Text

Connecticut Yankee Third 10-Yr Interval Inservice Insp Plan Summary Submittal
	ML20234C955
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1987
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20234C913	List: B12577, Forwards Connecticut Yankee Third 10-Yr Interval Inservice Test Pump & Valve Program Submittal & ...Inservice Insp Plan Summary Submittal, for Third 10-yr Insp Interval Commencing on 880101.Fee Paid; ML20234C914; ML20234C955; ML20266H852; ML20266H855; ML20266H858; ML20266H861; ML20266H863; ML20266H866;
References
	PROC-870630-01, NUDOCS 8707070039
	Download: ML20234C955 (101)
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l CONNECTICUT YANKEE .O' INSERVICE INSPECTION PROCRAM SUBMITTAL REVISION ABSTRACT This document describes the basis for the third ten-year interval for l l the: Inservice Inspection Program'at Connecticut Yankee, commencing L ~ January 1, 1988. This submittal incorporates revisions to'the inservice inspection program as described in the ASME Boiler and Pressure Vessel- -(B&PV). Code, Section XI, 1983 Edition, with Addenda through the Summer of 1983. Pursuant to 10CFR50.55a(g)4(11), Connecticut Yankee is committed to revising the inservice inspection program for successive 120-month intervals to comply with the latest edition and Addenda of.the Code incorporated by reference in 10CFR50.55a(b)2. 1 Included in this submittal are Relief Requests and tables identifying all items subject to examination by Code Category and Code item Number. O O re47/7422

TABLE OF CONTENTS df~ -- Cover Sheet with Approvals -- Abstract -- Table of Contents -- List of Tables

1.0 INTRODUCTION

1.1 General z 1.2 Applicable Editions and Addenda to Section XI 1.3 System Classification 1.4 Intervice Inspection Program j l

2.0 DESCRIPTION

OF THE INSPECTION PROGRAM ] 2.1 Class 1 Systems 2.1.1 ASME Code Exemptions Employed 2.1.2 Component Examination Development 2.1.3 Steam Generator Eddy Current j 2.1.4 Class 1 System Pressure Tests I 2.2 Class 2 Systems q 2.2.1 ASME Code Exemptions Employed V 2.2.2 Component Examination Development 2.2.3 Augmented Inspection Requirements 2.2.4 Class 2 System Pressure Tests ] 2.3 Class 3 Systems 2.3.1 ASME Code Exemptions _ Employed 2.3.2 Piping Systems 2.3.3 Class 3 System Pressure Tests 2.4 ASME Class 1, 2, and 3 Component Supports 2.4.1 ASME Code Exemptions Employed 2.4.2 Class 1 Component Supports 2.4.3 Class 2 Component Supports 2.4.4 Class 3 Component Supports 2.4.5 Mechanical and Hydraulic Snubber Inspections j 3.0 RELIEF REQUESTS 3.1 General 3.2 Completed Relief Requests j (( re47/7422 j

'l i 1 4.0 EVALUATION CRITERIA 4.1 Class 1 Acceptance Standards j 4.2 Class 2 Acceptance Standards J 4.3 Class 3 Acceptance Standards i 4.4 Acceptance Standards for Supports (Class 1, 2, and 3) 5.0 SUBMITTAL

SUMMARY

] 1 5.1 Description of the ISI Program Format { 5.2 Summary Submittal Tables 6.0 RECORDS AND DATA MANAGEMENT 7.0 FIGURES AND ATTACHMENTS 7.1 Figurec 7.1.1 System Boundaries 7.2 Attachments 7.2 Table A Class 1 Components Inservice Inspection Summary 7.2 Table B Class 2 Components Inservice Inspection Summary 7.2 Table C Class 3 Components Inservice Inspection Summary 7.2 hn Table D Class 1, 2, and 3 Component Support Summary Table 7.2 Table E Augmented Inservice Inspection Program 7.2 Table BCD-5000 System Pressure Tests re47/7422

i l RECORD OF REVISIONS This Section will identify subsequent revisions to the ISI Program which will require NRC notification. j l l l 1 l l k i i i O re47/7422

i Il LIST OF TABLES ~ LO-Inservice Inspection Program Summary Tables located in Attachment 7.2. ' Table A. Class;1 Components Inservice Inspection Summary ] j Table B. Class 2 Components Inservice Inspection Summary-J =1 . Table C. Class 3. Components Inservice Inspection Summary, Table D. Class 1, 2, and 3 Inservice Component Support Inspection Summary. - ') Table E. Augmented Inservice Inspection Program Table BCD-5000. System Pressure Tests I O q 1 i i -l O re47/7422

1.0 INTRODUCTION

O-1

'1.1 General This submittal describes the Connecticut Yankee third ten-year inservice inspection program plan. The plan, which consists of ASME Code Class.1, 2, and 3-components.(and their supports), pumps and valves,'and system pressure tests, has been developed by giving due' consideratir to the following' documents: o 10CFR50.55a ASME ' Code' Section XI,1983 Edition, with ' Addenda through o .the Summer of 1983 ASME Code Section XI, 1974 Edition, with Addenda through o the Summer'of 1975 o AShE. Code Section V USNRC Regulatory Guides: o Regulatory Guide 1.14, Rev. 1, August 1975 Regulatory Guide 1.26, Rev. 3, February 1976 Regulat'ory Guide 1.83, Rev. 1. July 1975 Regulatory Guide 1.147, Rev. 4, September 1985' Regulatory Guide'1.150, Rev. 1, February 1983. I J O Connecticut Yankee Technical Specifications o o ASME Code Case N-278 1 1.2 Applicable Editions and Addenda to Section XI A) Pursuant'to Title 10 of the Code of Federal Regulations,: Part 50, Parahraph 50.55(a), the inservice inspection requirements applicable to nondestructive examination. system pressure tests, and inservice testing of pumps and valves at Connecticut Yankee are based upon,the rules set forth in the 1983 Edition of ASME Section XI and Addenda through the Summer of 1983. l B)' As permitted by Paragraph 50.55a(b)2(ii),- the extent of examination of ASME Code Class 1 piping (applies.to Table IWB-2500 and IWB-2500-1 and Category B-J) will be determined by the requirements of Table _IWB-2500 and Table IWB-2600, Category B-J of Section XI of the ASME Code in the 1974 Edition and Addenda through the 1 Summer 1975. C) As required by Paragraph 50.55a(b)2(iv)A, the extent of. examination'of appropriate ASME Code' Class 2 pipe welds in Residual Heat Removal' Systems, Emergency Core Cooling Systems, and Containment Heat Removal Systems shall be determined by the requirements of Paragraph IWC-1220 Table IWC-2520, Category C-F and C-G'and' Paragraph IWC- ~ re47/7422 l

-y '- 1 i ,J 2411 in the 1974 Edition and Addenda through the Summer-1975 of.Section XI of the ASME Code. D) As permitted by Paragraph 50.55a(b)2(iv)B, the extent'of- ] examination for Code Class 2 piping welds will be deter-mined by the' requirements of Paragraph IWC-1220, J Table IWC-2520 Category C-F'and C-G.and Paragraph IWC- ) 2411 in the 1974 Edition and Addenda through the ' ] Summer 1975 of Section XI of the ASME Code. E) As permitted by Paragraph 50.55a(g)(4), Connecticut .] Yankee may elect, for certain components, to meet supple-mental requirements as set forth in the Editions and Addenda of the ASME Code which become effective subse-quent to the 1983 Edition through the Summer 1983 Addenda of ASME Section XI. Other editions and addenda of ASME Section XI or ASME Code Cases that are' adopted will be j identified-in the appropriate sections of this inspection program. It is.the intent of Connecticut Yankee to -{ continually apply appropriate changes of the Code, with NRC approval, which improve the overall quality of the Connecticut Yankee Inservice Inspection Program. 1.3 System' Classification 1.3.1 The commercial operating license for Connecticut O Yankee was issued on January 1, 1968. The con-struction permit was issued in February 1964. 1.3.2 Vessels, piping, pumps, and valves were built and installed according to the rules of ASA B31.1.0, ' 3 Nuclear Design and Examination 1(NDE)' methods. Acceptance standards in accordance with~ASME Boiler and Pressure Vessel Code, Section.VIII. 1 1.3.3 The system classifications used as a. basis for the inservice inspection program are based on the requirements of 10CFR50 and Regulatory Cuide 1.26. 1.3.4 System boundary diagrams are provided to show the specific boundaries for the Class 1, 2, and 3 systems. From these boundaries, the inservice-inspection program has been' developed. 1.4 Inservice Inspection Program Examinations for the ten-year interval will be scheduled in accordance with Inspection Program B, as described in IWA-2400~ of ASME Section XI, for all Class 1, 2, and 3 components and ~ supports. O-re47/7422

2.0 DESCRIPTION

OF THE INSPECTION PROGRAli ("l The following is a detailed description of the inspection program i basis for each component / system to be examined. 1 2.1 Class 1 Systems l The Class 1 system boundaries have been developed based upon j the requirements of 10CFR50.2(v) and the Connecticut Yankee 1 Technical Specifications. The components / systems to be i examined in the Class 1 systems are described in detail below. Refer to Section 7.2, Table A of this submittal for the Inspection Summary of Class I components. d 2.1.1 ASME Code Exemptions Employed IWB-1220 - The following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWB-2500: Component connections, piping, and associated o valves of one-inch nps and smaller, except for steam generator tubing. 1 o Reactor vessel head connections and associated l piping, two-inch nps and smaller, made r ( inaccessible by control rod drive penetrations. 2.1.2 Component Examination Development ) A) Reactor Pressure Vessel (RPV) and RPV Closure Head Examination of the Connecticut Yankee RPV and closure head will be conducted in accordance { with Table IWB-2500-1 of ASME Section XI. l Refer to Relief Requests 3-1, 3-2, and 3-7 for areas not examinable. The RPV examinations will be performed to meet the intent of the requirements of Regulatory Guide 1.150 and ASME Section XI. Ultrasonic examinations will be in accordance with Figures IWB-2500-1, -2, -3, -4, -5, and -7 and Code Case N-278. B) Steam Generators (Primary Side) Examinations are performed in accordance with Table IWB-2500-1. Refer to Relief Requests 3-3, 3-5, and 3-8 for areas not examinable. Connecticut Yankee is a four-loop pressurized water reactor with four steam generators. Where applicable, as permitted by the Code, re47/7422

i n only the items on steam generator no. 4 will be fy) examined. C) Pressurizer All examinations are performed in accordance with Table IWB-2500-1. Refer to Relief Re-quest 3-5 for areas not examinable. D) Reactor Coolant Pressure Boundary Piping j Weld examinations are performed in accordance j with the requirements of ASME Section XI, 1983 Edition, with Addenda through the Summer of 1983. As referenced in Section 1.2(B), the ) extent of examinations for Category B-J welds { is in accordance with ASME Section XI, 1974 I Edition, with Addenda through the Summer of 1975. Twenty-five percent of the total number of welds selected for examination will be examined during the third inspection interval. i Specific items that cannot be examined to the j extent required by ASME Section XI will be j identified in the NIS-1 report submitted in j accordance with ASME Section XI, Article 1 p IWA-6000, v q The arrangements and details of the piping systems and components are such that some examinations are limited due to geometric j configuration or accessibility. Additionally, the arrangements and details of the Class 1 piping system and components were designed and j fabriented before the examination requirements of Section XI of the Code were formalized and j again, some examinations are limited or not practical due to geometric configuration or i accessibility. Generally, these limitations exist at all fitting to fitting welds such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface con-ditions preclude ultrasonic coupling or access for the required scan length. The limitations exist to a lesser degree at pipe to fitting welds, where examination can only be fully per-formed from the pipe side, the fitting geometry limiting or even precluding examination from the opposite side. No effort has been made to identify individual welds in the ten-year plan where such restrictions exist. Welds having such restrictions will be examined to the extent practical, re47/7422 E) Pressure Retaining Welds in Pumps and Valves Welds are selected for examination in accor-i dance with Table IWB-2500-1. Refer to Relief Requests 3-9 and 3-10 for areas not examinable. As required by Regulatory Guide 1.14, the bore and keyway areas of each of the four reactor coolant pump flywheels will be examined ultra-sonically, once each period. Additionally, the flyvheels receive a 100 percent ultrasonic examination and a surface examination once during the interval. 2.1.3 Steam Generator ECT Examinations j i The steam generator tubing surveillance' requirements are contained in the Connecticut Yankee Technical Specifications. The surveillaue requirements are based upon the modification of Regulatory Guide 1.83, Rev. 1, and previous eddy current examination results. j 2.1.4 Class 1 System Pressure Tests A) System pressure tests are conducted on Class 1 /~h systems and components as required by (> Table IWis-2500-1, Examination Category B-P. B) A system leakage test and a system hydrostatic test is performed in accordance with IWB-5221 and IWB-5222, respectively. C) The system boundaries subject to system leakage and system hydrostatic tests, as well as the test program, are included in the Inservice Inspection Program. The test requirements are identified in Section 7.2, Table BCD-5000 of this submittal. 2.2 Class 2 Systems The Class 2 system boundaries were based upon the requirements of Regulatory Guide 1.26 and the Connecticut Yankee Technical Specifications. Refer to Section 7.2, Table B, of this submittal for the inspection summary of Class 2 components. re47/7422

