ML20203N849
| ML20203N849 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/30/1986 |
| From: | Lake L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20203N846 | List: |
| References | |
| PROC-860930, NUDOCS 8610200069 | |
| Download: ML20203N849 (138) | |
Text
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HOPE CREEK GENERATING STATION INSERVICE EXAMINATION PROGRAM SUBMITTAL FIRST 10-YEAR INTERVAL O
l Public Service Electric and Gas Company P. O. Box 236 Hancocks Bridge, New Jersey 08038 i
September 1986 O
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86-25P Inservice Inspecti'on Engineer V-SORC Chai e 8610200069 861010 PDR ADOCK 05000354 PDft 0
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HOPE CREEK GENERATING STATION INSERVICE EXAMINATION PROGRAM SUBMITTAL i
FIRST 10-YEAR INTERVAL j
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Public Service Electric and Gas Company P. O. Box 236 Hancocks Bridge, New Jersey 08038 i.
September 1986 Inservice Inspection Engineer SORC Chairman
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ABSTRACT
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i This document describes the basis for the first 10-Year Inservice Examination (ISI) Program for Hope Creek Generating Station. This document addresses the
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requirements of the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 1983 Edition, through Summer 1983 Addenda.
Included are Relief Requests and tables identifying those items subject to examination by Code Category and Code Item Number.
By law, Hope Creek Generating Station is committed, as a minimum, to develop this ISI Program to the 1980 Edition through the Winter 1981 Addenda of Section XI.
However, Public Service Electric and Gas Company has ' opted to upgrade this program to the 1983 Edition through the Summer 1983 Addenda, per 10CFR50.55a(g)(4)(iv), January 1, 1986.
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TABLE OF CONTENTS D
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1.
INTRODUCTION............................
a 1.l ' General............................
1 1.2 Applicable Editions and Addenda to Section XI.........
2 3
1.3 System Classification......
1.4 Examination Program Schedule.
3 2.
EXAMINATION PROGRAM REQUIREMENTS 4
4 2.1 Class l' Systems.
5 2.2 Class *2 Systems.
6 2.3 Class 3 Systems.
2.4 ASME Class 1, 2, and 3 Component Supports.
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3.
RELIEF REQUESTS................
3.1 General............................
8 3.2 Relief Request Submittals........
8 4.
REPAIRS, REPLACEMENTS, AND MODIFICATIONS 11 TABLE AND ATTACHMENTS Table 1 Hope Creek Generating Station Component and Piping Examination Summary Hope Creek Generating Station, Unit 1, Preservice Examination Limitations -
Relief Request 1 Hope Creek Generating Station ISI Boundary Diagrams a
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1.
INTRODUCTION
,s 1.1 General' 1.1.1 This submittal is a summary of the Hope Creek Generating Station Inservice Examination program (HCISI Program) for the first 10-year inspection interval. The first 10-year inspection interval will begin at commercial operation, which is presently scheduled for the end of 1986. Unless otherwise specified, the examination requirements identified herein will be in effect for the first 10-year interval.
1.1.2 The Construction Permit for Hope Creek Generating Station was issued in November 1974, and a 5% Power Operating License was issued in April 1986. A full Power License was issued in July 1986. Public Service Electric and Gas Company (PSE&G) is the operator of record and Bechtel Power Corporation was the A/E and installer of rece-d.
1.1.3 The HCISI Program, which consists of ASME Class 1, 2, and 3 sys-tems and components (and their supports), has been developed from information in the following documents:
Code of Federal Regulations, Title 10-Energy, Part 50, Para-graph 50.55a (the Regulation)
Section XI of the ASME Code,1983 Ed., through 1983 Summer i
Addenda (83S83)
Section III of the ASME Code Section V of the ASME Code USNRC Regulatory Guides:
Regulatory Guide 1.26, Rev. 3, February 1976, quality Group Classifications and Standards for Water, Steam, and Radioactive-Waste-Containing Components-of Nuclear Power l
Plants l
Regulatory Guide 1.147, Rev. 5, August 1986, Inservice Inspection Code Case Acceptability ASME Section XI, Division 1 Regulatory Guide 1.150, Rev.1, February 1983, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examination USNRC NUREGS NUREG 0313. Rev.1, July 1980, Technical Report on Material and Processing Guidelines for BWR Piping-NUREG 0619, November 1980, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking r
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NUREG 0800, July 1981, Standard Review Plan NUREG 1048 and Supplements 1 through 5, NRC Safety Evalu-ation Report for Hope Creek Generating Station ASME Code Cases N-307-1, Revised Ultrasonic Examination Volume for Class 1
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Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Examinations Are Conducted from the Center-Drilled Hole,Section XI, Division 1 N-408, Alternate Rules for Examination of Class 2 Piping,Section XI, Division 1 N-426, Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1,Section XI, Division 1-Hope Creek Generating Station FSAR Hope Creek Generating Station Preservice Examination Program -
The Pre' service Examination Program was conducted in accordance with 1977 Edition through the Summer 1978 Addenda of Section XI as amended by 10CFR50.55a(b)(2)(iv)(A). In order to make the PSI program consistent with the anticipated requirements for ISI, augmented examinations were performed on Class 2 RHR and ECCS piping welds. See NUREG 1048, NRC Safety Evaluation Report for acceptance of the PSI Program.
.s 1.1.4 An Inservice Examination Plan is being prepared for the examina-tions required by the HCISI Program. The examination plan will list each compo-nent examination to be performed and when scheduled.
1.1.5 The program for inservice testing of Class 1, 2, and 3 pumps and valves was addressed separately and submitted to the NRC for review.
1.2 Applicable Editions and Addenda to Section XI In accordance with Paragraph 10CFR50.55a(g)(4)(iv), the ISI requirements applicable to nondestructive examination and system pressure testing at Hope Creek Generating Station are based on the rules set forth in the 1983 Edition of ASME Section XI through Sommer 1983 Addenda, hereinaf ter referred to as ASME 1
Section XI.
In addition, the following considerations were implemented into the ISI program.
1.2.1 In lieu of the requirements in Paragraph 50.55a(b)(2)(iv)(A) of the regulation, FSE&G will incorporate the requirements of ASME Code Case N-408 for C) ass 2 piping welds in RHR, ECCS, and CHR systems. This Code Case has been approved by the NRC as referenced in Reg. Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI Division 1.
1.2.2 As permitted by Paragraph 50.55a(b)(2)(iv)(B) of the regulation,
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Class 2 piping welds will meet the requirements of ASME Code Case N-408.
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I 1.2.3 In accordance with Federal Register 48FR5532, Article IWE of ASME r ' ')
P Section XI has not been adopted by the NRC.
PSE&G has not incorporated the requirements of Article IWE into Hope Creek Inservice Examination Program.
1.2.4 NRC Question 210.14 in HCFSAR requested assurance that an augmented examination program consisted of 100% volumetric examination of all pipe welds in the break exclusion area (see NUREG 0800 Standard Review Plan 3.6.2).
At Hope Creek, High Energy Levels between containment isolation valves are Nuclear Class 1.
A 100% inspection of longitudinal and circumferential welds are volu-metrically examined during each inspection interval as defined by IWA-2400 of ASME Section XI.
Therefore, no augmented inspection program is required.
1.2.5 As permitted by Paragraph 50.55a(g)(4)(iv), PSE&G may elect, for certain components, to meet supplemental requirements as set forth in the edi-tions and addenda of the Code which become effective subsequent to the 1983 Edi-tion through the Summer 1983 Addenda of ASME Section XI.
Later editions and addenda of ASME Section XI or ASME Code Cases that are adopted by PSE&G will be identified to.the NRC.
It is the intent of PSE&G to continually apply appropri-ate Code changes, with NRC approval, which improve the overall quality of Hope Creek Generating Station examination programs.
1.3 System Classification 1.3.1 The classification of systems are in accordance with ASME Sec-tion III Nuclear Class 1, 2, and 3.
These classifications are based or. the requirements of 10CFR50 and the information in NRC Regulatory Guide 1.26.
See O
FSAR, Table 3.2.1, for the applicable Code Section, Edition, and Addenda, and other information applicable to specific components.
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1.3.2 The boundaries for Nuclear Class 1, 2, and 3 systems in the Inser-vice Examination Program are shown on the Inservice Inspection Boundary Diagrams in Attachment 2.
1.4 Examination Program Schedule Examinations for the 10-Year Interval will be scheduled in accordance with Inspection Program B, as described in IWA-2400 of ASME Section XI, for Class 1, 2, and 3 components and supports.
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EXAMINATION PROGRAM REQUIREMENTS The following is a detailed description of the examination program basis for components to be examined.
2.1 Class 1 Systems 1
i The Class 1 System Boundaries, as determined by requirements 10CFR50.2 and the Hope Creek Generating Station FSAk, are shown in the ISI Boundary Diagrams
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in Attachment 2.
These diagrams provide additional information on the extent of the examinations required under Table IWB-2500-1. In addition, examinations performed are summarized in Table 1 for each ASME Section XI Table IWB-2500-1 category and item number.
i 2.1.1 ASME Code Exemptions The following Class 1 components are exempt from volumetric and j
surface examination requirements in accordance with IWB-1220:
1 (1)
Components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary and that are of such a size and shape that upon postulated rupture i
j the resulting flow of coolant from the reactor coolant sys-tem under normal plant operating conditions is within the capacity of makeup systems which are operable from onsite emergency power.
(2)
Piping of 1-inch nominal pipe size and smaller.
(3)
Components and their connections in piping of 1-inch nominal i
pipe size and smaller.
!c (4)
Reactor vessel head connections and associated piping, 2-inch nominal pipe size and smaller, made inaccessible by control
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rod drive penetrations.
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2.1.2 Examinations 2.1.2.1 Reactor Pressure Vessel (RPV) and RPV Closure Head l
Examinations of the Reactor Pressure vessel will be con-ducted in accordance with Table IWB-2500-1 of ASME Section XI.
