isometric Drawings which have been developed for all vessels, piping, pumps and valves which require volumetric and/or surface examination by this program.
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Ravicion 1 Program Tables The following tables correspond to the format of those presented in ASME Section XI. Subsections IWB. IWC, and IWD. These tables contain the following information: PAGE of : is the c>nsecutive and total page numbers for the NDE tables. , REVISION: is the revision number of Section 2.0 of the Inservice Inspection and Testing Program. Note, if the Revision number is followed by a lower case alpha designator, this page has been revised but the overall Section was not. SYSTDf: refers to the component (s) and/or system (s) being addressed. CODE CATEGCRY: is the Examination Category as defined by ASME Section XI, Subarticles IWB-2500, IWC-2500, or IWD-2500. ITEM NO.: lists the Item No. as defined by ASME Section XI, Subarticles IWB-2500, IWC-2500 or IWD-2500. Note, all Item No.'s are addressed. PARTS EXAMINED: lists the title for the Item No., the equipment noun name, or system noun name as applicable. COMPCNENT DESCRIPTION: is the equipment part -number or line number for the corresponding component / system being addressed. The total number of items for each component are listed in parenthesis below the description. ISI ID: lists the individual identification number assigned to the component / weld. In addition, fie1<1 weld (W) numbers may appear under the assigned ISI weld number as applicable. P & ID: identifies the applicable Piping and Instrumentation Drawing for the component / weld. ISO DRAWING: identifies the applicable Inservice Inspection Isometric Drawing for the component / weld. EXAM METHOD VOL/SUR/VIS: identifies the nondestructive examination method (s) to be performed on the component /we!i as defined by ASME
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Section XI or Augmented requirements. ID SEL: identifies those component (s)/ weld (s) selected for examination during the first inspection interval. The following list of alpha designators is employed to designate the type of selection made: a- Mandatory Selection: component (s)/ weld (s) required by the applicable Item No. for examination during the first inspection interval. 2-4 (0326M)
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R: vision 1 b- Terminal End: extremities of piping runs that connect to structures, components (such as vessels, pumps, and valves), or pipe anchors each of which act as rigid restraints or provide at least two degrees of restraint to piping thermal expansion. c- High Stress: terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following' limits under loads associated with specific seismic events and operational conditions:
- 1) p' rimary plus secondary stress intensitf range of 2.4Sm for ferritic steel and austenitic steel:
- 2) Cumulative usage factor (U) of 0.4.
d- Dissimilar Metal: welds between combinations of:
- 1) carbon or low alloy steels to high alloy steels:
- 2) carbon or low alloy steels to high nickel alloys:
- 3) high alloy steels to high nickel alloys.
e- Class 2 EmergenIcy Core Cooling Systems, Containment Heat Removal Systems, and Residual Heat Removal Systems: component / weld selections based upon ASME Section XI, 1974 Edition through Summer 1975 Addenda In addition, the following numeric designators will be used following the alpha designator:
- 1) circumferential butt welds at structural discontinuities *:
- 2) circumferential butt welds in piping within 3 pipe diameters of the centerline of rigid pipe anchors, or anchors at penetrations of the primary reactor containment, or at rigidly anchored components:
- 3) branch connection weld joints:
- 4) longitudinal weld joints in pipe fittings (i.e., in tees, elbows, or reducers):
- 5) pump casing and valve body weld joints, f- Main Steam System 8 in. Nominal pipe Size and Smaller:
additional welds at structural discontinuities
- such that the total number of circumferential welds selected for examination equal 10% of the total welds in main steam piping 8 in. nominal pipe size and smaller.
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R; vision 1 g- Balance of Class 2 Piping: additional welds at structural discontinuities *, such that the total number of circumferential
-welds (or branch connection, or socket welds) selected for examination equal 25% of the total number of circumferential welds (or branch connection or socket welds) in each Class 2 System.
h- . Reactor Coolant Piping: additional circumferential butt welds-(or bianch connection or socket welds) such that the total number of circumferential butt welds (or branch connection or socket. welds selected for examination equal 25% of the circumferential-butt welds (or branch connection or socket welds) in the reactor coolant piping system. j- Longitudinal Welds: intersecting longitudinal welds at circumferential welds selected for examination.