4 4' i q 6-y, 2.2.1 ASME Code Exemptions Employed IWC-1220 - The following components (or parts of compon'ents) are exempted from the_ volumetric and surface examination requirements of_IWC-2500: ) o Componento of systems or portions of systems that during normal' plant operating' conditions I are.not required.to operate or perform a system-function but remain flooded under static conditions at a pressure of at least 80 percent-of the pressure _that the component or system, will be subjected to when required to operate.- o 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'F.. J Component connections'(including nozzles in. o vessels and pumps), piping and associated-valves, and vessels and their: attachments that are four-inch nominal pipe size and_ smaller. 1 2.2.2 Component Examination Development

'i O

A) Steam Generators (Secondary Side)- ) All volumetric examinations will be performed l in accordance with Table IWC-2500-1 of ASME Section XI. Refer to Relief Request 3-12'for areas not examinable. B) Residual Heat Exchangers l All examinations will be performed in_accor - ~ dance with Table IWC-2500-1. Refer to Relief Requests 3-11 and 3-12 for areas not examinable. C) Piping Examination Requirements Weld examinations are performed in accordance with the requirements of ASME Section XI, 1983 Edition, with Addenda through the Summer of4 1983. As referenced in Sections 1.2(C) and (D), the extent of examinations for Catego-ry C-F welds is in accordance'with'ASME' Section XI, 1974 Edition,.with Addenda through the Summer of 1975. The 74 Code references: Category C-G welds, the 83 Code has incorporat-ed the Category C-G requirements into the Category C-F requirements. re47/7422

a i 1 - The following' describes the extent.of examina-h tion for Category.C-F welds of each Class 2 system, based on system, pipe size and multiple-stream concepts. The total number of welds of each stream have i been identified. The average number of welds per stream and the percentage of welds required to be examined have been identified. The scheduled welds are based on the above'percen. I tage requirements. Residual Heat Removal System Item No.: C5.11 There are two streams or. loops for the RHR suction and discharge piping (A and B). There are also single stream lines which are listed separately. Twenty-five percent of-the total number of welds will be examined during the third inspection interval. Multiple Stream Welds Suction Total Number - Scheduled Piping Pipe Diameter (25%) A 15-10" 2 B 2-10" 1 average per stresm = 8.5 welds 25% 2,1-A 18-8" 2 B 23-8" 3 average per stream = 20.5 ,25% - 5.1 Discharge Piping A 30-8" 4 B 29-8" 3 average per stream = 29.5 25% = 7.375 Single Stream Welds Suction Piping 3-18" 1 26-10" 8 6-8" 2 O re47/7422 Discharge Piping 34-10" 9 18-8" 4 8-6" 2 Core Deluge System Item No.: C5.11 There are two streams or loops for the core deluge piping (A & B). There are also three welds that will be. considered single stream and listed separately. Twenty-five percent of the total number of welds will be examined during the third inspection interval. j Multiple Stream Welds Total Number - Scheduled Pipe Diameter (25%) A 20-6" 2 B 19-6" 3 average per stream = 20.5 25% = 5.1 ) Single Stream Welds ( 3-8" 1 \\ Chemical and Volume Control System l Item No.: C5.11 There are two streams or loops associated with the CVCS piping (A & B). There are also single stream velds which will be listed separately. Twenty-five percent of the total number of welds will be examined during the third inspection interval. Multiple Stream Welds Total Number - Scheduled Pipe Diameter (25%) A 11-6" 1 B 7-6" 1 average per stream = 9 25% = 2.25 Single Stream Welds 12-6" 3 re47/7422

9-High Pressure Safety Injection System 1 O u Item No.: C5.11 There are two streams or loops associated with:. the HPSI discharge system.(A & B). There are. also single stream welds which will be listed-separately. Twenty-five percent of the total number'of welds will be examined during.the q 9 third inspection interval. Hultiple Stream Welds ' Total Number - Scheduled' Pipe Diameter (25%) A 16-6" 2-B 18-6" 2 average per stream.= 17 25% = 4.25 Single Stream Welds 12-8" 3 j 6-6" 2 Low Pressure Safety Injection System Item No.: C5.11 1 There are two streams or' loops associated with 1 the LPSI discharge system.. There are also ) single stream welds which will be listed separately. Twenty-five percent of the total! number of welds will be examined during the-third inspection interval. Multiple Stream Welds Total Number - Scheduled i Pipe Diameter (25%) A 12-10" 1 B 13-10" 2 average per stream = 12.5 25% = 3.1 Single Stream Welds 5-10" '2 1 0: re47/7422

1 I ] I I Main Steam SystemL -i 'O There are four loops ~or streams associated with the MS system (A, B, C & D). Per the 74 Code, this system is considered a Category C-G system. The 83 Code has incorporated this system into Category C-F. As referenced in Section 1.2(D), the extent of examinations will-be to the 74 Code. -The required examinations-will include 50 percent of the total number of. welds of the equivalent of one stream over.the service life (40 years) of the plant. At least one exam will be performed in each stream of the MS system during each inspection interval.

I C5.21

'l 1 Multiple Stream Welds 'I .i Total Number - Scheduled Pipe Diameter' (25%) A 25-24" I i B 21-24" 1 C 22-24" 1 D 25-24" 1 1 O average per stream = 23.25 welds. 50% = 12. Three welds due per interval (four intervals); i however..four welds will be scheduled during. the third interval to meet the requirements j that at least one veld in each loop be examined ] during each interval. Item No: C5.11 A 4-6" B 4-6" 1 C 4-6" D 4-6" average per stream = 4 welds 50% = 2 One veld due per interval (four intervals). O re47/7422 Item No: C5.31-O A-12-6" 1: B 12-6" C 12-6" D 12-6" average per' stream.= 6 welds 30% = 3 One weld due per interval (four intervals). Feedwater System There are four loops or streams associated ~with the FW system. Per?the 74 Code, this system is considered a Category C-C system.' :The 83' Code q has incorporated this system into Category C-F. j As referenced in'Section 1.2(D), the extent of examinations will include _50 percent-of:the' j total number of welds of the equivalent of._one ~ stream over the service life-(40 years) of the' plant. At least one exam will be performed in. each stream of the FW system'during each inspection interval. Multiple Stream Welds Total Number - Scheduled Pipe Diameter (25%) Item No: C5.21 A 1-14" 1 B 1-14" C 1-14" D 1-14" average per stream = 1 50% =.5-One veld due per interval' A 32-12"- 1 B 33-12" 1 C 30-12" 1-D 31-12" 1-average per stream = 31.54 ~50% = 15.75' Four welds due per interval'(four intervals)~ O L l 1 j re47/7422 j I Item No: -C5.11 A 2-8"' B 2-8" C 2-8" '1 D 2-8" average per stream = 2 50% = 1 One weld due per interval. 2.2.3 ' Augmented Inspection Requirements Augmented. examinations are performed in accordance with Section XI. The high energy piping systems are defined in the Connecticut Yankee Inservice Inspec-tion Program.. The areas subject.to examination are in accordance with Examination Category:C-F and are. specifically denoted in the Inspection Plan as requiring augmented inspections. A) Consistent with the guidance contained in NRC Mechanical Engineering Branch Technical Position No. 4, dated March. 18, 1975, an: inservice inspection program is instituted at-potential high energy pipe break locations at-p which consequences of a postulated pipe rupture "could" affect the plant's-safe shutdown cap-ability and other methods.'of pipe restraint.are-considered to be impractical.. This augmented inspection program will provide a means for-timely detection of cracks. propagating in'the piping. Since the Connecticut Yankee Plant.was-built prior to adoption of the-ASME Code ~for ISI, there is not complete accessibility for inspection in accordance<with specific require-ments of that code. Inspections will be conducted to the extent practical within'the limitations of design, geometry, and materials of the components. Visual inspections will be-conducted for all areas identified in Table E. I B) These requirements apply to inservice inspec - tion of'certain main steam and feedwater system piping welds, identified in Table E. i i C) The augmented inservice inspection program at I each veld identified.in Table E shall be per-formed'as follows in accordance with the ~ applicable requirements of the ASME Section XI. Code, Subsection IWC, Examination Category C-F and are specifically denoted in'the inspection plan as requiring augmented inspections, re47/7422 4 l D) One hundred percent of the items will be 7s (,) inspected over the third ten-year interval. I I If indications are detected that exceed the allowable standards of the ASME Section XI Code, they shall be investigated and evaluated and the frequency of examination for that veld sLc11 be once per period for three consecutive periods. If no further indications are found I or indications do not exceed the allowable rcandards of ASME Section XI, the subsequent inspections will be limited to once during each ten-year interval. E) A *:sual examination (VT-2) of all areas iden-tified in Table E will be performed semi-annually. F) Repairs, Reexamination and Tests Repairs, reexamination and piping pressure tests shall be conducted in accordance with ASME Section XI. 2.2.4 Class 2 System Pressure Tests (} A) The pressure retaining components within the Class 2 system boundaries are subjected to System Pressure Tests as required by Table IWC-2500-1, Examination Category C-H. System Functional Tests, IWA-5211(b) and System Hydrostatic Tests. IWA-5211(d) will be per-formed in accordance with IWC-5210. B) The boundaries subject to system pressure tests (functional and hydrostatic), as.well as the test program, are included in the Inservice Inspection Program. The test requirements are identified in Section 7.2, Table BCD-5000 of this submittal. 2.3 Class 3 Systems The Class 3 boundaries are based upon the requirements of Regulatory Guide 1.26 and the Connecticut Yankee Technical Specifications. 2.3.1 ASME Code Exemptions Employed IWD-1220.1 - Integral attachments of supports o and restraints to components that are four-inch nominal pipe size and smaller within the system boundaries of Examination Categories D-A, D-B, re47/7422 and D-C of Table IWD-2500-1 shall be exempt !G from the visual examination VT-3, except for U pWR Auxiliary Feedwater Systems, IWD-1220.2 - Integral attachments of supports o and restraints to components, exceeding four-inch 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 systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling; and l (b) the components operate at a pressure of i 275 psig or less and at a temperature of s 200'F or less. l t 2.3.2 Piping Systems Refer to Section 7.2, Table C, of this submittal for the Inspection Summary of Class 3 components. 1 l There are no Class 3 integral attachments on piping l p) greater than one-inch nps at Connecticut Yankee. \\ 2.3.3 Class 3 System Pressure Tests A) The pressure retaining components within the boundary of each system specified for Examina-tion Categories D-A, D-B, and D-C are pressure l tested and visually examined as specified in I Table IWD-2500-1. A System Inservice Test, IWA-5211(c), System Functional Test, j IWA-5211(b), and System Hydrostatic Test, IWA-5211(d) will be performed in accordance with IWD-5221, IWD-5222, and IWD-5223, j ) respectively. B) Refer to Section 7.2, Table C, of this sub-mittal for Inspection Summary for Class 3 components. C) The boundaries subject to system pressure tests (Functional, Inservice, and Hydrostatic), as ] well as the test programs are included in the l Inservice Inspection Program. The test requirements are identified in Section 7.2 Table BCD-5000 of this submittal. re47/7422