Refer to Table 1 i
of this submittal for the inspection summary of Class 1 components. Refer to Relief Request No. 1 for examination limitations.
The RPV examinations will be performed to meet the intent of the toquirements in Appendix A, " Alternate Method," of Regulatory Guide 1.150 Rtvision 1 and ASME Section XI.
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2.1.2.2 Other Components I
Examinations and pressure tests will be conducted in accordance with IWB-2500. Refer to Relief Request No.1 for examination limitations.
l Specific examination area selection criteria are amended by adopted Code Case N-426 (Extent of VT-1 Examinations, Category B-G-2 l
of Table IWB-2500-1).
l 2.2 Class 2 Systems The Class 2 System Boundaries are shown on the ISI Boundary Diagrams in.
These diagrams provide additional information on the extent of j
the examinations required under Table IWC-1220. In addition, the examinations j
to be performed are summarized in Table 1 for each Section XI Table IWC-2500-1 l
category and item number.
l 2.2.1 ASME Code Exemptions t
The following exemptions are applied in accordance with Code Case I
l N-408, Alternative Rules for Examination of Class 2 Piping,Section XI, Divi-sion 1, for all components (or parts of components):
(1)
The following components (or parts of components) of RRR, 1
ECC, and CHR systems (or portions of systems) are exempt from the volumetric and surface examination requirements of i
IWC-2500:
(a)
Vessels, piping, pumps, valves, and other components NPS 4 and smaller.
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Component connections NPS 4 and smaller (including i
nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components 1
of any size.
l (c)
Piping and other components of any size be,ond the last shutoff valve in open-ended portions of systems that do not contain water during normal plant operat-I ing conditions.
(2)
The following components (or parts of components) of systems (or portions of systems) other than RHR, ECC, and CHR sys-tems are exempt f rom the volumetric and surface examination 1
l requirements of IWC-25001 l
(a)
Vessels, piping, pumps, valves, and other components l
NPS 4 and smaller.
(b)
Component connections NPS 4 and smaller (including nozzles, socket fittings, and other connections) in O
vessels, piping, pumps, valves, and other components of any size.
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(c)
Vessels, piping, pumps, valves, other components, and component connections of any size in systems or por-tions of systems that operate (when the system func-tion is required) at a pressure equal to or less than i
275 psig and at a temperature equal to or less than 200 degrees F.
7 (d)
Piping and other components of any size beyond the last shutoff valve in open-ended portions of systems 2
that do not contain water during normal plant operat-ing conditions.
2.2.2 Examinations Examinations and pressure tests will be conducted in accordance with IWC-2500; however, the selection and examination of piping is in accor-4 dance with Code Case N-408.
Refer to Relief Request No. 1 for examination limitations.
2.3 Class 3 Systems The Class 3 System Boundaries are shown on the ISI Boundary Diagrams in These diagrams provide additional information on the extent of the examinations required under Table IWD-1220. In addition, examinations to be performed are summarized in Table 1 for each Section XI Table IWD-2500-1 category and item number.
2.3.1 ASME Code Exemptions i
The following exemption criteria are applied to Class 3 components and piping in accordance with IWD-1220.
IWD-1220.1 Integral attachments of supports and restraints to y
components that are NPS 4 and smaller within the system boundaries of Examina-tion Categories D-A, D-B, and D-C of Table IWD-2500-1 shall be exempt from the visual examination VT-3.
IWD-1220.2 Integral attachments of supports and restraints to components exceeding NPS 4 may be exempted from the visual examination VT-3 of j
Table IWD-2500-1 provided:
l (1)
The components are located in systems (or portions of sys-tems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emer-gency core cooling.
(2)
The components operate at a pressure of 275 psig or less and at a temperature of 200 degrees F or less.
2.3.2 Examinations Examinations and pressure tests will be conducted in accordance O
with IWD-2500.
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2.4 ASME Class 1, 2, and 3 Component Supports i
ASME Code Class 1, 2, and 3 component supports are examined in accordance with the requirements of IWF-2500. Component supports selected for examination are supports of those components that are selected to be examined by the surface, volumetric, or VT-1, VT-3, and VT-4 examination methods under the rules of IWB, IWC, and IWD. Relief Request No. 2 identifies that the snubbers on tiuclear Class 1, 2, and 3 components will be examined and functionally tested in accor-dance with Hope Creek Generating Station Technical Specification 3/4.7.5 and its associated bases; and therefore requests relief from the requirements of IWF.
Since IWE is not under the scope of this document, no component supports associated with IWE will be examined.
Examinations to be performed are summarized in Table 1 for each Section XI Table IWF-2500-1 category and item number.
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RELIEF REQUESTS.
t 3.1 General 3.1.1 During the PSI, there were cases where component configuration and/or interferences prohibited 100 percent ASME Section XI examination area coverage. In each case where such limitations were encountered, the details are documented in the Hope Creek Generation Station Preservice Examination Limita-tions Report (Relief Request 1).
Also included in Relief Request 1 is a supple-ment to the Preservice Examination Limitation Report which identifies limita-tions to examination areas when applying the coverage requirements of the 83S83.
For reactor vessel examination areas selected for ISI, the same conditions will prevail during the first inspection interval. Examination areas of other compo-nents are presented for information only and PSE&G will try to select welds with no limitations.
3.1.2 In cases where parts of the required examination areas cannot be effectively examined, because of a combination of component design or current examination technique limitations, PSE&G will continue to evaluate the develop-ment of new or improved examination techniques, with the intent of applying these techniques where an improvement in the examination can be achieved.
3.2 Relief Request Submittals Relief Request 1 - Class 1 and 2 Components Relief Request 2 - Snubbers 0
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Relief from Inservice Examination Requirements f
Relief Request:
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j Class 1 and Class 2 components.
Component Identification:
j Code Class: 1 and 2 Components Categories: Per Tables IWB-2500-1 and IWC-2500-1 Code Requirement:-
l For Hope Creek Generating Station surface and volumetric examinations shall be conducted in accordance with ASME B&PV Code,1983 through the Summer 1983 Addenda, Article IWB-2500 and IWC-2500, respectively.
Code Relief Request:
Pursuant' to 10CFR50.55a(g)5(iii), relief is requested from performing the inser-vice examination of the-inaccessible portions of the examination areas identi-fled in Attachment 1.
Individual weld numbers, area of coverage, bases for i
limitation and alternate examinations (if applicable) are identified. This attachment is a copy of the limitation report that was accepted by the NRC for the PSI program. Also included in Relief Request 1 is a supplement to the Pre-service Examination Limitation Report which identifies limitations to examina-c.
tion areas when applying the coverage requirements of the 83S83. Although not I
all of the welds contained in Attachment I will be selected during the first l
inspection interval, relief is requested for any of the velds listed in -
- which may be selected for examination. Those welds that are selected, if any, will be examined to the extent possible.
Basis for Relief:
Geometric configuration and permanent obstructions affect the ability to obtain complete Code coverage of the examination areas. The prevailing limitations j
and the specific relief as they apply to each weld are noted in the attached.
.The subject welds received volumetric examination by radiography and/or surface examinations during f abrication, in accordance with ASME Section III require-ments which provide adequate assurance of the structural integrity of the welds.
i Support for Relief / Alternate Examinations:
l An inservice hydrostatic test and inservice system leakage test will be conducted on the Class 1 and Class 2 pressure boundaries of which these welds are a part.
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_ Relief from Inservice Examination Requirements P.
Relief Request: 2 i
' Component Identification: Snubbers I
code Class:
1, 2, and 3 Examination Category:
F-C Code Requirement:
Article IWF-2000 required VT-3 and VT-4 inservice visual examinations of mechan-t ical and hydraulic snubbers. Article IWF-5000 requires inservice tests to be l
performed on mechanical and hydraulic snubbers. The number of snubbers subject
- to these requirements is 1086.
Code Relief Request:
l Pursuant to 10CFR50.55a(g)S(iii), relief is requested from performing the inser-vice VT-3 and VT-4 visual examinations and inservice (functional) testing to the requirements of the Code.
I Basis for Relief / Alternative Examinations:
Visual examinations and functional testing will be performed on Code Class 1, 2, and 3 (and other) snubbers in compliance with Hope Creek Generating Station O
Technical Specification 3/4.7.5 and its associated Bases.
Performance of examinations and testing to the requirements of the Technical Specification meet some of the Code requirements; however, this approach differs in the area of examination scheduling, reexaminations, and functional testing requirements, resulting in an increase in the overall level of plant' quality and j
safety.
The requirements of the Technical Specification became effective on April 11, 1986, the issuance date for the Low Power (5%) Operating License at Hope Creek Generating Station. The first visual examination of all safety-related snubbers j
and compensating struts is presently scheduled to be performed at least 4 months after but within 10 months of date of commercial operation. Functional testing will commence at the first refueling shutdown in accordance with the provisions and requirements of the Technical Specification.
l These mechanical and hydraulic snubbers and compensating struts were constructed and installed in accordance with the requirements of ASME Section III, Subsec-i tion NF.
Documentation of fabrication and installation examinations is stored st the plant site. Records of manufacturer functional testing results are avail-l able for drag force, activation and bleed rate (as applicable) in both tension j
and compression; as are records of the manual stroke testing of these component supports during the later stages of plant construction.
l This relief is requested for the entire first 10-year interval.
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REPAIRS, REPLACEMENTS, AND MODIFICATIONS National Board NR Stamp No. 36, PSE&G Nuclear Department Repair Program Manual, I
has been issued to cover repairs, replacements, and modifications. This manual l
incorporates the requirements of ASME Section XI which refers to the Code used 7
for construction at Hope Creek. Various editions of ASME Section III and ASME I
Section VIII were used during fabrication and construction. Hope Creek FSAR Table 3.2.1, as well as detail specifications available at the site, provide this information on specific components.