- Structural discontinuities are pipe weld joints' to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc. conforming to ANSI.B16.9) and pipe branch connections and fittings.
PERIOD 1st/2nd/3rd: to be completed by the station in order to schedule selected (ID SEL) examinations during the first inspection interval'and thus meet the requirements of Inspection Program B. REMARKS: additional information and/or identification of Notes and/or Relief Requests. f i 2-6 (0326M) m
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PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 134 OF 407 ,
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1 i- - (00290) - i-PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 229 OF 407 i
- EBASCO SERVICES INCORPORATED --
REVISION 1 . i SYSTEM: CODE CATEGORY: B-L-1, B-M-1 Residual Heat Removal B-L-2, B-M-2 (CONT) . ! ITEM COMPONENT ISI ISO EXAM METHOD ID ' PERIOD I' NO. PARTS EXAMINED DESCRIPTION ID P&ID DRAWING VOL SUR VIS SEL 1st 2nd 3rd REMARKS { B12.50 Valve Body, Exceeding 3 4 in. Nominal Pipe f Size (Cont) [ Residual Heat 1RH-1-ISI
. Removal IRH8701-A M062-1 2 of 9 VT3 a Relief Request NR-9 l
!- 1RH8701-B N062-1 2 of 9 VT3 - l ! 1RH8702-A M062-1 1 of 9 VT3 a Relief Request NR-9 i
'1RC-1-ISI ; 1RH8702-B M062-1 11 of 42 VT3
' e 4 9 5 9 i 4 l
tuussus , il y. PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 230 OF 407 :
^ REVISION 1 EBASCO SERVICES INCORPORATED SYSTEM: CODE CATEGORY: B-L-1, B-M-1 -
Safety Injection B-L-2, B-M-2 (CONT) f ITEM COMPONENT ISI ISO EXAM METHOD ID ' PERIOD NO. PARTS EXAMINED DESCRIPTION ID P&ID DRAWING VOL SUR VIS SEL Jst 2nd 3rd REMARKS i B12.50 Valve Body, Exceeding , 4 in. Nominal Pipe i Size (Cont) ISI-1-ISI
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[ ISI8808D-1 M061-6 13 of 33 VT3 ISI8818A M061-4 3 of 33 VT3 a Relief Request NR-9 ISI8818B M061-4 6 of 33 VT3 i i 1SI8818C M061-4 10 of 33 VT3 f ISI8818D M061-4 14 of 33 VT3 1 ISI8841A M061-3 2 of 33 VT3 a Relief Request NR-9 i 1SI8841B M061-3 11 of 33 VT3 i I I l l t t t i
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i PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 232 OF'407-- _ _ _ p
" ^ REVISION 1 i EBASCO SERVICES INCORPORATED - - -
SYSTEM: CODE CATEGORY: B-N-1, INTERIOR OF REACTOR VESSEL t Ructor Pressure Vessel B-N-2, INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTAC104ENTS TO REACTOR : VESSEL B-N-3, REMOVABLE CORE SUPPORT STRUCTURES { ITEM COMPONENT ISI ISO EXAM METif0D ID PERIOD 'j NO. PARTS EXAMINED DESCRIPTION ID P&ID DRAWING VOL SUR VIS SEL 1st 2nd 3rd REMARKS [ Reactor Vessel. , l B13.10 Vessel' Interior IRC-01-R All M060-1 1RPV-1-ISI VT3 a - i i Reactor Vessel (BWR) B13.20 Interior Attachments k Within Beltline Region ! N/A None B13.21 Interior Attachments ' Beyond Beltline Region N/A None i B13.22 Core Support Structure N/A . None f i Reactor Vessel (PWR) ~ B13.30 Interior Attachments IRC-01-R All M060-1 RPV-1-ISI VT1 a Structure shall be Within Beltline Region removed for Inspect. I B13.31 Interior Attachments 1RC-01-R All VT3 I Structure shall be Beyond Beltline Region removed for Inspect. ! i B13.32 Core Support Structure IRC-01-R All VT3 f i f a t I i 1 4 a ___ A____