y M 2.4 ASME Class 1, 2, and 3 Component Supports i ASME Class _1, 2, and 3 component supports.are examined in j accordance with the requirements of IWF-2500. Component supports _ selected for examination shall be supports of those components that are required to be examined under Articles-IWB, IWC, and IWD. l Refer to Section 7.2, Table D, of this submittal for the 1 ' Inspection Summary of Class 1, 2, and'3 component supports. 2.4.1 ASME Code Exemptions Employed Component supports of those components that are required to be' examined under Subsection IWE. The requirements of subsection'IWE are not imposed on the licensee by 10CFR50.55a, as referenced in the Federal Register Vol. 48, No. 26 dated February 7, 1983. 2.4.2 class 1 Component Supports Class 1 piping and component supports are. visually examined (VT-3) to determine their general mechan-feal and structural integrity and, where appropri- ] ate, to determine conditions relating to their operability (VT-4). ) 2.4.3 Class 2 Component Supports Piping and component supports are visually examined (VT-3) to determine their general mechanical and structural integrity and, where appropriate, to determine conditions relating.to their operability j (VT-4). 'i 2.4.4 Class 3 Component Supports Class 3 piping and component supports are visually ) examined (VT-3) to determine their general i mechanical and structural integrity and, where ) appropriate, to determine conditions relating to their operability (VT-4). ( 2.4.5 Hechanical and hydraulic snubber inspections, including functional testing, are conducted in accordance with the augmented surveillance require-l ments of plant Technical Specifications and are not i included in this submittal. I O o re47/7422 1 1 Supports listed for examination in Subsection IWF t have not been separated further than code class as the examination methods and acceptance criteria are the same. Connecticut Yankee believes that this l manner of listing is sufficient and that it satis-fies the intent of the Code. l l l ( 0 re47/7422 n-3.0 RELIEF REQUESTS 3.1 General 3.1.1 In cases where parts'of.the required examination areas cannot be effectively examined because~of a combination of cornonent design or current inspec-tion technique limicstions, Connecticut Yankee will continue to evaluate the development of new or improved examination techniques with the intent of applying these techniques where a practical improve-ment in the examination can be achieved. 3.1.2 Format Relief Requests are arranged _in order by Code. Category. They are numbered sequentially with the first digit representing the third interval and the second digit' representing the individual relief request (i.e., Relief Request'3-2). Each relief request contains the following information: (a) Code Identification - describes the Code Class, Examination Category, and Item Number. (b) Code Requirement - describes the examination requirements. (c) Code Relief' Requested - self-explanatory. (d) Reason for Relief - describes examination conducted and/or evaluated to support the basis for relief. (e) Proposed Alternative Examination - self-explanatory. 3.1.3 Relief Request Support Documentation Where applicable, additional information, in the form of drawings or sketches, have been provided to support the reason for relief.. The additional information has been referenced in the reason for relief section of the applicable relief request. 3.1.4 Section 7.2, Tables A,.B, and C.will reference the applicable relief request, by number, for the effected areas of examination described in this section. 3.2 Completed Relief Requests .o re47/7422 Relief Request: 3-1 Code Class: 1 Examination Category: B-A, Pressure Retaining. Welds in Reactor Vessel Item No.: Bl.21 Code Requirement: Section XI of the ASME B&PV Code, 1983 Edition,.with Addenda through the Summer of 1983, requires that the accessible length of one circumferen-tial head weld be volumetrically examined. This includes veld metal and base metal for one plate thickness beyond the edge of the weld, g de Relief Request: Pursuant to 10CFR50.55a(g)S(iii), relief is requested ~from performing l the inservice volumetric examination of the closure head peel segment-to-disc circumferential weld. Reason for Relief: The closure head peel segment is completely enclosed within the pattern of.CRDM penetrations inside the shroud and is not accessible for examina-tion as required by Table IWB-2500-1. O During the February 1979 refueling outage,-an investigation was made by CYAPCO and Westinghouse personnel to determine-inspectability of the RPV head peel segment welds. As can be seen from the sketch, Reference Bl.2, access for the examination of these velds is prohibited by.their loca-tion relative to the CRDM penetrations, the permanent insulation, and the head ventilation. shroud sections.- We have also attached photographs of the actual installation which'shows the congestion in.this area. Inspection from the inside (clad) surface-is not possible.because of surface irregularities and high radiation. Proposed Alternative Examinations: A. The subject veld will receive a visual examination during each Code-required (B15.10) system leakage test prior to reactor startup following each reactor refueling outage. The test will be per-formed at not less than the system nominal operating pressure, at 100 percent rated reactor power. B. One closure head meridional is required to be examined. If unac-ceptable indications are revealed, the accessible portions of addi-tional meridional welds will be volumetrically examined. O re47/7422

Y.' E E ' !G H OU SE ELE CittlC Cr..P OP ' 't0!,' Sce s a+ Reu= 51. 2 C Yvv' 1 Cop 4RoL PC.OD DRIVE ] MECMAMISto AGSEMBLIES I7J T ~ ) lb lh som i ASSEtef>LY

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i y I f_ !!$2i$27$c-I!z$h-Loma a ( t ee m, _ 1 c) u% M7 ye94 Todecwa2 kl j h .] h j &;s /, '['f]i -rT s l p( HeAb t. 4' L! o % re g & l h Q R L 3 L5 Li5 Weta u \\ i ~ l' j 'j ~~ Y .i e T-M hEAc-Tce vesse.t-b A w asmear ne % As Relief Request: 3-2 Code Class: 1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Item No.: Bl.30 l Code Requirement: Section XI of the ASME B&PV Code, 1983 Edition, with Addenda through the Summer of 1983, requires that the Shell-to-Flange weld be volumetrically examined. A partial deferral of the inspection to the end of the inter-val is permitted so long as partial examinations are conducted from the J flange face. Code Relief Request: Pursuant to 10CFR50.55a(R)S(111), relief is requested from performing the partial volumetric examinations of the flange face prior to the end j of the interval. j Reason for Relief: The reactor vessel shell-to-flange weld has been 100 percent volumetri-cally examined in 1980 and will be examined in August 1987. To date, Connecticut Yankee has not found any indications on the shell-to-flange veld to date. Connecticut Yankee believes that the examinations per- ,e~N, formed along with a 100 percent volumetric examination at the end of the U third interval is sufficient to detect any indications. Because of Connecticut Yankee's continuing effort to reduce radiation exposure, the full volumetric exam from the flange surface will be per-formed at the end of the interval, coincident with the other reactor vessel welds. Proposed Alternative Examination: A 100 percent volumetric examination of the reactor vessel shell-to-flange weld will be performed at the end of the third inspection interval. re47/7422 Relief Request: 3-3 Code Class: 1 Examination' Category: B-B, Pressure Retaining Welds in Vessels other-than Reactor. Vessels Item No.: B2.40 Code Requirement: Section XI of the ASME B&PV Code, 1983 Edition, with Addenda.through'the~ Summer of 1983, requires that 100 percent of the tubesheet-to-head weld will be volumetrically examined. The examination may be limited to one vessel among the group of vessels performing a similar function. Q de Relief Request: Pursuant to 10CFR50.55a(g)5(iii), relief is requested from performing approximately 28 percent of the steam generator tubesheet-to-head weld. Reason for Relief: The steam generator bottom head is a cast material. In 1984, the steam generator no. 4 bottom head-to-tubesheet veld was ultrasonically ex-amined. It was discovered that the calibration block and bottom head materials were different. An attempt was made to compensate for~acous-0, tic differences by measuring attenuation and adjusting instrument gain. This attempt was unsuccessful; the gain required for equivalent sensi-tivity yielded inconsistent and unreliable data'. The examination was void due to the incorrect calibration standard and inherent difficulties when examining cast materials. In 1986, the_ steam generator no. 4 bottom' head-to-tubesheet veld was ultrasonically examined using an automated ultrasonic system. Due to physical limitations of the four steam generator support lugs, 28 per-cent of the required volume cannot be examined. Because of the inherent difficulties associated with examining cast materials, CY plans on examining the bottom head-to-tubesheet veld using an automated ultrasonic device. Connecticut Yankee will evaluate new-technologies as they are developed to try and reduce those areas that are presently inaccessible to automated tools. Proposed Alternative Examinations: A. The subject veld will receive an ultrasonic examination to the extent practical. B. The subject veld will receive a system leakage test in accordance with Table IWB-2500-1, Category B-P, item B15.30. O re47/7422

, Relief Request: 3-4 Code Class: 1 . Examination Category: B-B, Pressure Retaining Welds in Vessels other than Reactor Vessels Item No.: B2.50, B2.51, B2.60, B2.70, and B2.80 Code Requirement: Section XI of the ASME B&PV Code,.1983 Edition, with Addenda'through the Summer of 1983, requires that: A. One circumferential head'(B2.51) weld on the primary side of the regenerative heat exchanger be. volumetrically examined in accor- ' dance with Figure IWB-2500-1 and -3 over essentially 100 percent of its length. B. One circumferential tubesheet-to-head weld (B2.60) on the primary. side of the regenerative heat exchanger be volumetrically examined in accordance with Figure IWB-2500-1 and -3 over essentially 100 percent of its length. C. One longitudinal weld (B2.70) on the regenerative heat exchanger primary side shall be volumetrically examined for one foot of the weld at each end of the shell, in accordance with-Figure IWB-2500-2. D. One tubesheet-to-shell weld (B2.80) on the regenerative heat exchanger shall be volumetrically examined in accordance with Figure IWB-2500-6 over essentially 100 percent of the' veld length. Code Relief Request: Pursuant to 10CFR50.55a(g)S(iii), relief is requested from performing all of the vessel examinations on the regenerative heat exchangers. Reason for Relief: Radiation in the vicinity of the regenerative heat exchanger was measured at 9R to 12R during the 1983 outage. CYAPCO has determined that the time needed for the Code-required volumetric examination of the head-to-shell and head-to-tubesheet welds is approximately 40 minutes for each. If indications required mapping and evaluation, much addi-tional time would be required. The 40-minute examination would subject the examiner to an exposure of approximately 6R. In addition to the examiner, personnel are required to remove and reinstall insulation, clean the welds, and to perform a surface ex-amination. There are no connections to enable these heat exchangers to be flushed to lower the radiation levels. In accordance with Regulatory Guides 8.8 and 8.10, CYAPCO requests ] relief from the Code-required examinations and proposes that a visual 1 re47/7422 ) ij 1 examination be made during the system leakage and system hydrostatic / tests. Proposed Alternative Examinations: The subject welds will receive the Code-required visual (VT-2) examina-i tion during system leakage (B15.40) tests and system hydrostatic (B13.41) tests. a l O re47/7422

f - 24 Relief Request: 3-5 Code Class: 1 Examination Category: B-D, Full Penetration Welds of Nozzles in Vessels - Inspection Program B Item No.: B3.120, B3.140 Code Requirement: Section XI of the ASME B&PV Codc, 1983 Edition, with Addenda through the Summer of 1983, requires that each Nozzle Inside Radius Section be volumetrically examined in accordance with Figure IWB-2500-7(b) and (d). All of the pressurizer and steam generator nozzle inside radius sections are required to be examined during the third inspection interval. Code Relief Request: Pursuant to 10CFR50.5Sa(g)S(iii), relief is requested f rom performing the volumetric examinations on all of the pressurizer and steam genera-tor nozzle inside radius section welds. Reason for Relief: No acceptable ultrasonic inspection technique is presently available to perform completely the nozzle inner radius examination from the outer (]- surface (Reference NUREG-0619). Present ultrasonic techniques are not capable of accurately and repeatedly characterizing flaws and quantify-ing their size from the exterior. Up to the present time, the only effective examination of this area is a surface examination. However, very limited stay times.due to radiation in the area of the primary nozzles of the pressurizer and steam genera-tor preclude this examination without extensive decontamination. Connecticut Yankee will continue to defer the inner radius examination on the steam generators and pressurizer until such ultrasonic techniques for this examination are available and acceptable for use. Meaningful volumetric examination of the nozzle inside radius section from the external surface is difficult with existing inspection equip-ment. Typical nozzle configurations involve different radii of curva-ture on the inside and outside surfaces in the transition region where the inside radius section is to be examined. Changes in section thick-ness are also typical in this region. These geometry factors cause the attenuation and redirection of ultrasonic signals and result in unreli-able interpretation of examination data. Current radiographic methods are also of little use in detecting fine surface cracks on the inside radius of nozzles. Surface examination of the inside radius is a useful alternative method. This method, however, must be performed from inside of the vessel where radiation exposure to inspection personnel becomes a factor. re47/7422

i Proposed Alternative Examination: (~ \\ A visual examination (VT-2) vill be performed on the nozzles during the Code-required pressure tests. ) l i i O re47/7422