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TABLE 1 j
HOPE CREEK GENERATING STATION COMPONENT AND PIPING EXAMINATION
SUMMARY
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'L Tabla 1 IlOPE CREEK GENERATING STAT 104 INSERVICE EXAMINATION FROGR#l FIRST 10-TEAR liffERVAI.
EKAMINAT10N CATEGORIES Emmelnation Category 5-A PRESSURE RETAINING WELOS IN REACTOR VESSEL.
Itee Components and Parts Emmelnation No.
to Be Esamined Method Emmelnations to Re Performed Relief Request 10o.
i 81.10 longitudinal and Circue-Volumetric Circumferential and longitudinal I
ferential Shell Weld welds will be enantned. Enset-l nations will be performed at or j
near the end of the inspection
. Interval.
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Bl.20 Meridional and Circumfer-Volumetric Meridional and circumferential I
ential Head Welds welds of the closure head and lower head will im examined.
Emmelnations v111 be performed at or near the end of each inspection interval for the lower head.
Bl.30 Shell-to-Flange Weld Volumetric At least 50% of the weld v111 I
be emantned by the end of the first inspection period, and the reestnder by the end of the third inspection period.
f 81.40 Ilead-t o-Flange Weld Volumetric At least 50% of the weld will I
j and Surface be exaatned by the end of the 4
ftrat inspection period, and the remainder by the end of the third inspection period.
B1.50 Repair Area in Beltline Volueetric Not Applicable.
Not Applicable.
3-Regions j
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' Table 1 HOPE CREEK CENERATING STATION INSERVICE EKAMINATION PROGRAPt PIRST 10-YEAR INTERVAL.
EXANINATION CATECORIES l
Esselnation Category B-B PRESSURE RETAINING WEl.DS IN VESSEL.S OTHER THAN REACTOR VESSEL.S Itee Components and Parte Euseination No.
to Be Enseined Method Esselnations to Be Performed Relief Request leo.
R2.10 Pressure-Retaining Welds Volumetric Not Applicable.
Not Applicable.
through in Vessels Other Than B2.80 Reactor Vessels Page 2 af %
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Table 1 HOPE CREFJC CENERATING STATION INSF.RVICE EXANINATION PROGRAN FIRST 10-YEAR INTERVAL.
EXANINATION CATECORIES I
i Esselnation Category 8-D FUI.I. PENF;TRATION WEl.DS OF N0ZZ12S IN VESSEI.S - INSPECTION PROGRAN A Itee Cneponents and Parts Examination No.
to Re Exaelned Method Examinations to Be Performed Relief Request No.
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81.10 Full Penetration Welds Volumetric Not Applicable.
Not Applicable.
I through of Morales in Vessels -
R1.80 Inspectton Program A 1
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Table 1 IK)PE CREEK CENERATING STATION INSERVICE EXAMINATitMi FROGRAM PIRST IU-YEAR IltTERVAL EKAMINATION CATECORIES f
Examinatton Category B-D FULL PENETRATION WELDS OF MOZZLES IN VESSELS - INSPECTION PROGRAM B ltee Components and Parts Examination No.
to Be Examined Method Enaelnations to Be Performed Relief Request No.
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l Bl.90 Nozzle-to-Vessel Volumetric At least 251 but not more than i
Bl.100 Welds and Hozzle Inside 50% of the nozzles will be Radius Section examined by the end of the first period, and the remainder by the end of the interval.
51.110 Full Penetrattor4 Welds Volumetric Not Applicable.
Not Applicable.
through of Nozzles in Vessels --
Bl.160 Inspection Program B i
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O Table 1 HOPE CREEK CENERATINC STATION INSERVICE EXANINATION PROGRAN FIRST 10-YEAR INTERVA1.
EXANINATION CATEGORIES l
Examination Category
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8-E PRESSURE RETAINING PARTI AI. PENETRATION WEIAS IN VESSEL.S Ites Components and Parts Exaetnation No.
to Re Examined Nethod Enaminations to Be Performed Rettet Respeent No.
54.11 Vessel Nozzle Welds Visual (VT-2) 251 of each group of comparable Not Applicable.
size and function will be examined.
he examinations will be performed l
when the RPV is pressurized prior I,
to operation.
54.12 Control Rod Drive Nozzle Visual (VT-2) 251 of each group of comparable Not Applicable.
size and function will be emanined.
Welds n e examinations will be performed when the RPV is pressurized prior to operation.
84.13 Instrumentation Nozzle Visual (VT-2).
251 of each group of comparable Not Applicable.
Welda '
size and function will be examined.
n e emaninstions will be performed when the RPV is pressurized prior i
to operation.
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84.20 Hester Penetrations Visual (VT-2)
Not Applicable.
Not Applicable.
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j TaMa 1 1
HOPE CREEK CENERATING STATION INSERVICE EXAMINATION PROCRAM FIRST 10-YEAR INTERVAL 4
EXAHINAftDN CATEGORIES 4
Examination Category j
8-F PRESSURE RETAINING DISSIMILAR METAL WELDS l
k Itee Components and Parts Examinstton' I
No.
to Be Examined Method Examinations to Be Performed Rettef Request No.
85.10 Vessel Nozzle-to-Safe End Volumetric Dissimilar metal welds at Not Applicable.
Butt Welds t 4 Inches and Surface nozzles will be examined.
Nominal Pipe Diameter l
(Reactor Pressure Vessel) l H5.20 Vessel Nozzle-to-Safe End Surface Not Appitcable.
Not Applicable.
through Butt Welds < 4 Inches 85.120 l*)minal Pipe Diameter 85.130 Dissistler Metal Butt Welds Volumetric Dissimilar metal velds will be Not Applicable.
In Piping 2 4 Inches and Surface examined.
85.140 Dissimilar Metal Rutt Welds Surface Dissimilar metal welds will be Not Applicable.
In Piping < 4 Inches examined.
85.150 Dissimilar Metal Socket Surface Not Applicable.
Not Applicable.
Welds in Piping l
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Table 1 I
i HOPE CREEK GENERATING STATION INSERVICE EXANINAT1oM PROGRAN i
FIRST 10-YEAR INTERVAL EKANINATION CATECORIES i
Exaatnation Category B-C-1 PRESSURE RETAINING BOLTING, CREATER THAN 2 in. IN DIAMETER l
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lten Componente and Parte Examination
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No.
to Be Exaelned Nethod Examinations to Be Performed Relief Reaguest No.
2 4j l
B6.10 Closure Ilead Nuts Surface Examinatioa will be performed at 1
(Reactor Pressure Vessel) or near the end of the inspec-tion interval.
86.20 Closure Stude, in Place Volumetric Examination will be performed at Not Applicable.
(Reactor Pressure Vessel) or near the end of the inspec-tion interval.
B6.10 Closure Stude, When Removed Volumetric Stude will be examined if removed.
Not Applicable.
(Reactor Pressure Vessel) and Surface Examination will be performed at or near the end of the inspec-tion interval.
86.40 Threads in Flange Volumetric Examinetton will be performed I
(Reactor Pressure Vessel) at or near the end of the inspec-tion interval. 1-inch annular area around threaded hole will be examined.
B6.50 Closure Washers and Visual (VT-1)
Washers, and bushings will be Not Applicable.
i Bushings exantned upon stud removal.
(Reactor Pressure Vessel) l l
B6.60 Bolts and Stude, Flange Volemmet ric, Not Applicable.
Not Applicable.
through Surface, When Connection Visual (VT-1)
B6.170 Disassembled, and Nuts, Bushings, and Wastiers Par,e 1 of 34
"L Table 1 Il0PF, CREElt CENERATING STATION INSERVICF EXAMINATION PROGRAM FIRST 10-YEAR INTERVAL EXAMINATION CATECORIES Examinatton Category 8-C-1 PRESSURE RETAINING BOLTING, CREATER THAN 2 in. IN DIAMETER (Cont'd)
Itee Componente and Parte.
Emaetnation No.
to Be Examined Method Examinations to Be Performed Relief Request No.
56.180 Bolts and Stude Volumetric Bolte and stude will be exam-Not Applicable.
l (Pumps) ined. The bolting will be exse-l Ined in place under tension, when connection is disassembled, or l
when the botting is removed.
86.190 Flange Surface for Bolting Visual (VT-1).
Surfaces and I inch annular Not Appilcable.
When Connection le area around each stud hole will be Disassembled enantned when disassembled.
(Pumps) 1 B6.200 Nute, Bushings, and Washers Visual (VT-1)
Nute, bushings, and washers Not Apn1tcable.
l (Pumpe) will be enantned when disassembled.
56.210 Bolte end Studs Volumetric Not Applicable.
Not Applicable.
(Valves)
R6.220 Flange Surface for Botting Visual (VT-1)
Not Applicable.
Not Appitcable.
When Connection Is Dienseeabled (Valves) l l
R6.210 Nuts, Bushings, and Washers Visual (VT-1)
Not Applicable.
Not Applicable.
(Valves) 4 i
Page 8 of 14 1
i -
7tble 1 Il0PE CREEK CENERATING STATION INSERVl(7. EIANINATION PROGRAN FIRST 10-YEAR INTERV Al.
EXANINATION CATECORIES Exnetnatton Category PRESSURE RETAININC BOLTING, 2 f n. AND lESS IN DIAMETER 8-C-2 Examination lten Componente and Parts Examinations to Be Performed Relief Request No.
No.
to 8e Examined Nethod 87.10 Prwesure-Retalning Botting Visual (VT-t)
Not Applicable.
Not Applicable.
through 57.40 I
57.50 Bolts. Stude, and Note Visual (VT-1)-
Bolts, stude, and nuts will Not Applicable.
be enseined. The botting may (Piping) be examined in place under ten-ston or when removed.
87.60 Bolts. Stude, and Nute Visual (VT-1)
Bolts, stude, and nuts will Not Applicable.
be essetned. The botting may (Pumps) be exsetned in place under ten-ston or when removed.
57.70 Bolts Stude, and Nuts Visual (VT-1)
Bolts, stude, and nuts will Not Applicable.
be enantned. The botting may (Valves) he examined in place under ten-ston, when the connection is dis-assembled, or when the botting to removed.