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PROJECT: CEEo BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 234 OF 407_ I'
^
EBASCO SERVICES INCORPORATED REVISION 1 , SYSTEM: Reactor Vessel, CODE CATEGORY: B-P, ALL PRESSURE RETAINING COMPONENTS i Pressurizer Vessel, and Steam Generators ( t ITEM COMPONENT' ISI ISO EXAM METHOD ID PERIOD ! NO. PARTS EXAMINED DESCRIFTION ID P&ID DRAWING VOL SUR VIS SEL 1st 2nd 3rd REMARKS i Reactor Vessel . l l B15.10 Pressure Retaining 1RC-01-R All M060-1 1RPV-1-ISI VT2 a System Leakage Test j
. Boundary IWB-5221 [
i B15.11 Pressure Retaining 1RC-01-R All VT2 a System ifydrostatic i Boundary Test, IWB-5222 l l Pressurizer Vessel ;- t B15.20 Pressure Retaining 1RY-01-S All M060-5 IPZR-1-ISI VT2 a System Leakage Test Boundary IWB-5221 f3 6 B15.21 Pressure Retaining 1RY-01-S All System liydrostatic ! Boundary . Test, IWB-5222 .! [~ Steam Generators .' i B15.30 Pressure Retaining ISG-1-ISI { Boundary 1RC-01-BA All M060-1 1 of 4 VT2 a System Leakage Test, I 1RC-01-BB All M060-2 2 of 4 VT2 a IWB-5221 ! 1RC-01-BC All M060-3 3 of 4 VT2 a j 1RC-01-BD All M060-4 4 of 4 VT2 a i
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B15.31 Pressure Retaining IRC-01-BA All M060-1 1 of 4 VT2 a System Hydrostatic Boundary 1RC-01-BB All M060-2 2 of 4 VT2 a Test, IWB-5222 j 1RC-01-BC All M060-3 3 of 4 VT2 a 1RC-01-BD All M060-4 4 of 4 VT2 a l l !
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!- Piping: Class 1 Portions B-P,.(CONT)
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PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 240 OF 407 EBASCO SERVICES INCORPORATED REVISION la SYSTEM: Chemical & Volume CODE CATEGORY: 1 Control C-A, (CONT) } t' ITEM COMPONENT ISI ISO EXAM METHOD ID PERIOD I NO. PARTS EXAMINED DESCRIPTION ID P&ID DRAWING VOL SUR VIS SEL 1st 2nd 3rd REMARKS [ C1.20 Head Circumferential I Welds f l Volume Control ICV-01-T VCTC-01 M064-4 IVCT-1-ISI X a Tank l (2) VCTC-02 X , a Sealwater Return ICV-02-F SWRFC-01 M064-3 ISWRF-1-ISI X a :. Filter (1) ; i Reactor Coolant ICV-03-F RCFC-01 M064-5 ISWRF-1-ISI X a ; Filter (1) - t Regenerative lleat ICV-03-AA RGXC-01 M064-5 1RGX-1-ISI X a > Exchanger (6) RGXC-02 X a l RGXC-03 X a I RGXC-04 X a $ RGXC-05 X a j RGXC-06 X a > i i f ICV-03-AB RGXC-01 X f (6) RGXC-02 X j RGXC-03 X < RGXC-04 X i, . RGXC-05 X : RGXC-06 X : l 4 l l
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PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 241 OF 407 [ EBASCO SERVICES INCORPORATED
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PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 247 OP 407 i EBASCO SERVICES INCORPORATED - REVISION 1
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SYSTEM: Main Feedwater CODE CATEGORY: i '. C-C, (CONT) ~ ITEM COMPONENT ISI ISO EXAM METIIOD ID PERIOD ! NO. PARTS EXAMINED DESCRIPTION ID P&ID DRAWING VOL SUR VIS SEL 1st 2nd 3rd REMARKS h Piping f t C3.20 Integra1ly WeIded' l-Attachments IFW-1-ISI {- Main Feedwater 1FW87CA-6 C4 M036-1 11 of 12 X a ' (2)
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PROJECT: CECO BYRON UNIT 1 INSERVICE INSPECTION PROGRAM PAGE 294 OF 407 I. 1
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