_ _ _ _ Relief Request: 3-6 Code Class: 1 Examination Category: B-D,. Full Penetration Welds of Nozzles in Vessels - Inspection Program B Item No.: B3.150, B3.160 Code Requirement: 'Section XI of the ASME B&PV Code, 1983 Edition, with Addenda through the Summer of 1983, requires that all nozzle-to-vessel welds and inside radius sections in the primary' side of the regenerative heat exchanger-be volumetrically examined in accordance with Figures IWB-2700-7(a) through (d) during the third inspection interval. The nozzle-to-vessel weld and adjacent areas of the nozzle and vessel are included.- Code Relief Request: Pursuant. to 10CFR50.55a(g)S(iii), relief is requested from volumetric examination of'the nozzle-to-vessel welds and the nozzle inner radius section on the regenerative heat exchanger. Reason for Relief: High radiation on the nozzle-to-vessel weld precludes volumetric and surface examination. As explained in Relief Request 3-4, CYAPCO O requests relief from the Code-required examination. Proposed Alternative Examination: A visual examination (VT-2) will be performed on the nozzles during the Code-required pressure tests. O re47/7422

) .l - 27'- Relief Request: 3-7 LO Code Class 1: 1 Examination Category: B-F,-Pressure Retaining Dissimilar Metal Welds 1 Item No.: B5.10 I Code Requirement: Section XI of the ASME B&PV Code 1983 Edition, with addenda through.the { Summer of 1983, requires that a 100 percent volumetric and surface- ' examination be performed on'all nozzle to safe end butt welds greater i than 4 inch nps.- Code Relief Request 3 Pursuant to 10CFR50.55a(g)5(iii), relief is requested from performing the inservice surface examination of the nozzle to safe'end butt velds i greater than 4 inch nps on the Reactor Vessel. Reason for Relief The Connecticut Yankee reactor vessel is a four-loop PWR. There are eight nozzle to safe end butt welds for item B5.10,'of Category B-F, in the inservice inspection program. In 1980 all eight velds were surface examined. O An ALARA review was completed that identified a radiation exposure total v of 10.90 man-rem for the 203 man hours required to perform the exam. Included as part of this man rem number was a surface examination of four safe end to pipe welds located adjacent to the nozzle to safe end welds. The man rem totals also include any preparation work required such as insulation removal / replacement, weld cleaning,.or scaffolding erection. A total of twelve (12) welds were examined with an average rate of exposure of 0.9 man rem per veld. The ultrasonic examination of the nozzle to safe end welds will be per-formed from the ID surface using the remote immersion method. Connecticut Yankee believes that any f ailure of the veld will be induced from the ID surface and that the ultrasonic examination of this surface shall be sufficient to detect any indications. Each of the nozzle to safe end welds'has received a surface exam per-formed in 1980. No service-induced indications were reported as part of this examination. Connecticut Yankee believes that the proposed ultrasonic examination is adequate to detect flaws in the' listed items. In its commitment to. reduce overall exposure rates, Connecticut Yankee believes that the-ultrasonic exam will assist in reducing the exposure rates, without losing the ability to detect flaws in the reactor vessel nozzle to safe end welds. O re47/7422

8 28 - . Proposed Alternative Examinations O A'. The subject welds will receive a full volume volumetric examination from the ID surface in accordance with ASME Section'XI and. Regulatory Guide 1.150. B.- The OD surfaces shall be visually examined'during the. reactor: coolant system hydrostatic test,_in accordance with Category B-P, Table IWB-2500-1. C. A calibration will be-performed to demonstrate that a UT exam from .the ID surface can. detect an OD surface-induced flaw. O J re47/7422

- _ _ _ - _ - _ _ _ _ 1 I Relief Request: 3-8

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t Code Class: 1 Examination Category: B-F, Pressure Retaining Dissimilar Metal Welds Item No.: B5.70 Code Requirement: Section XI of the ASME B&PV Code, 1983 Edition, with Addenda through the O Summer of 1983, requires that a volumetric and surface examination be performed on each nozzle to safe end butt veld with a nominal pipe size greater than or equal to four inches. The examination shall be in accordance with Figure IWB-2500-8. Code Relief Request: Pursuant to 10CFR50.55a(g)S(111), relief is requested from performing a complete volumetric examination on the steam generator nozzle to safe end butt velds. The areas shall include dissimilar welds (e.g., safe-end welds) between combinations of carbon, low alloy, or high tensile steels and stainless steels, nickel-chromium-iron alloys, nickel-copper alloys. This shall i include the base material for at least one wall thickness beyond the edge of weld. O V Reason for Relief: I 1 l The configuration of the eight steam generator nozzle-to-safe-end welds l prevents a complete volumetric examination from being performed. The i carbon steel nozzle casting on one side and the geometry of the safe-end j forging on the other side prevent full ultrasonic coverage from being ) possible. To supplement the limited 42* refracted L-wave examinations of the weld, transducers of other characteristics will be utilized to the extent practical, as will surface examination techniques. Itlwill be possible to perform a Code examination of about 60 percent of this weld design. A detailed sketch (Ref. B4.5) identifying the examination coverage and the configuration of the nozzle safe-end weld is included. Proposed Alternative Examination: A. The Code-required surface examination shall be performed. B. The Code-required volumetric examination will be performed to the extent practical, b) i v q re47/7422 l

I 1'fN'p 1 t k7 D n CAC N O ',P Q I E TA L p/ U / f S / N I / 'l l / O ',l !/ N- / F [//s / F OD I,/ O N S D Rg H A L A ';_/ X E C E ) TDW E 'y MX A EN D .T KEE I R S P S EA y'y EI 'x HP FP 1 A T T kX T 0 SO E F S T L O \\\\X ~ xf&, E 'k D T T S U \\ TE XE N O C H I OL E ( R x MT Q \\ N, X RZ s I \\ O L N E PZF X E .I P0A y/ \\ \\ c FA AE ANS [A OR M VA V W W E i A x E O O 'L x / R C S' H A x D y .A SE E T / N /l / /, LA C I y,NE R D F !t E E T g frf /' T R O'2 Y; /j 4 D 4 4 b 1 g. Relief Request: 3-9 %J Code Class: 1 Examination Category: B-L-1, Pressure Retaining Welds in Pump Casing B-L-2, Pump Casings Item No.': B12.10, B12.20 Code Requirement: l 'Section XI of the ASME B&PV Code,'1983 Edition, with Adden'da through the Summer of 1983, requires that all pump casing welds be volumetrically examined and that pump casing internal surfaces be visually (VT-3) examined. Examinations,are limited to welds in at least one pump in each group of pumps performing a similar function. { ) Code Relief Request: { l Pursuant to 10CFR50.55a(g)5(iii), relief is requested from performing .) the reactor coolant pump welds'and internal surface volumetric and ) visual (VT-3) examinations, respectively. .] 1 Reason for Relief: ~l j i CYAPC0 evaluation has determined that the hardships that must be endured j to perform this inspection are not justified on a technical basis for the following reasons: The reactor coolant pump casing consists of four Type 316 stainless o steel cast rings with a minimum thickness of approximately eight inches. Considering the stainless steel Type 316 characteristics and the water chemistry limitations for the reactor coolant system, the potential for any stress corrosion mechanism is considered to i be negligible. Thermal embrittlement is a function of ferrite content in duplex o cast stainless steels. Connecticut Yankee's casing material is made of CF-8M (316 S.S.), with a maximum ferrite content on the order of 15-25 percent, based on industry standards. Using EPRI I data for cast austenitic stainless CF-8 (304 S.S.) and a maximum ferrite level of 25 percent for the specific CY CF-8M RCP casing, the minimum time required for thermal embrittlement'to lower the Charpy-V-Notch toughness below 50 joules (37 f t-lbs) is 36 years. Therefore, adequate fracture toughness will be retained over the lifetime of the plant, thereby eliminating potential nonductile fracture concerns. Service-induced flaws would more likely be-generated from a cy-o clical loading mechanism such as fatigue. However, the pump bowl geometry, as well as endurance limit of the given material, make this a negligible concern. O The examinations completed on four Westinghouse Model 93 pump o casings have shown.that no detectable interior service-induced re47/7422

l . flaws have occurred. The CYAPCO pumps are Westinghouse Model 63 pumps, which is a smaller and similar version of the Model 93.. Disassembly of the pump for inspection could result in significant o damage, as the pumps were designed prior to ISI requirements, and 1 ease of disassembly in the field was not part of the design basis. I o Radiation levels will be very high, estimated at 60-80 rem /hr. at the pump impeller prior to decontamination, The reactor coolant pumps have performed satisfactorily at o Connecticut Yankee. No operational problems have been encountered which have required disassembly of a reactor coolant pump. o The pump inspection is not justifie'd from a cost / benefit perspec-tive. The pump disassembly, inspection, and reassembly is estimat-ed to cost $500,000. The dollar value associated with the radia-tion exposure required to perform this work is $105,000-(50 man-rem valued at $2,100 per man-rem). The dollar man-rem value is based upon guidelines presented in NU Corporate ALARA Manual. The total examination cost is, therefore, in excess of $600,000. This cost i is not justified in light of the lack of improvement in safety provided by this examination. These costs exclude the expenditures associated with any unique decontamination process if'a feasible process is found to be available, p The imposition of this requirement will' result in technical and finan- \\.J cial hardships and unusual difficulties without a compensating increase in the level of quality or safety associated with the reactor coolant pumps. A vibration monitoring system has been installed on the reactor coolant pumps and is providing on-line monitoring of the pump's mechan-i ical condition. In addition, more comprehensive vibration data are taken on all four reactor coolant pumps prior to shutdown for refueling. We are, therefore, confident that a progressing mechanical malfunction will be detected before failure. In summary, confidence in the safe condition of the existing pumps, the significant radiation exposure, the potential of damaging pump compo-nents during disassembly and reassembly, the lack of benefit to plant integrity, and the significant expense in both dollars and time have led CYAPCO to conclude that pump casing examinations, as required by the ASME Code using existing techniques, are not justifiable. Proposed Alternative Examination: If the reactor coolant pump is disassembled due to maintenance, a o visual examination (VT-3) of the pump internal. surface will be performed. I The pump casings will be visually examined (VT-2) during the o Code-required system pressure tests. O' A surface examination on the exterior surfaces of the pump casing o welds will be performed in accordance with Section XI. re47/7422

-- Relief Request: 3-10 Code Class:' 1 Examination Category: B-M-2, Valve Bodies Item No.: B12.50 Code Requirernent: Section XI of the ASME B&PV Code, 1983 Edition, with Addenda through the Summer of 1983, requires that the internal surfaces of valve bodies exceeding four-inch nps be visually examined (VT-3).- Examinations are limited to one valve within each group of valves that are of the same ] construction design and manufacturing method and that perform similar { functions in the system. i Code Relief Request: Pursuant to 10CFR50.55a(g)S(iii), relief is requested from performing i the inservice visual examination (VT-3) on the valve body internal surfaces. 3 Reason for Relief: ) The requirement to disassemble an operable valve for the sole purpose of performing a visual examination (VT-3) of the internal surfaces is O 1 vr ctic 1 "a = t c e" = rete ith the i=cre ed retv chieved av this inspection. To disassemble these items would provide a very small potential for increasing pisnt safety margins with a disproportionate impact on expenditures and resources. Proposed Alternative Examination: The subject valves will receive a visual examination (VT-2) during o the Code-required pressure tests. If a valve is disassembled for maintenance, the code required o visual examination VT-3 will be performed. System Valve Number RCS RC-MOV-546 RCS RC-MOV-538 RHR RH-MOV-780 RHR RH-MOV-781 BYPASS RC-MOV-577. RCS RC-MOV-537 l RCS RC-MOV-526 RER RH-MOV-803 RHR RH-MOV-804 O BvrASS RC-M0v-528 RCS RC-MOV-528 re47/7422

_ _ - - - _ - _ RCS RC-MOV-514 g (_) RCS RC-MOV-513 BYPASS RC-MOV-515 RCS RC-NOV-512 RCS RC-MOV-501 BYPASS RC-MOV-510 CORE DEL CD-CV-872A CORE DEL CD-CV-872B CORE DEL CD-MOV-871A CORE DEL CD-MOV-871B 1 l 1 O) ) re47/7422 1 ' Relief Request: 3-11 1 Code Class: 2 Examination Category: C-B, Pressure Retaining Nozzle Welds in Vessels Item No.: C2.11 Code Requirement: Section XI of the ASME B&PV Code requires that nozzles in vessels less than or equal to 0.5 inch nominal thickness have a surface exam per-. formed in accordance with Figure IWC-2500-3. In the case of' multiple j vessels of similar design, the exams may be limited to one vessel or distributed among the vessels. Code Relief Request: Pursuant to 10CFR50.55a(g)5(iii), relief is requested from performing the surface examination of the residual heat exchanger E-5-1A & IB nozzle-to-shell welds in accordance with' Figure IWC-2500-3. I i Reason for Relief: The design of the Connecticut Yankee residual heat exchanger does not correspond to Figure IWC-2500-3 as depicted in the Code. The design of; the residual heat exchanger is better represented by Figure IWC-2500-4(c'). O-Refer-to the attached drawing 16103-20206, SH. 39 for a typical nozzle. and collar arrangement. Proposed Alternative Examination: Connecticut Yankee will perform a surface examination in accordance with the requirements of Figure IWC-2500-4(c). i 1 'i a C:) re47/7422