57.80 Rolts. Stude, and Nuts Visual (VT-1)
Bolts, stude, and nuts in CRO Not Applicable.
housing will be enseined when dis-(CRD Ilousings) assembled.
Page 9 of 14
~
~~
n Table !
Il0PE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRMI FIRST 10-YEAR liffERVAL EXAll! NATION CATECORIES Exaelnation Category B-il INTEGRAL ATTACIBtENTS FOR VESSEt.S Ites Components and Parts Examination No.
to Be Exaelned Hethod Exaelnations :o Be Performed Itellef Reaguest.No.
88.10 integrally Welded Vessel Volumetric 1he accessible area of the 1
Supports or Surf ace circumference of the weld to the (Reactor Pressure Vessel) vessel will be exaelned.
88.20 Integrally Welded Vessel Volumetric
.Not Applicable.
Not Applicable.
through Supports.
or Surface 88.40 Page 10 of 14
C 1
uj I
Table 1 i
NOPE CREEK CF,NERATING STATIDN i
INSERVICF. EXAMINATinM PROCRAM l
FIRST 10-TEAR INTERV AL EKAMINATION CATEGORIES l.
J Exaetnation Category 8-J PRESSURE RETAINING WELDS IN PIPINC I
i Ites Components and Parts Examtpatton No.
to Be Examined Method Exaetnations to Be Performed Relief Request No.
j l
l 89.11 Circumferential Pipe Welds Volumetric 25% of the circumferential butt 1
1 2 4 Inches in Diameter and Surface welds, selected per Note (t) of Table IWB-2500-1, category 5-J.
will be enantned.
59.12 Longitudinal Pipe Welds Volumetric Adjoining longitudinal welds 1
2 4 Inches in Diameter.
and Surface for scheduled circumferential welds will be examined. One pipe-diameter length or 12 inches of l
each longitudinal weld tenRth will he enseined.
59.21 Circumferential Welds Surface 25% of the circumferential butt I
< 4 inches in Diameter welds, selected per Note (1) of Table IWS-2500-1, Category B-J.
will be essetned.
89.22 Longitudinal Pipe Welds Surface Not Applicable.
Not Appliemble.
< 4 Inches in Diameter 89.31 Branch Pipe connaction Volueetrie 25% of the branch connection 1
Welds R 4 Inches or Larger and Surface joints, selected per Note (1) of in Diameter Table IW8-2500-1, category B-J, will be exaetned.
59.32 Branch Pipe Connection Surface 25% of the branch connection Not Applicable.
Welds < 4 Inches in Diameter joints, selected per Note (1) of Table IW8-2500-1, Category B-J.
will be enseined.
59.40 Socket Welds surface 25% of the socket veldg.
Not Applicable.
l selected per Note (l) of Table IWB-2500-1 Category 8-J. will I
be examined.
4 i
l Page 11 of 14 i
i i
i l
f w
Table I HOPE CREEK CENERATING STATION l
INSERVICE EXAMINATION PROGRAM j
FIRST 10-YEAR INTERVAL, l
EXAMINATION CATECORIES Examination Category B-K-1 INTEGRAL ATTACIMENTS FOR PIPINC, PlHPS, AND VALVES I
i Itee Components and Parts Examination No.
to Be Examined Method Examinations to Be Performed Relief Requent No.
l I
i 810.10 Integrally Welded Attachments Volumetric 25% of the supports whose attach-Not Appitcable.
(Piping) or Surface ment base material is 5/8 inch and greater will be examined.
l 810.20 Integrally Welded Attachments Volumetric Attachments to pumps associated Not Applicable.
(Pumps) or Surface with piping selected under Cate-gory B-J whose attachment base material thickness is 5/8 inch and greater will be examined.
Blo.10 Integrally Welded Attachments Volumetric Attachments to valves associated Not Applicable.
f (Valves) or Surf ace with piping selected under Cate-gory B-J whose attachment base j
material thickness is 5/8 inch a
I anJ greater will be examined.
l i
t i
l l
Page 12 of 14
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on N
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SPVI F
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4 OiTTI 3
NOTG I
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it m
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p mu P
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s P e d
e n
l c
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f aa r
x g
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S t
i ne s
l s
eB a
ae e
n C
ng t
oo r a t
pt p
et o2 m
m t s g-o u
na eL C
P I C t -
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t1a-nL 0
0 1
2 l
eB s.
s e
2 2
s t o t
1 E
I N B
8
b s
i l
Table i HOPP, CREEK CENERATING STATION i
l INSERVICE EXAMINATIoM PROGRAM FIRST 10-YEAM INTERV At.
]
EXAMINATION CATECORIES Examinatton Categories R-N-1 and B-N-2 FRESSURE RETAINIMC WEl.DS IN VAI.VE BODIES I
Ites Componente and Parte Examination No.
to Be EmaetneJ Nethod Examinations to Be Forformed Relief Request No.
i 512.30 Valve Body Welds < 4 Inches Surface Not Applicable.
Not Applicable.
Noelnal Pipe Size l
1 j
R12.40 Valve Body Welds t 4 Inches Volumetric Not Applicable.
Not Applicable.
l Noelnal Pipe Stre 512.50 Internal Surfaces of Valve Visual (VT-3)
One valve in each group of Not Applicable.
Bodies on Valves > 4 Inches valves that is of the same con-Nominal Pipe Size struction and staller function will be enantned.
Page 14 of 34 i
e.
,O v
U Table 1
\\
i ilOPE CREEK CENERATING STATION i
INSERVICE EXANINATION PROGRAN
)
FIRST :D-YEAR INTERVAL j
EXANINATION CATECORIES l
Examination Categories INTERIOR OF REACTOR VESSEL INTEGRALt.T WEl.DED CORE SUPPORT STRUCTURES B-N-l and B-N-2 AND INTERIOR ATTACHNENTS To REACTOR /ESSEt.S 1
l Itee Compenente and Parte Exaetnation l
a No.
to Be Ensetned Nethod Emmelnations to Ee Performed Relief Request No.
1 i
l B11.10
. Vessel Interior Visual (VT-3)
Acceselble areas above and below Not Applicable.
1 reactor cara will be emnetned at tot i
refueling outage and every 3 yeare.
l thereafter.
I Bil.20 Interior Attichmente Withtr.
Yleual (VT-1)
Acceselble attachment velde will Not Applicable.
Beltline Regton be esseined at or near the end of the inopertion interval.
811.10 Interior Attachmente Beyond Vleual (VT-1)
Acceselble attachment welds will Not Applicable.
Beltline Region be enseined at or near the end of the inspection interval.
Bil.40 Core-Support Structuree Visual (VT-3)
Acceselble surfsces will be Not Applicable.
enseined at or near the end of the inspection interval.
811.50 Reactor Vessel Interior Visual (VT-1, VT-1)
Not Applicable.
Not Applienble.
through Attachmente and Core Support B1).70 Structure I
.Page 15 of 14
_.___g__.
\\
i TablaL.J J
i f
HOPE CREEK CENERATING STATION f
INSERVICE EKAMINATION PROCRAM FIRST 10-YEAR INTERVAL i
i EXAMINATION CATECORIES 4
1 Emanination Category i
B-O PRESSURE RETAIN 1NC WEIAS IN CONTROL ROO HOUSINCS l
)
Ites Componente and Farte Enamtnation No.
to Be Esseined
. Method Emmelnations to Be Performed Bellef Reaguest No.
l 514.10 Control Rod Drive Volumetric Welds to 10% of the peripheral Not Applicable.
l Housing Welde or Surface CRD housings will be enemined.
j (Reactor Vessel)
Esantnetton may be performed
}
st or near the end of the l-
. inspection interval.
4 i
i I
i i
l
.I i
Page 16 of 34
t*
,.,O Table 1 i
110PE CREEK CENERATINC STATION INSERVICE EXAMINATION PROGRAM FIRST 10-YEAR INTERVAL I
EXAMINATitWI CATECORIES a
I 1
Examination Category i
5-P At.t. PRESSURE RETAINING COMPONENTS l
1 l
Item Components and Parts-Examination No.
to Be Examined Nethod Examinations to Be Performed Relief Request th.
515.10 Pressure-Retaining Visual (VT-2)
Components will be examined Hot Applicable.
Boundartes for Vessel during system leakage test. Exam-instions will be performed in accor-l Components dance with IWs-5221 for each 3
refueling outage.
)
B15.11 Pressure-Retaining Visual (VT-2)
Components will be examined Not Applicable.
Boundaries for Vessel during system hydrostatic test.
4 Examinations will be performed j
Components once in accordance with IWB-5222 l
at the end of the inspection interval.
B15.20 Pressure-Retaining Componenta Visual (VT-2) -
Not Appitcable.
Not Appliccble.
l through 515.41 j
Rt5.50 Pressure-Retalning Visual (VT-2)
Components will be examined-Not Appitcable.
Boundaries for Piping during system leakage test.
Examination will be performed in Components accordance with IWB-5221 for each refueling outage.
RLS.51 Pressure-Retaining Visual (VT-2)
Components will be examined Not Applicable.
Boundarles for Piping during system hydrostatic test.
Components Examination will be performed in accordance with IWs-5222 at the end of the inspection interval.
B15.60 Pressure-Retatning Bound-Visual (VT-2)
Components will be examined Not Applicable.
i artes f or Pump Components during system leakage test.
I Examination will be perf ormed l
In accordance with IW8-5221 l
for each refueling outage.
I i
i l
l Page 17 of %
. _._ _. ~.._. _ __ _. _ _ _.. _ _.
Table 1
'I i
NOPE CRP.EK CENERATING STATION l
'1 INSERVICE EXAMINATION PROGRAM
)
PIRST 10-YEAR litTERVAL l
EXAMINATION CATE00 RIES i
Examinatton Cetegory B-P ALI. PRESSURT. RETAINING COMPONEDFTS (Cont'd)
Ites Components and Parts Examination No.
to Pe Examined Hethod Examinations to Be Performed Relief Request No.
315.61 Pressure-Retaining Bound-Visual (VT-2)
Components will be examined Not Applicable.
artes f or Pump Components during system hydrostatic test.
Examination will be performed in accordance with IWB-5222 at the end of the' inspection interval.
B15.70 Pressure-Jetaining Bemnd-Visual (VT-2)
Components will be enemined Not Applicable.
artes for Valve Components during system leakage test.
Examination w!!! be performed in accordance with IWs-5221 i
for each refueling outage.
l 815.71 Pressure-Retaining Bound-Visual (VT-2)
Components will be examined Not Applicable.
artes for Valve Components Juring system hydrostatic test.
Examination will be performed once in accordance with IWs-5222 at the end of the inspection interval.
Page 18 of M
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P en r
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I N 3t 8
1 v
Table 1 HOPE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRAN I
FIRST 10-YEAR INTERVAL EXAMINATION CATEGORIES Examination Category C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS 1
Itee Components and Parts Examination i
No.
to Se Examined Method Examinations to Be Performed Relief Request No.
l l
Cl.10 Shell Circueferential Welds Volumetric Welds at gross structural dis-Not Applicable.
continuities will be examined.
For multiple vessels of sluttar multiple vessels of stattar design size and service, exam-instions will be limited to one vessel.
Cl.20 need Circumferential Welds Volumetric Welds at gross structural dis-Not Applicable.
continuttles will be enseined.
For multiple vessets of sistlar design size and service, exam-instions will be limited to one vessel.
Cl.30 Tube Sheet-to-Shell Weld Volumetric Welds at gross structural dis-Not Applicable.
continuities will be examined.
For multiple vessels of similar design size and service, exam-instions will be limited to one vessel.
Page 20 of 34
p l
~
k _-
s-4 Table 1 l
j ll0PE CMEEK CENERATING STATION l
INSERVICE EKAMINATION P?OCRAM
]
FIRST 10-YEAR INTERVAL EXAMINATION CATECORIES 1
1 1
Examination Category
}
C-B PRESSURE RETAINING N0ZZI.E WELDS IN VESSELS 1
Item Components and Parts Examination No.
to Be Examined Method Examinations to Be Performed Relief Request No.
C2.10 Nozzles in Vessels 1/2-Surface Not Applicable.
Not Applicable.
and Inch Nominal Thickness
{
C2.11
. Nozzle-to-Shell (or Ikad)
Weld 1
i C2.20 Nozzles in Vessels 1/2-Surface and Nozzle selection and examination Not Applicable.
and Inch Nominal Thickness Volumetric area will be limited to one C2.21 Nozzle-to-Shell (or llead) vessel at the teretnal end of Weld 1/2-inch Nominal the piping selected under cate-Thickness gory C-F-2.
Manways and hand I
holes are excluded.
C2.22 Nozzle Inside Radius Section Volumetric Nozzle selection and examinetton I
area will be limited to one vessel at the terminal end of the piping selected under Category C-F-2.
Manways and hand holes are excluded.
C2.10 Nozzles with Reinforcing Surface and Not Applicable.
Not Applicable.
1 throingh Plate in vessels 1/2-Inch Volumetric l
C2.33 Nominal Thickness l
l l
Page 21 of 14
^
E
_O Tchts 1
]
l l
HOPE CREEK CENERATING STATION l
e INSERVICE EXAMINATION PROGRAM
'l i
l FIRST 10-YEAR INTERVAL EXAMINAT10N CATECORIES l
i-l Examination Category IltfECRAL ATTACIMENTS FOR VESSELS, PIPING, PUHPS, AND VALVES C-C Itee Components and Parts Emmeinstion No, to Be Emanined Nethod Examinations to Be Performed Relief Request No.
j I
I Integrally Welded Attachments Surface Attactuments whose base material Not Applicable.
l C3.10 is 3/4 inch or greater will (Vessels) be enseined. Selection is lietted to attachments on those components selected under Emme-ination Category C-A.
l C3.20 Integrally Welded Attachments Surface Attachments whose base material Not Applicable.
I is 3/4 inch or greater will (Piping) be emanined. Selection is lietted to thsse components selected under Examination j
Category C-F-2.
l
' Not Applicable.
C3.10 Integrally Welded Attactuments Surface Attachments whose base material is l
3/4 inch or greater will be examined.
{
(Pumps)
Selection is limited to those compo-(
o?nts selected under Emmelnation 2
Category C-F-2.
C3.40 Integrally Welded Attachments Surface Attachments whose base material is Not Applicable.
L 3/4 inch or greater will be emantned.
I (Valves)
Selection is limited to those compo-nents selected under Enseinstion t
Category C-F-2.
Page 22 of 14 -
M
-1
~ - - --- -
~x-
s
.I j
Table 1 HOPE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRAM i
f FIRST 10-YEAR INTCRVAI.
{
EXAMINATION CATECORIES i
Examinstinn Category C-D PRESSURE RETAINING BOLTING CREATER TilAN 2 In. IN DIANETER Item Components and Parts Examination No.
to Re Examined Nethod Examinations to Be Performed Relief Request No.
I C4.10' Bolte and Studs Volumetric
'Not Applicable.
Not Applicable.
l (Pressure vessels)
C4.20 Bolte and Stude Volumetric Not Applicable.
Not Applicable.
P ng)
(Pl i
l C4.30 Bolte and Stude Volumetric Not Applicable.
Not Applicable.
l (Pumpe)
C4.40 Bolts and Stude Volumetric Not Applicable.
Not Applicable.
(Valves) l 1
i Page 21 of 14
b Table 1 HOPE CREEE CENERATING STATION INSERVICE E "lNATION PROCRAN FIRST lis a'.AR INTERVAL.
I EKAHINATION CATECORIES l
Examinstton Category C-P-1 PRESSURE RETAININC WELDS IN AUSTENITIC STAINt.ESS STEEL. OR IllCN Al.tDYS ltee Componente and Parte Examination No.
to Be Examined Method Emmelnatione to Be Performed Relief Request No.
C5.10 Piping Welde in Austenttle Surface and Not Applicable.
Not Applicable.
Stainless Steel or litsh-Volumetric Alloy Piping ? 3/R-Inch Noetnal Wall Thicknese for Piping > NPS 4, Circumfer-ential and longitudinal C5.20 Piping Welds in Austenttle Surface and Not Applicable.
Not Applicable.
Stainless Steel or Iltsh-Volumetric Alloy Piping > l/5-inch Nominal Wall Thickness for Piping B NPS 2 and < NPS 4, Circumferential and 1.ongt-tudinal C5.30 Socket Welde in Austenttle Surface Not Applicable.
Not Applicable.
Stainless Steel or High-Alloy Piping C5.40 Pipe Rranch Connections in Surface Not Applicable.
Not Applicable.
Austenitic Stainlese Steel or liigh-Alloy Piping ? 7 NPS, Circumferential and langt-tudinal Page 24 of 34 1
j Table 1 l
IIOPE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRAM PIRST 10-YEAR litTERVAI.
EXAMINATION CATECORIES-l Examination Category i
C-F-2 PRESSURE RETAINING WELDS IN CARBON OR LOW At.LOY STEEL. PIPING 1
j ltee Components and Parts Exactnation l
No.
to Be Ermetned Method Examinations to Be Performed Relief Request No.
1 l
l C5.50 Piping Welds in Carbon or Surface and Welds will be selected per Not. Applicable.
l tow-Alloy Steel 3/8-Inch Volueetric Examination Category C-F-2 l
Piping 4 NPS, Circumferen-'
guidelines, tial or longitudinal C5.60 Piping Welds in Carbon or Surface and Not Applicable.
Not Applicable.
Low-Alloy Steel 1/5-Inch Volumetric Nootnal Wall Thickness for Piping NPS 2 and NPS 4, circumferential and tongt-tudinal C5.70 Socket Welds in Carbon or Surface Not applicable.
Not Applicable.
tow-Alloy Steel C5.80 Pipe Branch Connections in Surface Welds will be selected per Not Applicable.
Carbon or low-Alloy Steel Emanination Category C-F-2 2 NPS, Circumferential guide lines.
and longitudinal e
Page 25 of 34
Table 1 1R)PE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRAM l
FIRST 10-YEAR INTERVAL EXAMINATION CATECORIES Examination Category C-C PRESSURE RETAINING WELDS IN PUNPS AND VALVES l
Itee Cneponents and Parts Emaetnation No.
to Be Examined Method Examinations to Be Performed Relief Request No.
C6.10 Pump Casing Welde Surface Pump select ion and examination 1
areas will be limited to one pump for each piping run exam-Ined under Category C-F-2.
C6.20 Valve Body Welds Surface Not Applicable.
Not Applicable.
Page 26 of 34
\\
i
' Table 1 HOPE CREEK CENERATING STATION INSERVICE EXAMINATION PROCRAM FIRST 10-YEAR INTERVAL EKAHINATION CATECORIES Examination Category C-li ALI PRESSURE RETAIN 1NC COHPONENTS i
Ites Components and Parts Examination No.
to Be Examined Method Examinations to Be Performed Relief Request No.
4 l
C1.10 Pressure-Retaining Components Visual (VT-2)
Components will be enantned Not Applicable.
(Pressure Vessels) during system pressure test.
Examinations will be performed In accordance with IWC-5221 i
j for the inspection period.
C1.20 Pressure-Retaining Components Visual (VT-2)
Components will be examined Hot Applicable.
(Pressure Vessels) during system hydrostatic test.
Examinations will be performed i
in accordance with IWC-5222 at the end of each inspection interval.
C7.30 Pressure-Retaining Components Visual (VT-2)
Components will be examined Not Applicable.
(Piping) during system pressure test.