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.. Relief Request: 3-12 Code Class: 2 Examination Category: C-B, Pressure Retaining Nozzle Welds in Vessels Item No.: C2.22 Code Requirement: Section XI of the ASME Code requires that nozzle inside radius sections-be' volumetrically examined in-accordance with the requirements.of . Figure IWC-2500-4(a) or (b). Code Relief Request: Pursuant to 10CFR50.55a(g)S(iii), relief is requested from performing the volumetric examination of the nozzle inside radius section of the steam generator nozzles. Reason for Relief: Connecticut Yankee has four steam generators, with a total of eight nozzle inside radius sections required to be examined. Connecticut Yankee was designed and constructed prior to the implementation of ASME Section XI. The steam generator nozzle configurations involve dif ferent radii of curvature on the inside and outside surface in the transition () region where the inside radius section is to be examined. At the present time, no acceptable ultrasonic inspection technique is available to perform completely the nozzle inner radius section from the outer surface. Present ultrasonic techniques are not capable of accu-rately and repeatedly characterizing flaws and quantifying their size from the exterior. Proposed Alternative Examination: q 'l Connecticut Yankee will follow industry progress with technique develop- ] ment and work towards the performance of a meaningful ultrasonic examina-j tion. l l i i 4 i O re47/7422

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- - - -. - - - - -, f] 4.0 EVALUATION CRITERIA \\,1 4.1 Class 1 Acceptance Standards 1983 Edition of Section XI through and including the Summer 1983 Addenda. Examination Components and Parts Acceptance Category Examined Standard B-A Welds in Reactor Vessels IWB-3510 B-B Welds in Other Vessels IWB-3511 B-D Vessel Nozzle Welds IWB-3512 B-F, B-J Dissimilar & Similar Metal Welds IWB-3514 B-G- 1 Bolting IWB-3515 B-H, B-K-1 Integral Attachments for Vessels, IWB-3516 Piping, Pumps, & Valves B-L-1, B-M-1 Welds in Pumps & Valves IWB-3518 B-L-2, B-M-2 Pump Casings & Valve Bodies IWB-3519 ,.( B-N Interior Surfaces & Internal IWB-3520 Components of Reactor Vessels 1 B-0 Control Rod Drive Housing Welds IVB-3523 B-Q Steam Generator Tubing - Not covered by this submittal and is handled by the Plant Technical Specifications 4.2 Class 2 Acceptance Standards Article IWC-3000, Acceptance Standards for Flaw Indications, are in the course of preparation. The rules of IWB-3000 may be used. Examination Components and Parts Acceptance Cat e go ry Examined Standard C-A Welds in Other Vessels IWB-3511 C-B Vessel Nozzle Welds IWB-3512 C-C Integral Attachments for Vessels, IWB-3516 g3 Piping, Pumps, & Valves (/ C-D Bolting IWB-3515 re47/7422

l 1 Examination Components and Parts Acceptance-Category Examined Standard C-F Dissimilar and,Similar Metal IWB-3514 Welds -) C-G Welds in Pumps & Valves IWB-3518 1 4.3 Class 3 Acceptance Standards Article IWD-3000, Acceptance Standards for Flaw Indications, are in the course of preparation. The rules of IWB-3000 may be used. Examination Components and Parts Acceptance Category Examined Standard D-A Integral Attachment Welds on 'IWB-3516 Systems in Support of Reactor. Shutdown Function D-B Integral Attachment Welds on IWB-3516 i Systems in Support of ECC, CHR,- 1 Atmosphere Cleanup, and RHR D-C Integral Attachment Welds on IWB-3516 O S steme in SePPert ef Re idua1 F Heat Removal From Spent Fuel Storage Pool 1 4.4 Acceptance Standard for Supports (Class'1, 2, and 3) l 4.4.1 Inservice snubber testing is not covered by this summary submittal as-it is handled by the plant-Technical Specifications. 4.4.2 Acceptance Standards (IWF-3400) Acceptance Standards to verify component support structural integrity will be based on IWF-3410. 4.5 Repair and Replacement Program In the event that repairs or replacements of pressure-retaining components are required, Article IWA-4000-(Report Procedures) and Article IWA-7000 (Replacements) shall be followed. The latest edition and addenda of Section XI, that has been-approved per 10CFR50.55a(b)2 or the Federal Register, may be used for repair, replacement, or modification requirements. All we.d repairs shall be in accordance with the Northeast Utilities Welding Manual. re47/7422

1 i l 5.0 SUBMITTAL

SUMMARY

5.1 Description of the ISI Program Format The third ten-year ISI program' plan is being prepared for the components identified in this submittal. Individual compo-nents shall be identified and listed in the program. The following information will be provided for each component. A) System Designation - as described by the plant P& ids. I B) Component Identification - unique number' designation which includes the isometric drawing number for location. C) Code Item Number, Code Category, and Applicable Code Edition and Addenda being employed. D) Examination Method - the required exam method (s) to be used for each component. I E) Procedure - the appropriate procedure being used for each component. F) Schedule - listing of components scheduled for examina-tion this interval and/or completed during previous intervals. i G) Drawing - the applicable isometric drawing identifying the location of each component. f H) Also included will be a comments section defining the calibration block to be used, special exam techniques, and relief requests associated with the component, and a component description identifying the size and location. 5.2 Summary Submittal Tables 5.2.1 The summary submittal tables (Section 7.2) A, B, and C for Class 1, 2, and 3, respectively, summarize by code category and code item number.the component to be examined, method of examination, total number of components in the item number, and the' amount of components scheduled for examination during the i third ten-year interval. Where. examinations required by the Code cannot be performed completely, they will be performed to the extent practical. These examinations will be considered,in compliance, as identified on the applicable relief request. f' Specific relief has been requested for areas that cannot be examined to the requirements of the Code J re47/7422

c. - 43 I O or have been identified to be areas where the potential for high radiation exposure is likely. 5.2.2 Table D summarizes the hangers-and supports subject'- to examination'per IWF for Class 1, 2, and 3. The table summary is the same as 5.2.1 above. ( 5.2.3 Table E summarizes the augmented' inspection program for the 111gh Energy Piping Systems. There are no. i'I relief requests associated with these items. 5.2.4 Table BCD-5000 summarizes 'he system pressure test

t requirements for Class 1, 2, and 3 components.

1 O ) ) -4 ll !I i 1 1 j j l re47/7422 l 'J

y l '! 6.0 RECORDS AND DATA MANAGEMENT' 6 '.' 1 Records of the ISI Program, schedules, calibration standards, examination ~ procedures, examination reports and results, certifications, and corrective actions required and taken- ) shall.be developed and maintained at Connecticut Yankee in 1 accordance with Article'IWA-6000 of ASME Section XI. ,7 1 l6.2 Responsibilities'for maintaining the ISI Program current shall j; be defined in specific plant procedures.and the QA Program. 6.3 As described'in Section 5.1, a computerized data managewent system is used to schedule items for examination and to i determine percentage requirements required by the Code.. L t 4m I'\\ ,i If. O io 1 d 7 i i l O re47/7422

W, 7.0 ' FIGURES AND ATTACHMENTS ' - 7.1' Figures - System Boundcry Drawings-7.2 Attachments Table A) Class 1. Components Inservice, Inspection Summary Table B). Class 2 Components' Inservice' Inspection Summary Table C) Class 3 Components Inservice Inspection Summary. Table D) Class 1, 2, and 3 Component Support Summary Table; i . Table E) Augmented Inservice Inspection Program f "Jable BCD-5000) System Pressure Tests 1 i g . ) ) _l A*i qs 't n-re47/7422 i

22 47 / k 7 S c 4 FT o e ES AAA 11A 2 A AA l IE /// / / // b LU NNN 33N 3 N NN EQ n RE o R i tar b i D l E a LS c UM DE 211 422 1 1 ee e ET nn h HI oo t C nn S gn isu R d. E ee L BS md E MM ro S UE oC S NT 239 422 I 1 ee f E I 1 1 1 nn rI V L oo eX AF nn p R TO n O O eo T T bi C t A l c E l e R aS E e h E N & c sE K I D a M NY MO .f sS AR S AH lll lll l l rll dA YAA D XT ooo ooo o ouoo l M L EE VVV VVV V VSVV ee TME E M wh UUL W t CSB V I A G Pf TIT N Ro CS I EI N e8 N I h7 N A t2 O T C E fN R o e E ss R na U oC S i S t e E ad R no P iCm an A xi N l e B O l l e n d I a a g e o ce Y T i i n g i iv R P 1 tl t a n sg no O I sna 1 n l a de or G R den sel F l l R sp E C l ri d ra F e ap T S eed l en o We ra A E Wf u ef o t o n t C D mt Wmi t ri l n l ui ud l il ug E M l cg dci l d at i D E ern arr e a pl es O T hio eie h e ee h e C I SCL HCM S H RB Td 1 I S S E A T L O O C N N 012 012 0 0 01 E M 111 222 3 4 55 D E O T lll lll l l 1l C I BBB BBB B B BB

l{!! S FT ES AAA AAA AAA 3 444 IE /// /// /// LU NNN NNN NNN 3 333 EQ RE R S L E S S D E E V LS UM R DE 422 000 000 1 000 O ET T HI C C A S E R N AH R T EBS R MM E UE H NT 422 000 000 4 660 T I O LAF S TO L O E T S SE V E E N K I D NY MO AR S AH lll lll lll l lll YAA D XT ooo ooo ooo o ooo M L EE VVV VVV VVV V VVV TME E M UUL W CSB I A G TIT N CS I EI N N I N A O T C E R E R U S S l E d d l R l a e P e e h s W H S d B l d N e s a B O Wl l r l e s l s I a a o) a H r) a r) Y T di i t e i ee i ee R P atl t ad t o gd t gd O I r ena n ri n t ni n ni G R e Hen sel eS sel aS sel aS E C z - ri d ra n d ra t h dra h T S i oed l en ey l en e cy l en cy A E r tf u ef o Gr ef o e xr ef o xr C D u mt Wmi a Wmi h Ea Wmi E a s l ui ud mm ud s m ud m E M s l cg dci ai d ci e ti dci ti D E e ern arr er arr b ar arr ar O T r hi o eie tP eie u eP eie eP C I P SCL HCM S( HCM T H( HCM H( 1_ SSA L O C N 012 012 012 0 012 E M 111 222 333 4 555 D E O T 222 222 222 2 222 C I BBB BBB 8BB B BBB

s 22 4 ) D 7 E /7 U S N FT 4 I ES 44 4 T IE N LU 33 3 O EQ C RE ( R S L E SS D E E V LS UM R DE 00 0 O ET T HI C C A S E R NAH R T EBS R MM E UE H NT 33 3 T I O LAF S TO L O E T SS E V E E N K I D NY MO AR S AH ll l YAA D XT oo o M L EE VV V TME E M UUL W CSB I A G h TI T N CS I EI N N I N A O T C E R E R US s S s d E d l R l e P e W W s l B dd l N al e B O ee h I HW S Y T R P ol o O I ta t G R n E C ti t T S ed e A E eu e C D ht h si s E M eg e D E bn b O T uo u C I TL T 1 S S A L O C N 00 0 E M 67 8 D E O T 22 2 C I BB 8

2247 44 n / o 7 S 33 i 4 FT t e ES AA A5 A5 a IE // /- /- r LU NN N3 N3 66 b EQ i RE 33 l R ac e h t D E g B LS n UM i M DE 88 60 00 00 s A ET u R HI G C d O S e, R me P rd oo fCr S R eI L E pX E BS S MM en S UE bo E NT 88 66 08 22 i V I 11 lt L l c N AF ae I TO hS O s S T E E sM L dS Z l A Z e E 0 we E N h K D et NY F MO l AR O AH ll ll ll ll zf YAA XT oo oo oo oo zo M S EE VV VV VV VV o TME D M n8 UUL L CSB E 7 V2 I A W TIT P - g RN CS N EI O ee N I N T hs O A ta C R C f T oe E n n n n d N o o o o so E i i i i nC P t t t t o c c c c in L 1 e e e e ti L sS sS sS sS a U d d d d nd F l s l s l s l s ie eu eu eu eu mv Wi Wi Wi Wi ao D d d d d xr N l a l a s l a l a ep B O eR eR r eR s eR p I l s s o) s r) s ca Y T e se se t e se ee se i R P s ed ed ad ed gd ed nn O I s Vi r Vi ri Vi ni Vi og G R e - s e - s eS - s aS - s si E C V on z on n on h on as T S tI i tI ey tI cy tI re A E r r Gr xr td C D o ee u ee a ee Ea ee l t ll s l l mm ll m ll uk E M c zz s zz ai zz ti zz c D E a zz e zz er zz ar zz eo O T e oo r oo tP oo eP oo hl C I R NN P NN S( NN H( NN Tb 1 1 S S E A L O TO C N 0 00 00 00 N 00 12 34 56 E M 91 11 11 11 D E O T 33 33 33 33 C I BB BB BB BB

S FT ES AAAA A IE //// / LU NNNN N EQ RE R D ELS S UM L DE 9513 0 E ET 7 62 9 S HI S C E S V N I S R D E L BS E MM W UE NT 9513 0 N I 7 62 9 O L I AF T TO A O R T TE N E E P E ll ll l K L D aaaa a NY A MO uuuu u AR I AH ssss s YAA T XT iiii i M R EE VVVV V TME A M UUL P CSB I A G TI T N CS I EI N N I N A O T C E R E R U s s S d e s S l l s d E e ze l R W zl e P oz W n Nz o o n E i eN o N t v i B O a i n t I rsro a Y T t eDi r R P el t t O I nzda r e G R ezot e n E C P oRn z e T S N e i P A E l l m r C D al ou u r i err s e E M tstt s t D E rsns e a O T aeon r e C I PVCI P H 1_ S SA L O C N 0123 0 E M 1111 2 D E O T 4444 4 C I BBBB B

22 47 /7 S 4 FT e ES 7 A A A A A 8 A A g I E / / / / / / / LU 3 N N N N N 3 N N EQ RE R D ELS UM DE 8 0 0 2 4 0 8 0 0 ET HI C S R E BS S MM D UE L NT 8 0 0 2 4 0 8 0 0 E I W LAF L TO A O T T E M R E A e e e e e e e e e E L & c c c &c c c &c c c K I D a a a a a a a a a Y M MO .f f f .f f f .f f f 1 fAR I AH l r r r l r r r l r r r YAA S XT ou u u ou u u ou u u M S EE VS S S VS S S VS S S TME I M UUL D CSB I A G TI T N h CS I EI N N I N A O T s s s C E d d d R s s l s s l s s l d d e d d e d d e E l l W l l W l l W R e e e e e e U .W .W t .W .W t .W .W t S n n e n n e n n e S it it k it it k it it k E t t c t t c t t c R 4u 4 u o 4 u 4u o 4u 4u o P B B S B B S B B S d d d d d d d d d F en en n en en n en en n N zE zE E zE zE E zE zE E B O i i i i r i i I l S e S e e Se Se e o Se Se e Y T e f f f f f f t f f f R P s ea ea a ea ea a a ea ea a O I s pS pS S r pS pS S r pS pS S G R e i - i - e i-i - e i - i - E C V P o P o o z Po Po o n P o P o o T S t t t i t t t e t t t A E r l l - r l l G l - l - C D o ae ae e u ae ae e ae ae e t nl nl l s nl nl l m nl nl l E M c iz iz z s iz iz z a iz iz z D E a mz mz z e

nz mz z

e mz mz z O T e oo oo o r oo oo o t oo oo o C I R NN NN N P NN NN N S NN NN N 1_ S S A L O C N 0 0 0 0 0 0 0 0 0 E M 1 2 3 4 5 6 7 8 9 D E O T 5 5 5 5 5 5 5 5 5 C I B B B B B B B B B

a 4' 2 2 4 7 /7 S 4 FT ES A A A A A A IE / / / / / / LU N N N N N N EQ RE R D ELS UM DE 0 0 0 0 0 0 ) ET D HI E C U S N I TNO C R ( EBS S MM D UE L NT 0 0 0 0 0 0 E I W L AF L TO A O z T T E M R E A e e e e e e E L &c c c &c c c K I D a a a a a a NY M MO .f f f .f f f AR I AH l r r r l r r r YAA S XT ou u u ou u u N S EE VS S S VS S S TP E I M UUL D CSB I A G TIT N CS I EI N N I N A O T s C E d d R s s l l d d e d d e E l l W l l W R e e e e U .W .W t .W .W t S n n e n n e S it it k it it k E t t c t t c R 4u 4u o 4u 4u o P B B S B B S d d d d d d F en en n en en n N zE zE E zE zE E B O s i i i i I r Se Se e Se Se e Y T e f f f f f f R P g ea ea a ea ea a O I n pS pS S pS pS S G R a i - i - i-i - E C h Po Po o Po Po o T S c t t t t .t t A E x l l - l - l - C D E ae ae e g ae ae e z nl nl l n nl nl l E M t iz iz z i iz iz z D E a mz mz z p mz mz z O T e oo oo o i oo oo o C I H NN NN N P NN NN N J_ S SA L O C N 0 0 0 0 0 0 0 1 2 3 4 5 h. E M 1 1 1 1 1 1 D E O T 5 5 5 5 5 5 C I B B B B B B T

2 2 47. /7 -S 4 FT e ES AAA A AA A AA A AA A I E /// / // / // / // / LU NNN N NN N NN N NN N EQ RER ) R I E ( T D E ES M LM A UE 000 00 00 0 00 0 00 0 I DT 5 5 55 D EI H N C I S N I 2 R m E a N BS r A MM g H UE 000 00 00 0 00 0 00 0 o T NT 555 55 r I p R L E AF e T TO h A O t E T R n G i E G e e s E N c &c l l l l l l l t K I D a a a a a a a a a u NY T MO f ..f .u .u u .u u .u u n AR L AH rll rl s l s s l s s l s s YAA O XT uoouoi oi i oi i oi i r M B EE SVVSVV VV V VV V VV V o TME M UUL G s CSB N t I A I l TIT N o CS I EI A b N T f N E o O R n n .n' C o o o' r E i i i e R t t t b U d c s c s c s m S e e r e r e r u S v s n e n e n e n E o g n h n h n h R em n o s a s o s l P ce i c a c a c a a ar h W W W t l s n n n o 1 pn u e d e d e d t e B h n h n h n G snh e w a w a w a e N ti w g, s h B O u ns s, r s, s s, t I l N,, ar d e s o de s r de s Y T e ss l e ucdg t ucdg e ucd g e R P s ddd Fh t aen a t aen g t aen d O I s auu s r Sfli r Sfli n Sfli u G R e ett na e rbh e rbh a rbh l E C V HSS i W z d ums n dums h dums c T S i nSeu e nSeu c nSeu n A E r eee se r a sB G a sB x a sB i C D o rrr dr u es es E es t uuu au s sga, m sga, sga, s E M c sss es s tnss a tnss t tnss m D E a ooo ro e l ait e l ait a l ait e O T e lll hl r oldu t oldu e oldu t C I R CCC TC P BF N S BF N H BF N i de lu de 1 hc S S S A L O C N 0 0 00 0 1 000 00 00 0 00 1 23 4 h E M 123 45 67 8 91 11 E 1 1 D E T O T 666 66 66 6 66 6 66 6 O C I BBB BB BB B 8B B 8B B N

2 2 47 / 7 ) S D FT 4e E ES AA A AA A AA A U IE // / // / // / N LU NN N NN N NN N I EQ T RE N R O C ( ) 1 R ( E D T E E LS M UM A DE 00 0 41 0 21 2 I ET 2 2 2 D HI C N S I N I m R a 2 E r BS g N MM o A UE r H NT 00 0 64 0 68 6 p T I 9 7 7 L 1 1 e R AF h E TO t T O A T n E i RG s d E G e u E N l l l l cl l t K I D a a .a a aa a s NY T MO .u u u u fu u AR L AH l s s l s s rs s d YAA O XT oi i oi i ui i n M B EE VV V VV V SV V a TME M UUL G s CSB N t I A I l TI T N o CS I b EI A N T f N E o O R n n n C o o o r E i i i e R t t t b U c s c s c s m S e r e r e r u S n e n e n e n E n h n h n h R o s o s o s l P c a c a c a a W W W t n n n o 1 e d e d e d t h n h n h n G w a w a w a e N h B O s, s, s, t I de s d e s de s Y T ucdg ucd g ucdg e R P taen taen t aen d O I Sfl i Sfli Sfli u G R rbh rbh rbh l E C dums dums dums c T S nSeu nS eu nS eu n A E a sB a sB a sB i C D g es es s es n sga, s sga, e sga, s E M i tnss p tnss v t nss m D E p l ait m l ait l l ait e O T i ol du u ol du a ol du t C I P BF N P BF N V BF N i de lu de 1 h S c S S A L O C N 00 0 00 0 00 0 1 56 7 89 0 12 3 E M 11 1 11 h 2 22 2 E D E T O T 66 6 66 6 66 6 O C I BB B BB B BB B N

22 47 /7 S 4 FT 4 ES A A A A A A IE / / / / / / 'LU N N N N-N N EQ RER ) 1 f DE R LS E UM T DE 0 6 8 0 2 4 0 E ET 1 2 7 2 M HI 1 4_ A C m I S a D r g N o I rp S R S E e E BS h L MM t UE D NT 0 6 8 0 2 4 0 n N I 1 2 7 2 i. A ~L 1 4 AF s TO t N O u I T n 2 ro E G E N l l l l l l l l s K I D a a a a a a' a a d NY T MO u1 u1 u1 u1 u1 ul u1 u1 u AR L AH s - s - s - s - s - s - s - s - t YAA O XT iT iT iT iT iT iT iT iT s M B EE VV VV VV VV VV VV VV VV TME M UUL G s CSB N t I A I l TIT N o CS - I b EI A N T f N E o O R C r E e R b U m S u S n ER 1_ P s s s 's s s s s a t t t t t t t t t u u u u u u u u o 2 N N N N N N N N t G d d d d d d d d e N n n sn n n n n n h B O a a ra sa a a a a t I l o r Y T e, t, e, e R P ss s as gs s s s ss d O I sd rd rd nd d d d gd u G R eu eu eu au u u u nu l E C Vt zt nt ht t t t it c T S S iS eS cS S S S sS n A E r r G x u i C D o, u, E, g, s, o, t s ss ms s ns ss es Hs s E M ct st at tt it pt vt t m D E al el el al pl ml ll Dl e O T eo ro t o eo io uo ao Ro t C I RB PB SB HB PB PB VB CB i d e lu d 1_ e h S c S SA L 0 e-C N 1 0 0 0 0 0 0 0 0 E M 1 2 3 4 5 6 7 8 E D E T O T 7 7 7 7 7 7 7 7 0 C I B B B B B B B B N.