Examinations will be performed in accordance with IWC-5221 for 4
j the inspection period.
l C1.4 0 Pressure-Retaining Components Visual (VT-2)
Components will be examined Not Applicable.
(Piping) during system hydrostatic test.
Examinations will be performed in accordance with IWC-5222 for each inspection interval.
I C7.50 Pressure-Retaining Components Visual (VT-2)
Components will be examined Not Applicable.
(Pumps) during system pressure test.
Examinations will be performed in i
accordance with IWC-5221 for each l
inspection period.
i i
i Page 27 of 34
L/
d C{%
[
Table 1 IIOPE CREEK CENERATING STATION INSERVICE EKAMINATION PP.0 GRAM FIRST 10-YEAR INTERVAL EXAMINATION CATECORIES I
Examination Category C-Il ALi. PRESSURE RETAINING COMPONENTS (Cont'd) item Components and Parts Examination No.
to Be Examined Method Examinations to Be Performed Relief Request No.
I C7.60 Pressure-Retaining Components Visual (VT-2)
Components will be enemined Not Applicable.
(Pumps) during system hydrostatic test.
Examinations will be performed in accordance with IWC-5222 for each inspection interval.
C7.70 Pressure-Retaining Components Visual (VT-2)
Components will be examined Not Applicable.
(Va lves) during system pressure test.
Examinations will be performed in I
accordance with IWC-5221 for each l
Inspection period.
C7.80.
Pressure-Retaining Componente Visual (VT-2)
Components will be examined Not Applicable j
(Valves) during system hydrostatic test.
Exautnations will be performed in accordance with IWC-5221 for each inspection interval.
1 1
J 1
pap,e 28 of 14 4
^
Table 1 Il0PE CREEK CENERATING STAft0N INSERVICE EXAHlWATION PROGRAM FIRST 10-TEAR INTERVAL 4
1 EXAMINATION CATECORIES I
L Examination Category SYSTEMS IN SUPPORT OF REACTOR SilUTDOWN FUNCTitN4 D-A Item Components and Parts Emmelnation No, to Be Examined Nethod Examinations to Be Performed Relief Request No.
D1.10 Pressure-Retaining Compo-Visual (VT-2)
Components will be, examined Not Applicable.
nents in Support of Reactor during system pressure.or sys-l Shutdown Function tem hydrostatic test. Enseina-tions will be performed in accor-dance with IWD-5221 for each i
inspection period and performed once in accordance with IWD-5223 i
at the end of the inspection interval.
1 i
j Di.20 Integral Attachments Visual (VT-3)
Attachments will be examined Not Apglicable.
j through (i.e., Supports, Restraints, during the inspection interval.
Dt.60 Nechanical and Ilydraulic q
Snuhbers, and Shock
+
i Absorbers) 1 l
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..,N Taste 1 HOPE CREEK CENERATING STATION 3
INSERVICE EKAMINATION PROCRAM FIRST 10-TEAR INTERVAL EKANIMATION CATECORIES t
f Examination Cstegory SYSTEMS IN SUPPORT OF EMERGENCY CORE C00LINC, CONTAINNElff HCAT REMOVAL, ATHOSrilERE CLEANUP, AND REACTOR RESIDUAL ltEAT RENOVAL i
D-6 i
i Itee Components and Parts Emmelnation j
Ho.
to Be Examined Method Examinations to Be Performed Relief Request No.
l D2.10 Pressure-Retaining Compow nts Visual (VT-2)
Components will be enseined Not Applicable.
In Support of ECCS, QlR, AC, during system pressure test or and RRIIR system hydrostatic test. Exam-instions will he performed in accor-dance with IWD-5221 for each
~1nspection period and will be enseined once in accordance with l
IWD-5223 at the end of the inspec-tion interval.
i D2.20 Integral Attachments Visual (VT-3)
Attachments will be emantned Not Applicable.
i 1
through (i.e., Supports, Restraints, during the inspection interval.
D2.60 Mechanical and Hydraulic Sanbbers, and Shocit Absorbers) 4 1
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4 Page lo of 34
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Table 1 HOPF. CREEK CENERATINC STATION INSEMVICE EXAMINATION PROGRAM FIRST 10-YF.AR INTERVAI.
EXAMINATION CATECORIES a
Exactnation Category SYSTEMS IN SUPPORT OF RESIDUAL. IlEAT REMOVAL FROM SPENT FUEt. STORACE POOL D-C l
itee Components and Parta Examination j
No.
to Be Examined Method Enantnations to Be Performed Relief Respiest No.
D1.10 Pressure-Retaining Components Visual (VT-2)
Components will be enantned Not Applicable.
during.a system pressure or j
in Support of RHR froe Spent system hydrostatte test. Exam-Fuel Storage Fool inations will be performed in i
accordance with IWD-5221 for each inspection period and will be exam-ined once in accordance with I
IWD-5223 at the end of the inspec-l tien interval.
D1.20 Integral Attachments Visual (VT-3)
Attachments will be enantned Not Applicable.
i during the inspection interval.
through (i.e., Supports, Restraints, D1.60 Hechanical and Ilydraulle Snuhhers, and Shock Absorbera) i l
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D Tshls 1 MOFE CREEE CENERATINC STATION INSERVICE ERAMINATION FROGRAM FIRST 10-TEAR INTERVAL.
EXAMINATION CATECORIES Emmelnation Category F-A Pt. ATE AND SIIEl.t. TYPE SUFFORTS Ites Componente and Parte Exaetnation No.
to Be Emmetned Method Exactnettone to Be Performed Relief Request No.
F1.10 Mechanical Connections to Vlonal (VT-3)
Seleded component supports will Not Applicable.
through Pressure-Retalning Compo-be esselmed. Enantnation of F t.40 nente and Bettding Structure; component supporte any be per-Weld Connections to Butid-formed during normal system ing Structure; Weld and operetton or plant outages.
Mechanical Connections at Intermediate Jointe in Multiconnected Integral and l
Montntegral Supporte; and Component Displacement Settings of Cutdee and Stops.
Misalignment of Supporte, Assembly of Support Itene Page 32 of 34
.-.a O
O Table 1 NOFE CREEK CENERATING STATION INSERVICE EXAMINATION PROGRAM
]
FIRST 10-YEAR INTERVAL l
EKAMINAT101 CATECORIES T
Esselnation Category' LINEAR TYPE SUFFORTS F-8 i
Ites Componente end Parte Emmelnation No.
to Be Emmetned Method Enestnations to Be Performed Rettef Request No.
F2.10 Mechanical Connections to Visual (VT-3)
Selected component supports will Not Applicable.
l through Pressure-Retalning Compo-be exaetned. Esseination of i
F2.40 nente and Butiding Structures comp? nent supporte may be per-d Weld Connections to Butid-formed during normal systee i
ing Structure; Weld and operation or plant outages.
Mechanical Connections at
]
Intermediate Jointe in i
Multiconnected Integral and Montategral Supporte; and Component Dioptocement f
i Settings of Guides and Stope, l
Mlealtgoment of Supporte, j
Assembly of Support Iteme t
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Table I llorE CRF.EK CENERATING STATION INSF.RVICE EXAMINATION PROGRAM FIRST 10-YEAR INTERVAL EXAMINATION CATFEORIES j
Exaelnat ton Category a
F-C-Q MpONENT STANDARD SUPPORTS I
Item Components and parts Examinetton
]
No.
to Be Emmetned Method Exneinstions to Se Performed Relief Request No.
1 l
F3.10 Mechanical Connections to Visual (VT-3)
Selected component supports will Not Applicable.
i through Pressure-Retaining Compo-be exaetned. Examination of 3
F3.40 nents and Butiding Structure; component supports asy be per-l Weld Connections to Build-formed during normal system ing Structure; Weld and operation or plant outages.
j Mechanical Connections at 1
Intermediate Joints in Multiconnected Integral and i
Montntegral Supports; and Component Displacement j
Settings of Cutdes and Stops, Misalignment of Supports, j
Assembly of Support items F3.50 Spring Type Supports, Con-Visual (VT-4)
Selected component supports will 2 (Snubbers only) stant Imad Type Supports, be ensetned. Excetnation of i
Shocit Absorbers, Hydraulic component supports may be per-and Mechanical Type Snubbers formed during normal system I
operation or plant outages.
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i ATTACHMENT 1 i
1 HOPE CREEK GENERATING STATION, UNIT 1, j
PRESERVICE EXAMINATION LIMITATIONS l
b RELIEF REQUEST 1 A
t h
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1 HOPE CREEK GENERATING STATION, UNIT 1 PRESERVICE EXAMINATION LIMITATIONS FINAL REPORT f
4 SwRI Project 17-3690 t
Prepared for Public Service Electric and Gas Company Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 January 1986 Q :\\
. W.,
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) Q }i'
%, S O U T H W E S T R E S E A R C H I N S T I T U T E i
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BOPE CREEK GENERATING STATION, UNIT 1 PRESERVICE EIAMINATION LIMITATIONS REPORT FINAL REPORT Sv1I Project 17-3690 PrepartJ. for Public Service Electric and Gas Company Nuclear Department P. O. Box. 236 Hancocks Bridge, New Jersey 08038 January 1986 Prepared by Approved by ON ll.'
f h*Llb h ?!!hs Edward J. Peig s Wayne T. Flach Project Engineer Director Inspection Engineering Department of Engineering Services Nondestructive Evaluation Services and Technology Division 0
0
i 1
r TABLE OF C0hTINTS EAE:
1.
ILTRODUCTION 1
2.
DISCUSSION 2
3.
LIMITATION SUMMART 7tBLIS.
3 4
CONCLUSION 4
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.__,.-. ~.-.__,_.___ _ _ _.._..__~_,_
I Hope Creek Generating Station, Unit 1 Preservice Examination Limitations Final Report
- 1. Introduction Southwest Research Institute (SvRI) was contracted by Public Service Electric and Gas Company (PSE&G) to perform the preservice examination (PSI) of the Hope Creek Generating Station (ECGS).