2 2 47 /7 S 4 FT e ES IE LU EQ RE R D ELS UM DE 0 0 O 0 ET HI C S REBS MM UE NT I LAF TO I O I T S s. s s s L ae ae ae ae E l S ,l ,l l. b ,b b ,b E S rea rea rea rea E E occ occ occ o c c_ K V D ai ai ai ai NY MO .fl .fl .fl. .fl AR R AH l rp l rp l rp l rp YAA O XT oup oup oup oup i F EE VSa VSa VSa VSa TME M UUL S CSB T I A N TIT E CS M EI H N C N A O T C TA s s s s t t t t L n n n n A e e e e R m m m m G h h h h E c c c c l T a a a a a N t t t t v I t t t t r A A A A e t H d d d d n N e e e e i B O d d r d s d I l l l o l r l d Y T e e e t e e e r R P s W W a W g W i O I s r r n h G R e y e y e y a y t E C V l z l n l h l T S l i l e l c l r A E r a r a G a x a o C D o r u r r E r f t g s g m g g E M c e s e a e t e e D E a t e t e t a t l O T e n r n t n e n b C I R I P I S I H I ac i lppa 1 t S o S N A L 0 C N 1 0 0 0 0 E M 1 2 3 4 E D E T O T 8 8 8 8 0 C I B B 8 B N. ll

2 247 / 7 S 4 FT e ES IE LU EQ RE R D ELS UM DE 6 1 2 6 2 ET 2 6 4 HI 1 C S R EBS MM UE NT 5 2 8 4 5 I 0 4 2 6 L 1 2 5 AF TO G O N T I P I P E e e ee e E N & c c &cc c K I D a a aa a NY MO .f f .ff f AR S AH l r r l rr r YAA D XT ou u ouu u M L EE VS S VSS S TME E M UUL W CSB I A G TI T N CS I EI N N I N A O T C E R s E d R l U enn S n n Wii S i i E s s n44 R 4d 4d o P l l i es es t Wd Wd cee J e l e l ezz N zl e zl e nii B O iaW iaW nSS I Si Si o Y T tl tl Cee R P ena ena pp s O I pen pen eii d G R i ri i ri pPP l E C P ed P ed i e T S f u fu Pll W A E l mt l mt aa C D aui aui h nn t ncg ncg cii e E M i rn i rn nmm k D E mio mio aoo c O T oCL oCL rNN o C I N N B S 1 S S A L O C N 012 012 012 0 h_ E M 111 222 333 4 D E O T 999 999 999 9 C I BBB B88 BB8 8

2 2 47 /7 S 4 FT ES IE LU EQ RER D ELS UM DE 0 0 0 ET S HI E C V S LAV D N R A EBS MM S UE P NT M I U L P AF TO O G T N s s s I ae ae ae P l ,l ,l I ,b b b E P rea rea rea E occ occ occ K R D ai ai ai NY O MO .fl .fl .fl AR F AH l rp l rp l rp YAA XT oup oup oup M S EE VS a VSa VS a TME T M UUL N CSB E I A M TIT H CS C EI A N T N T O A C L s s s l A t t t a R n n n v G e e e r E m m m e T h h h t N c c c n I a a a i t t t t t t d 1 A A A r i K d d d h N e e e t B O d d d I l l l e Y T e e e l R P W W W b O I a G R y y y c E C l l l i T S l l l l A E a a a p C D g r r s r p n g s g e g a E M i e p e v e D E p t m t l t t O T i n u n a n o C I P I P I V I N 1 S SA L O C N 0 0 0 1 E M 2 3 h E D E 0 0 0 T O T 1 1 1 O C I B B B N

22 47 /7 S FT 4e ES 99 A A 0 IE / / 1 LU 33 N N EQ 3 RE R DELS UM DE 00 0 0 0 ET HI C S R E = SS BS GE MM NI UE ID NT 24 0 0 0 SO I 1 2 AB L C AF E TO PV O ML T UA PV NN E II e E l c l K SS D a a NY DD MO .au3 f u AR LL AH l s - r l s YAA EE XT oiT u o i M WW EE VVV S V V TME M UUL GG CSB NN I A II TIT NN CS II EI AA N TTSS N EEGE n n O RRNI i i C ID EESO 4 4 RRAB UUC SS E n SSPV e e i EEML z z RRUA i i 4 PPPV S S g e e n 1122 p p i i i de LMLM s P P ez N d s s ei BBBB O l ld ld cS I e al al x Y T W ne ne E 'e R P iW iW p O I gg m m ,i G R nn oy oy yP E C ii Nd Nd d T S ss o o ol A E aa ,B ,B Ba C D CC s s s n s e ee ee ei E M p pp v vv vv vm D E m mm l ll ll l o O T u uu a aa aa aN C I P PP V VV VV V 1-SSA L O C N 00 0 0 0 12 E M 3 4 5 D E 22 2 2 2 O T 11 1 1 1 C I BB B B B

j ,/ S FT .s ES A A A A IE / / / / LU N N N N EQ RER D E R LS O UM I DE 1 R ET E HI T C N S I DNA R S~ E E BS .R MM U UE T NT 1 C I U L R AF T - S TO S E O R T TSU RLT OEC PSU E LPSR E EUET l l l l K SSVS D a a a a NY S MO u3 u1 u3 u3 AR EERT AH s - s - s - s - YAA VROR XT iT iT iT iT M OTO EE VV VV VV VV TME RCCP M UUL O AP CSB TDEU I - A CERS .e TIT AD CS ELOE EI RETR N W O N F SC O OYT C LNE RLEL OAMB I RHA n d RGCV i n EEAO h o TTTM t y NNTE i e IIAR w B er ) s s u 12 3 R t t t W n n c NN N P e e u N ( mn mn r BB B O r ho ho t I l o l ci ci S Y T e i e ag ag R P s r s t e te t O I s e s tR tR r G R e t e A A o E C V n V e e p T S I rn rn p A E r r oi oi u C D o l o il il S t e t rt rt E M c s c el el e D E a s a te t e r O T e e e nB nB o C I R V R I I C 1 S SA L O C N 0 0 0 0 1 E M 5 6 7 e D E 3 3 3 3 O T 1 1 1 1 C I B B B B

2 2 47 / 7 S 4 FT e ES A IE / LU N EQ RER D ELS UM DE 3 ET HI CS S G N I S R U E O BS H MM UE D NT 4 0 I 2 R LAF L TO O O R T T N O C E re E N oc K I D a NY MO .f AR S AH l r YAA D XT ou M L EE VS TME E M UUL W CSB I A G TIT N CS I EI N N I N A O T C E R ER U S S E RP gn i 0 s N u B O o I H Y T R P D O I R G R C E C T S n A E i C D s E M d D E l O T e C I W 1 S S A L O C N 0 1 h E M D E 4 O T 1 C I B

.S FT ES A IE / LU N EQ RE R l l 1 a DES e LM n UE i DT m EI a H x ~ C e S ot' d 1 e R m ES r BM o ME f UT r NI ep LF AO e T b S O T T l N l E i N w E O E P l K M D a 0 NY O MO u2 0 AR C AH s - 0 YAA XT iT 5 M G EE VV TME N M D UUL I C CSB N B I ' A I TIT A e-CS T l EI E b 1 N R a N T O E C R n U i SS y d E r e R a c P d n n e L u r L o e A B fe g r P n N i s B O n a I i Y T a R P t t O I e s G R R e E C t. T S e s A E r em C D u re s ut E M s si D E e s O T r eP C I P r-pB my er t o sg ye 1 st a S AC SA L O C N 1 E M e D E l t O T l o C I A N

2 2 47 /7 S 4 FT ES AAA AAA I E /// /// LU NNN NNN EQ RE R D ELS UM DE 211 011 ET HI C S S R L E E BS S MM S UE E NT 844 022 V I L E AF R TO U O S T S E R P E E N K I D NY MO AR S AH lll lll YAB D XT ooo ooo M L EE VVV VVV TME E M UUL W CSB I A G h TIT N CS I EI N N I N A O T C E R E s s R ds d s U ld l d S el el s S We r Wed E W e Wl R l g l e P al n alW i a a i a ti h til A ntd c ntl N ) enl x ene C O re ree E reh I od erW erS Y T ti fe-t f e-R P aS mfo a mfo O I r umt e umt G R ey cu-H cu - E C nr rct rct T S ea ire l ire A E Gd Cie a Cie C D n Ch u Ch mo l s d l s E M ac lde i l de D E ee eab s eab O T tS h eu e h eu C I S( SHT R SHT 2 SS A L 0 C N 000 000 h E M 123 123 D E O T 111 111 C I CCC CCC

a = 2 '2 47 /7 S k FT e ES 1 1 A 2 A A A A IE 1 1 / 1 / / / /' LU N N N N N EQ 3 3 3 RER D ELS UM DE 2 2 0 0 0 0' 0 ET HI CS RE' S BS L MM E UE S NT 6 8 8 0 0 0 0 S I E L. V AF TO N O I T SDL E E e e re e E W c c oc c l K D a a a a a NY E MO f f .f f u2 AR L AH r r l rl r l s - YAB Z XT u u ouo u o iT M. Z EE S S VSV S V VV TME 0 M UUL N CSB I A G TIT N CS I EI N N I e N A l O T s b C E d d e d ni R l l t l es e e n al' e hs E W g. W o l a W We R n nn i Pn o c U i ) ii ) t i t ) s ) c S d c d c gm di da S 2 a r2 a e no .s a an E / e o/ e S iN' .d el eI R 1 h f1 h c l he h 's P n s r. e s r i r u on W rs ri ss o e s o i fi l oe o B l s ( Rss ( d n ee(V (l N ee l e a i2 ts e C O sn l t en l R e/ aslf l s I sk l usk l R1 l el o l s Y T ec e osc e e PVe ee R P Vi h hei h d h he hV O I h S tVh S i ts gd S d e S G R nT i T s il snn il f E C i o Wn o n wesiaosboo T S l t il t I sec tnit_ A E sa s a ssnre I s-e C D en e een e e eek ol e sed li l l ti l l l Vcfzl neli E M zm z zam z z z inzzeczs D E zo z zl o z z z nhi o zh c z n O T oN o oPN o o oiTeNoWAoI C I N N N N N N R N N 2 S S A L 0 C N 0 1 0 1 2 0 1 2 3 E M 1 1 2 2 2 3 3 3 3 D E O T 2 2 2 2 2 2 2 2 2 C I C C C C C C C C C

22 47 / .S 7 FT 4e ES A A A A IE / / / / LU N N N N EQ RE R S V E E D L LS A UM V DE 6 1 8 0 ET 1 D HI N C A S S P M U R P EBS MM G UE N NT 0 6 6 0 I I 2 0 1 P L 1 I AF P TO O T S LE S E S e e e e E E c c c c K V D a a a a NY MO f f f f AR R AH r r r r AB O XT u u u u Y. N F EE S S S S TNE M UUL S CSB T I A N TIT E CS M EI H N C N A O T C TA s s s s t t t t L n n n n A e e e e R m m m m G h h h h E c c c c T a a a a N t t t t I t t t t A A A A D d d d d N s e e e e C O l d d d d I e l l l l Y T s e e e e R P s W W W W O I e G R V y y y y E C l l l l T S e l l l l A E r a a a a C D u r g r r s r s g n g s g e g E M s e i e p e v e D E e t p t m t l t O T r n i n u n a n C I P I P I P I V I 2 SS A L O C N 0 0 0 0 1 2 3 4 h. E M D E O T 3 3 3 3 C I C C C C

2 2 47 / 7 S 4 FT e ES A A A A IE / / / / LU N N N N EQ RER D R E E LS T UM E DE 0 0 0 0 M ET A HI I C D S N I N R I EBS 2 MM UE N NT 0 0 0 0 A I H L T AF TO R O E T TA E R E G E K G D NY N MO AR I AH l l l l YAB T XT o o o o M L EE V V V V TME O M UUL B CSB I A G TIT N CS I EI N N I N A O T C ER E R U S S E R P E N s C O l s s s s I e d d d d Y T s u u u u R P s t t t t O I e S S S S G R V E C d d d d T S e n n n n A E r a a a a C D u g s s s n s s s e s E M s t i t p t v t D E e l p l m l l l O T r o i o u o a o C I P B P B P B V B 2 S S A L 0 C N 0 0 0 0 2 3 4 h E M 1 D E O T 4 4 4 4 C I C C C C

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A AA IE // / / // LU NN N N NN EQ RE R D ELS UM DE 80 9 0 10 ET 6 HI C S R EBS MM UE NT 20 9 0 80 I 9 1 4 L 3 2 AF TO G O N T I P I P E ee e e ee E N cc & c& c cc K I D aa a a aa NY MO ff .f . f ff AR S AH rr l rl r rr YAB D XT uu ouou uu M L EE SS VSVS SS TME E M UUL W CSB I A G TIT N CS I EI N N I N A O T C E n R l l i a a E n n 4 R i i U m m e S o o z S N N si E nS R d d o d P n l n l i el i e i e t pe Wd W d ciWd F 2 l 2 l eP l N / l e / l e n l e C O 1 saW 1 sa W nhaW I si si oci Y T etl et l Cntl R P snna snn a ana O I dk en dk e n h ren G R l cri l cr i cBri E C ei e d eie d n ed T S Whf u Whf u alf u A E Tmt Tm t ramt C D g ui g u i Bnui nl cg nl c g icg E M il rn il r n emrn D E paio pai o poio O T iWCL iWC L INCL C I P P P 2 S S A L O C N 0 12 0 1 2 0 12 e E M 1 11 2 2 2 3 33 D E O T 5 55 5 5 5 5 55 C I C CC C C C C CC