Examinations were performed in accordance with the PSI Plan during the period of September 1983 through October 1985. During this period, any examination area coverage limitations which were encountered were recorded on data record sheets.
This report summarizes and documents the examination area limitations which limit Code coverage based on the examination requirements of ASME Section II,1977 Edition with r
Addenda through the Susaser 1978 and NRC Regulatory Guide 1.150.
- 2. Discussion PSI &G assisted by SwRI, focused significant attention to minimizing l
examination area limitations prior to, and during, the PSI at RCGS.
As a result of. these preparations, minimal examintion area limitations were encountered.. An Sw1I Access Engineering Program was implemented during plant design and construction to maximize
)
examination area access. This program evaluated access and provided i
design guidance to PSE&G and Bechtel Corporation for piping, components, and the reactor pressure vessel (RPV).
Examples of design criteria to facilitate examination included weld surface profiling, minimum access clearances for piping and components, and counterboring to minimize inside surface indication resolution questions.
The Access Engineering Program also designed track placement on the RPY to maximize the vessel mechanized examination coverage.
As a result, all vessel velds received at least partial volumetric coverage.
During the performance of the PSI onsite activities, PSE&G was i
notified of the examination area limitations that were encountered.
Each limitation was evaluated by PSE&G to determine alternative approaches which could afford a'more thorough coverage of the Code-specified examination volume or area.
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i Sw1I was requested to provide expertise in making recommendations of feasible alternatives to the planned examinations. This process was expanded to include consideration of future Codes and ISI conditions which may make alternative examination techn*. ques more or less valuable as determined on a case-by-case basis.
The result of this ongoing process was the completion of the PSI with the minimization of limitations to the examination coverage as required by the Code.
Special examination technique developments, supported by PSEM, unished examination coverage during the course of the PSI.
These include a UT technique for veld examination through corrosion resistant clad (CRC) piping in the Reactor Recirculation System.
This process involved basic research centered on ultrasonic. transducer development and testing on mockups which were a result of PSEM efforts to ensure similarity to the "as-built" condition of the CRC j
welds at RCGS.
An examination technique for the RPY closure stud was l
also developed to provide the~ examination coverage specified in the Code Case N307-1.
PSEM and SvRI also agreed to the utilization of a newly-introduced, automated ultrasonic examination system (AMDATA) j vhich provided additional capability for minimizing limitations attributable to weld joint configurations.
Further benefits of the AMDATA system included comprehensive recording of the test data for future comparison during ISI conditions.
These programs attest to the f act that PSEM and Sw1I performed the PSI at ECGS with full consideration of the factors that could maximize the effectiveness as determined by evaluation of the most minute details.
Even with a program of such proportions, limitations of two basic types were encountered.
Even with extensive examination procedure development, generic limitations were encountered inherent to examination areas and state-of-the-art examination techniques.
Inherent to the ultrasonic examinations where a full volumetric coverage is required from the entry surface to the opposite surface is the limitation at the near surface due to sound beam entry noise.
The second type of limitation is a result of scanning limitations due to component configuration or physical restrictions.
For example, a limitation to scanning due to an adjacent bracket or nozzle would prohibit the placement of the scanning device or transducer in a l
particular area and a scanning limitation would result.
For i
examination areas where track placement was impractical and where radiation exposure is considered to be acceptable for examiners during l
subsequent ISIS, the mechanized examinations were supplemented with l
manual examination techniques.
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- 3. Limitation suunnary Tables ne following tables provide details on the limitations which were encountand during the PSI at ECGS.
D e areas are listed in the order found in the PSI Plan. D e information in the tables is supplemented with figures and sketches as required.
Table 1 of this report 4
i provides information as follows:
he first column, " Class / Category / Item No.," identifies the ASME Code class, category, and item number for.the specific examination area identified in the second column.
Column 2 provides the i
examination area description and the examination requirement.
ne
'i third column, " Identification of Limitation" identifies the type of limitation and extent.
De following should be noted:
- 1) Examination volume limitations may be encountered, even when scanning of the complete weld length is possible.
- 2) In some cases, physical scanning limitations do not limit besa components from obtaining coverage beyond the physical limitations.
n is is possible when'the besa component can be directed to pass under the physical limitations, thus increasing total j
examination volume coverage.
- 3) Pressure vessel limitations have been identified by the percent of weld length accessible for scanning and the percent of the Code-required volume examined.
- 4) For piping, limitations are identified by their physical location or "L" dimension.
De fourth column identifies the " Basis For Relief" to include l
specific information with respect to the type of interference.
n e fifth column, " Fabrication NDE," describes the fabrication / con-
~
struction NDE that was performed to satisfy the requirements of ASME Section III.
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The " Remarks" column provides clarification of actual Code examination area limitations and information specific to later Code editions which may change the coverage requirements for subsequent inservice examinations. Where the Code specifies more than one method and complete coverage is o~btained, is also noted under " Remarks".
Table 2 provides a detailed listing of the percentage of volume coverage in compliance with paragraph 7 of Regulatory Guide 1.150,-
Revision 1, for reactor vessel welds.
The information provided includes percent of coverage for each angle used, as well as, the cumulative coverage.
The cumulative coverage is defined as the maximum percent of coverage achieved with at least one angle-bena component.
i l
The attached figures present a pictorial representation of the examination area coverage.
Figures are presented for the vessel welds I
and nozzle inner radii.
- 4. Conclusion i
The PSI program at RCGS was performed with full consideration of the limitations and capabilities of the nondestructive examination methods available. PSE&G and SwRI cooperated fully in an effort to ensure that the PSI was performed with the marinum cov.erage feasible.
This report is the documentation of the areas in which limitations were present that could not be eliminated through the combined efforts of PSE&G and Sw1I.
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Table 1 COMPONENT MTD PIPING LDfITATIONS l
e e
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.n a,,-,,,ne,,--,m,,
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S Reacter Vossel x
v Class Category Esanimation Areal Identificattom of j
isee No.
Emmelnation Requirement Liettation Basis far Rollef Fabrication HDE Remarks i
I j
l arvi-W1 Complete volumetric esse-Flange configestation pro-Volismetric and Surf ace See Figures I and 4.
B-A Shell-to-Flange ination of base estal htbits scannin5 f ree the See Table 2, Sheet 1.
38.10 Circueferenttal Weld ad jac ent to weld was not flange side of the weld.
Emmetmation was performed obtained. Approstaately Thereocouple pads lleited manually.
j Valuestric 972 of the weld length scanning from the shell 1
was acceselble for scen-side of the weld in two j
n ' =ng. See Table 2 for regions.
j percent of volume coverage for each bene component.
4 j
j l
Brvi-W4 Complete volesmetric cow-Proximity of the N12 Volumetric and Surface See Figure 1.
I B-A Shell-to-Shell erage of weld and base noaales llette scanning
'See Table 2, Sheet 1
]
tl.lt Circaseterential Weld metal was not obtaineJ.
from both sides of ties Esamination was performed l
Approsteetely 90% of the weld in four restons.
eenwally.
Volumetric weld length was acces-J sible for scanning. See Table 2 for percent of wolesse coverage for each beam component.
j l
arvi-W5 Complate valuestric cow-Prostetty of M4 metales Volueetric and Surf ace See Figure 1.
t-4 Shell-to-Shell erage of the weld and llette scanning f ree See Table 2, Sheet 1.
I 84.11 C6tcueferential Wald base metal was not above the weld in mis Enamination performed obtained. Approslaately locations. Prostelty of mechani seJ.
Volumetric
- 62% of the weld length N5 norales llette scan-
}
was accesalble for scan-ning tros,elther side of
, ming. See Table 2 for the weld in iner regions.
percent of volume cow-location of nosales pro-erage for each beam com-hibite Installing verti-i ponent.
cat track in three locations.
i j
l Brvi-W6 Complete valueetric cow-The prostetty of N16 and Volissetric and Surf ace See Figure I.
B-A Siwil-to-Saelt eroge of time weld and NIF nozzles prohibite See Table 2, Sheet 8.
Bl.ll Circuaterential WalJ base metal was not scanning frne either side Esselnation performed obtained. Approstaately of the weld in four loca-eschanised.
valueetric 41% of the weld length tions. l.ocation of natales j
was acceselble for scan-prohibits testallation of alng. See Table 2 for circumferential track and
]
percent of wolisme cow-lastallation of vertical erage for each beam com-track in four locattor.s.
i panent.
locations.
i
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l IslTE:
A 21 valueet ric Italtat ion inherent to the keector Pressure Vessel Weld Emaelnations is the result of laterface notee at the sound beae entry at the e.iteide vessel surface. See USNRC Regulatory Culde 1.150, Revision I, raragraph B.), "Near-Surface Esamination and Surface Re sol ut len."
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SYSTENs Reactor vessel (Cont'd)
I i
Claes C&tegory
,Esamleatton Areal IdentifIcatton of I
Is ee W.
Eumelnation seguirement Limitation Basle for Rollef Fabrication IIRE Remarke I
prvi-WF 100E of the weld length N/A.
Volueetr8c and Surf ace See l'!aute 2.
B-A Shell-to-Shell wee acceselble for scan-See Table 2, Sheet I.
l Bl.lt Circienf erent 8al Wald elas. See Table 2 for Emmelmation performed l
percent of volume cow-sec t.an t sed.
l VolueetrIc erage for each beam com-i ponent.
1 1
Ervi-US Complete volumetric cow-Interf erence f ree welded Volisestric and Surf ace See rigure 2.
l t-4 Shell-to-l.ower HeeJ erste of weld and base insulatton pade lletted See Table 2. Sheet 1.
84.11 Circumferential Wald metal was not obtained.
scanning at eight loc a-Enamination performed r
i Approstaately 872 of alie stune and prostetty of mechantsed.
Valueetric weld length wee acces-the N1 noszles tietted
[
elble for scanning.
scanning at two locatione.
i See Table 2 for percent I
cf volume ccwerage for each bene component.
t j
l Rrvi-Wil-l 100% of the weld length N/A.