2 2 47 / 7 S 4 FT e ES A A I E / / LU N N EQ RE R D E LS UM DE 0 0 ET HI C S S R E E V BS L MM A UE V NT 0 0 I D L N AF A TO O S T PM U P E e e E N c c K I D a a NY MO f f AR S AH r r YAB D XT u u M L EE S S TME E M UUL W CSB I A G TIT N CS I EI N N I N A O T C E R E RU S SE R P G s N d s C O l d I e l Y T W e R P W O I g G R n y E C i d T S s o A E a B C D C s s ee E M pp vv D E mm l l O T uu aa C I PP VV 2_ S SA L O C N 0 0 h_ E M 1 2 D E O T 6 6 C I C C

2 2 4 7 0 / S 0 7 0 '4 FT 5 ES A A A A A A A A IE / / / / / / / / D LU N N N N N N ~N N C EQ B RER e l ba T 1 n D i ES LM d UE e DT i EI f H i C t S ne d i I s R a ES BM ME m UT e NI ts LF y AO s T S O y T T N b E N de E O t E P l l l l l l l l s K M D a a a a a a a a e NY O MO u2 u2 u2 u2 u2 u2 u2 u2 t AR C AH s - s - s - s - s - s - s - s - YAB XT iT iT iT iT iT iT iT iT e M G EE VV VV VV VV VV V V. VV VV r h-TME N M u UUL I CSB N s I A I s TIT A e CS T r EI E p N R N e O E b C RU s s s s s s ~ s s l1_ S t t t t t t t t i S n n n n n n n n w E e e e e e e e e R n n n n n n n n s P o o o o o o o o m p p p p p p p p e L m m m m m m m m t L o o o o o o o o i A C C C C C C C C d g g g g g g g g e H n n n n n n n n l N si i i i i i i i u C O l n n n n n n n n d I ei i i i i i i i e Y T sa a a a a a a a h R P st t t t t t t t c O I ee e e e e e e e s G R VR R R R R R R R E C d T S ee e e e e e e e n A E rr r r r r r r r a C D uu u gu u u u su u ss s ns s ss s es s s E M ss s is s ps s vs s m D E ee e pe e me e l e e e O T rr r ir r ur r ar r t C I PP P PP P PP P VP P i la to t 2 e S h S T A L O C N 1 0 0 0 0 0 0 0 0 h E M 1 2 3 4 5 6 7 8 e D E t O T 7 7 7 7 7 7 7 7 o C I C C C C C C C C N

22 47 / 7 S 4 FT e ES A A A A A A IE / / / / / / LU N N N N N N EQ RER DELS UM DE 1 0 0 0 0 0 ET HI C S N O I T R C E N BS U MM F UE NT 1 0 0 0 0 0 N I W L O AF D TO T O U T H S R E O E T l l l l l l K C D a a a a a a NY A MO u2 u3 u3 u3 u3 u3 AR E AH s - s - s - s - s - s - YAC R XT iT iT iT iT iT iT M EE VV VV VV VV VV VV TME F M UUL O CSB I A T TIT R CS O EI P s s N P t r N U n e O S i b C a b N s r u I t t n s n s S t S e e r M n R c o E o i p T p d l p S m n u u Y o - a - a s S S C r t ts td t r t e t g nt ny no np n A n er eH ep ey e N i mo m mp mT ms D O n h p hd h u h h r I i cp cn cS cd ce Y T a au aa a aa ab R P t tS t t e t o t r O I e t tl t p tL t o G R R At Aa Ay A As E C n c T t b T S e l e li l l n lA A E r an an ag aa a C D u ro ra rn rt rk s gp gh gi gs gc E M s em ec er en eo D E e t o t e t p t o th O T r nC nM nS nC nS C I P I I I I I 3 S S A L O C N 0 0 0 0 0 0 E M 1 2 3 4 5 6 D E O T 1 1 1 1 1 1 C I D D D 0 D D

22 47 /7 S FT 4h ES A A A A IE / / / / ' A A / / LU N N N N N N EQ RE R TL AA EV HOM D TE E NR LS E UM MT DE 2 0 0 0 0 0 NA ET IE HI AH C T S NL OA. CU,D I GS R NE E IR 8S L HM OR LE OO NT 2 0 0 0 0 0 CT I C L EA AF RE TO OR O C T D YN CA N E E, E GP l l l l l l K RU D a a a a a a NY EN MO u2 u3 u3 u3 u3 u3 AR MA AH s - s - s - s - s - s - YAC EE XT iT iT iT iT iT iT M L EE VV VV VV VV VV VV TME FC M UUL O CSB E I .A TR h TIT RE CS OH EI PP s s N PS t r N UO n e O SM i b C T a b NA s r u I t t n s n s S t SL e e r MA n R c o EV o i p TO p d l p SM m n u u' YE o a - a s S SR C r t ts td t r te t g nt ny no np n B n er eH ep ey e N i mo m mp mT ms D O n hp hd h u h hr I i cp cn cS cd ce Y T a au aa a aa ab R P t tS t t e t o tr O I e t tl t p tL to G R R At Aa Ay A As E C n c T t b T S e l e li l l n lA A E r an an ag aa a C D u ro ra rn rt rk s gp gh gi gs gc E M s em ec er en eo D E e t o te t p t o th O T r nC nM nS nC nS C I P I I I I I 3~ S SA L O C N 0 0 0 0 0 0 h. E M 1 2 3 4 5 6 D E O T 2 2 2 2 2 2 C I D D D D D D l{ i

2 2 4 7 /7 S 4 FT e ES A A .A A A A IE / / / / / / LU N N N N N N EQ RE R D E' LS UM DE 1 0 0 0 0 0 ET HI C S M OR F R L E A BS V MM O UE M NT 1 0 0 0 0 0' E I R LAF T TO A O E i~ H LA E U E D l l l l l l K - I D a a a a a a' NY S MO u2 u3 u3 u3 u3 u3 AR E AH s - s - s - s - s - s - YAC RL XT iT iT iT iT iT iT M O EE VV VV VV VV VV TME F0 M VV UUL OP CSB I A TE TIT RG CS OA EI PR s s N PO t r N UT n e O SS i b C a b NL s r u IE t t n s U n s S t SF e e r M n R c o-ET o i p a TN p d l p SE m n _u u YP o - a - a s S 4 SS C r t ts td tr t' e t '~ g nt ny no np n C n er eH ep-ey e~ N i mo m mp-mT ms D O n hp hd hu h hr I i cp cn cS cd ce Y T a au aa a aa ab R P t tS t t e to tr O I e t' tl t p tL to G R R At Aa Ay A As E C n c T t b T S e l e li l l n-lA A E r an an ag aa a C D u ro ra rn rt-rk s gp gh gi gs gc E M s em ec er en eo D E e t o t e t p to-th O T r nC nM nS nC nS C I P I I I I ' I 3_ SSA L O C N 0 0 0 0 0 0 E M 1 2 3 4 5 6 D E O T 3 3 3 3 3 3 C I D D D D D D

l 2 2 4 7 /7 S 4 FT h_ ES A A A I E / / / LU N N N EQ RE R D ELS UM DE 8 1 1 ET 5 6 3 HI 2 C S R E BS MM UE NT 3 3 1 Y I 3 4 3 R L 2 2 2 A AF M TO M O U T S TR E O E P l l l K P D a a a NY U MO u u u AR S AH s s s YAD XT i i i M E EE V V V TME P M UUL I CSB P I A h TIT 3 CS EI D N N N A O C 2 1 S SALC N O I T P I R C S E 1 2 3 D s s s M s s s E a a a T l l l I C C C O N h M E T I

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-^ NOTES 1. Per ASME Boiler and Pressure Vessel Code (BPVC), Section XI, 1983 Edition through the Summer 1983 Addenda. 2. Test pressure-temperature limits shall be maintained per Connecticut Yankee (CY) Administrative Technical Specifications (ATS) Section 3.4.A.1, Amendment 70, Revision 1 and Figure 3.4-1, Amendment 70, Revision 1. 3. Test pressure not less than nominal operating pressure 0 100% rated reactor power per ASME BPVC Section XI, IWB 5221. 4. Test pressure equal to 1.08 times the system nominal operating pressure @ 100% reactor power per ASME BPVC Section XI. Table IWB-5222-1. 5. Test pressure equal to the nominal operating pressure of the system per ASME Section XI, IWC 5221, IWD 5221, or IWD 5222. 6. Test pressure of 1.10 times the system pressure for design temperatures of 200*F (or less) per ASME BPVC Section XI, IWC 5222 or IWD 5223. 7. b Test pressure of 1.25 times the system pressure for design temperatures greater than 200*F per ASME BPVC Section XI, IWC 5222 or IWD 5223. 8. System pressure based on the lowest safety or relief pressure setting per ASME Section XI, IWC 5222. 9. System pressure based on the design pressure of the piping. 10. The chemical and volume control charging, seal injection, anJ 1etdown systems are in operation during normal plant operation and are continuously monitored to ensure integrity and performance. In addition, the potential for inadvertent overpressurization of the reactor coolant system causes additional concerns on the advisability of pressurizing a Class 2 system to considerably higher pressure than the adjacent Class I system. In lieu of the Code requirements and for the reasnns stated above, a visual examination at operating pressure will be conducted. Facility Operating License NODPR-61, Amendment 37, Section 3.1.3.1 granted relief for this alternate pressure testing. 11. Test pressure based on system pressure per Connecticut Yankee Administrative Technical Specification, Section 3.6, Amendment 88. 12. Although the auxiliary feedwater system is designed for 500*F, the o system, as operated, takes its suction from the demineralized water Q storage tank with contents below 200*F. CYAPCO will use the design pressure of 1250 psig times 1.1 for the hydrostatic test pressure. re47/7422

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The steam generators are'within the pressure boundary of' the main ] 13. steam and feedwater systems and reactor coolant system. Special precautions must be taken so as not to exceed the design maximum of j 840 psid pressure differential across the tube sheet. During the it will be necessary to adjust the reactor coolant system j)

test, j

. primary side) pressure to a point compatible with nil ductility (transition temperature while keeping the test media temperature on the steam /feedwater (eecondary. side) below a condition where steaming would occur. 1 14. System / component operating pressure per " Summary of Design i Conditions, Nuclear Power Plant - Unit.No.1, Connecticut Yankee 1 Atomic Power Company, Haddam, Connecticut," Revised 5/20/66. l l i

15. ' Design pressure / temperature per Specification CYS-579, Revised 12/10/65, " Shop Pabricated Piping'for Secondary Plant and' Primary k

Plant Waste Disposal and other Miscellaneous Systems." Design pressure / temperature per. Specification CYS-1550, Revised 16. 7/21/65, " Shop Pabricated Nuclear Piping." This system is required to have 116# of air for emergency operation 17. of the PORVs. The system shall not leak greater than.3 psi /hr, which will ensure system operability. c

18. A system inservice test is being performed to verify system operability as an augmented test requirement. A verification of piping integrity is not necessary for the system, so a system hydrostatic test will not be performed.

O re47/7422

13. The steam generators are within the pressure boundary of the main-steam and feedwater systems and reactor coolant system. Special .( precautions must be taken so as not.to exceed the design maximum of 840 psid pressure differential across the tube' sheet. During the. .] test, it will be necessary to adjust the reactor coolant system ~j (primary side) pressure to a point. compatible with nil ductility transition temperature while keeping the test media temperature on the steam /feedwater (secondary side) below a condition where steaming would occur.

14., - System / component operating pressure per " Summary of Design.

Conditions, Nuclear Power Plant - Unit No. 1 Connecticut Yankee Atomic Power Company, Haddam, Connecticut," Revised.5/20/66.-

15. Design pressure / temperature per Specification CYS-579, Revised, 12/10/65, " Shop Fabricated Piping for Secondary Plant and Primary Plant Waste Dieposal and other Miscellaneous Systems."

i

16. Design pressure / temperature.per Specification CYS-1550,' Revised 7/21/65, " Shop Fabricated Nuclear Piping."

1 17-..This system is required to have 118# of air for emergency operation of the FORVs. The system shall not leak greater than.3 psi /hr, j i vhich will ensure system operability. 18. A system inservice test is being performed to verify system operability as an augmented test requirement. A verification of piping integrity is not necessary for the system, so a system hydrostatic test will not be performed. l = 19. Connecticut Yankee is currently reviewing the ISI Program require-ments for system pressure tests. The information provided in the submittal may not reflect the actual testing that will be per-formed. A revision to the ISI submittal vill be provided when the review has been completed. l O t i re47/7422' J

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Text

SUMMARY

1.0 INTRODUCTION

2.0 DESCRIPTION

SUMMARY

1.0 INTRODUCTION

2.0 DESCRIPTION

SUMMARY

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