Volumetric and Surf ace See Figure 1.
B-A t.omgitudinal Weld was acceselble f or scan-See Table 2. Sheet 1.
58.12 9 30 Iseg ming. See Table 2 for Esmeinetton performed j
percent of valueu cow-manually.
y i
valueetste erage for sach been com-3 posset.
I krvl-Wit-2 100% of the veld length 31 / 4.
Votismetric and Surf ace See Figure 1.
t-A longitudinal Weld was accessible for scam-See Table 2 Sheet 2.
9 150 Des minig. See Table 2 for Eneminattaa performed Bl.12 percent of volume cow-manually.
Volumetric erage for each beam com-ponent.
1 l
Mrvl-Wti-1 cmplete valuest ric cow-Prostetty of nossles N3C Valueetric and Surface See Figure 1.
l
't-4 tongitudlual Weld areas of the base metal amt N3D limited scanning See Table 2 Sheet 2.
38.12 9 270 taeg was not obtained. 8001 la two locat ione.
Emmelnation performed l
of time weld length was manually.
j volumetric acceselble for scanalas.
t See Table 2 for percent i
of volume coverage for j
each beam component.
4
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fesfEI A 2% walueetric limit at ion inherent to time keactor Pressure Vessel Wald Esselsatlops le the result of interface notes at tlie sound ' heae j
ruary ma s t.e outmIJe weasel surface. See USNRC Regsslatory Guide 1.150. Res taton I. I armarayli s.3, "Near-Surf ace Emaelnat ion end Seiriace 1
Resulotlow."
.i k,
1 m
k s
y
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SYSTtJes Reactor Vessel (Cont'd)
Class Category Esselnation Area /
Identification of It ee eso.
Esemination Requirement Limit at t aa tests for netter fabrication leDE senarks I
arvi-Wlf-l 100% of the weld length N/A.
Valueetric aM Surface See Figure 1.
B-A longituJinal Wald was acceselble for scen-See 1able 2, sneet 2.
31.82 9 Ito Des alas. See Table 2 for Esasination performed manu-percent of volume cow-ally and mecleanteed.
Voluestric erage for each beam com-ponont.
I RPVI-W12-2 Complete volumet ric cow-Fromletty of 184D and NSB Volumetric and Surf ace See Figure 1.
B-A Longitudinal Wald erage of the welJ and nozzles limits scanning See table 2, Sheat 2.
Bl.12 0 21o pes base metal was not to two locatione.
Emmetmation perf ormed mane-obt a lned. Approntmately Walded insulation pad ally and mechanised.
Voluentric 963 of the weld length limits scanatar in one was accessible for scan-location.
ning. See Table 2 for percent of volume cow-erage for each twee com-ponent.
I RPVI-Ul2-3 100% of the veld length N/A.
Volumetric and Surf ace See Figure 1.
B-4 Longitudinal Weld was acceselble for scan-See Table 2. Sheet 2.
On St.12
@ 350 beg ning. See Table 2 for Esselnattou performed manu-percent of volume cow-ally and mechantzed.
Volumetric erage for each beam com-ponent.
I trvl-Wii-l Complete wolismetric cow-Frostetty of.N12A norsle Volumetric and Surf ace See P8gure I.
S-A l.unglandinal Weld erage of time weld and limits scanning in one See Table 2. Sheet 2.
Bl.12
@ M Deg base metal was not location.
Esselnation performea obtained. 8001 of the mechantred.
Volueetric weld length was acces-sible for scanning. See Table 2 for percent of volume coverage f or each baas component.
I RPyl-wll-2 Complete volumet ric cow-Prosta'lty of the N94, Volumetric and Surf ace See Figiere 1.
t-A t.omgituJinal WelJ erage of tl.a weld and N17R. and N16B nosales See Table 2, Sheet 2.
31.12 9 155 Deg base metal was not limite scanning in two Esamination performed obtaimed. Approaleately locattons.
mechantred.
Valumetric 68% of slee weld lenath was accessible f or sc an-ning. See Table 2 for percent of volume cow-erage for each bene coe-ponent.
Insit : 4 21 valueet ric limitetten t-
- ent to the Rearter Pressure %essel Wald Esselnations is (le result of interface noise at slie sound beam entry at it.e u a sIJe wesul
's.
See tISNRC Regulatory Guide 1.350, Revistoss t. Paragral i S.3, "Near-Sur f ace Eamminat ion anJ Surf ace d
Resaluttoes."
I i
i
t Vessel (Cent'd)
STStaat t
Cl.
Id**EIIICE8888 "I Fabricralee last remarks E88888881** Af*3I Basis for Relief Cateserf Etelsattoe Itee %
Psaminatlom seguirement Voluentric and Surf ace See Figure I.
100E of the weld length N/A.
See Table 2. Sheet 1.
l ervi-Wi)-1 was acceselble for scan-Esaminatten percorned 5-A langitudinal WId Bl.12 9 275 Den ning. See Table 2 f or enchantsed.
pas.:ent of welues coverage for each been Volumetric component.
Volumetric and Surface See Figure 2.
3001 et the weld length N/A.
See Table 2, Sheet 1.
I arVI-Wie-I was acceselble for scam-Esaonnetton performed B-A l.oegiswJinal Weld 33.32 9 90 Deg ning. See Table 2 for secW nlsed.
percent of volume coverage for each boas Velueetric component.
Valuestric and Surf ace See Figure 2.,
800E of the weld length N/A.
See Table 2. Sheet 1.
I SFVI-Ule-2 was acceselble for scen-Esamination performed B-A leasituJInal Weld nlag. See Table 2 for mechea t sed.
31.12 9 210 beg percent of welume coverage for each base Volumetric component.
Frostelty of NI7D and Voluestric and Surface See Figures I and 2.
5es Table 1 Sheet 1.
1 Revi-Ut4-1 Completa weluestric cow-B-A Longitudinal WelJ etage of the weld and NibD nostles llette Esaelnation performed base metal wee not scanning at the top of sechantred.
Bl.12 9 130 I=g obtained. Approsteately the weld.
%1 of the wuld length Volumetric was acceselble for scan-ning. See Table 2 for percent of volume coversee for each beam F
-d component.
i RFvi-WIS-I Complete valuestric cow-Frostetty of NIA and Volumetric and Surface See Figure 2.
See Table 2, Slieet 1.
B-A langitudinal Wald erase of the weld and N2A mozzles llette Esaelmation perf ormed scanning in two areas of enchaatsed.
bene metal wee not Bl.82 9 IS Des obtained. Appresleat ely the weld.
911 of the weld length Volumetric wee acceselble for scan-ming. See Table 2 for percent of volume coverage for each bsaa component.
le the result of laterf ace notee at the sound bene to the teactor Pressure Vessel Wald Esselnatione See llSsseC begulatory Culde 4.150, Beulalon 1. Paragraph B.1, *Ilmar-Surf ace Emaninet tun and Surf ace senEs A 21 valueetric llettation inherent entry at thw ausalJe vessel surf ace.
Resoluttun."
(
SYSTEN: mesctor vessel (Cont'd)
Class 3
Cctegory Enaminaston Areal identiftestIos of item No.
Esselnation Requirement 1.leltation Baslo for Relief Fabricatlos NDE Remarks I
spVI-W15-2 500E of the weld length N/A.
Volueetric and Surf ace See Figure 2.
t-4 Innstandinal Wald was accessible for scan-See Table 2 Sheet 3.
38.12 9 118 B eg ning. See Table 2 Emmelnation performed for percent of volesse mechantzed.
voliseetric coverage for eacle beas component.
I syvl-W15-3 1002 of the weld length N/A.
Volueetric and Surf ace See Figure 2.
3-4 t.ongitwJinal Weld was accessible for scan--
See Table 2, Sheet 3.
Bl.12 9 258 Deg alng. See Table 2 Esaminat tom perf ormed for percent of volume mechantmed.
Volumetric coverage for each bene 1
component.
j l
spVI-Wl6-1 Complete valuestric cow-Support ak t rt attachment volumetric and Surface See Fagere 2.
B-A tmuer HeaJ etage of Else weld and limits scanning in one See Table 2, Sheet 4.
Bl.22 HertJtonal Wald base metal was not location.
Esamtmation performed 9 22.5 lies obtained. Approsteately mechaatsed.
821 of the weld length Votismet ric was acceselble for scan-sing. See Table 2 l
p j
O for percent of volume coverage for eacin beme i
componen t.
a l
upvi-Wit-2 Complete volumetric cow-Support skirt attachment Volumetric and Surf ace See Figure 2.
5-A Lower Head erage of the welJ and limits scanning in one See Table 2, Sheet 4.
j 58.22 sterlJIonal Wald base metal wee not location.
Esseination periormed 9 67.5 peg obtained. Approutestely mechanteed.
821 of the weld length valueetric was accessible for scan-ning. See Table 2 for percent of volume coverage for each bene ccaponent.
I kpvi-Wio-3 Complete valueetric cow-Support ektre attachment Votismetric and Surf ace See Figure 2.
I t-4 3.uuer ticad etage of the weld and llette meanning in one See table 2. Sheet 4.
I Bl.22 Merldtonst Weld base metal wee not location.
Esmeinstion performed 8 182.5 twg obtained. Apprus t eat el y mechanized.
i 321.of the weld length valueetric was accessible for scan-
{
ning. See Table 2 l
for percent of vulume coverage for each t.eae I
component.
}
CITt': A 21 volemmet ric lleltat ion inherent to the Reactor pressure Vessel Weld Emmelnations is the result of interface notee at the sounJ heae i
ei.try at a l.e outstJe vessel murface. See USts'tC Regulatory Guide 4.150, Rev telon I, paragraph B.3, "Near-Sur f ace Esselnation asmi Surface kemulut lue."
i t
k SYSTDis Beacter Vessel (Cent'd)
Class Category Esselnation Areef Identificatten of I t es sea.
Esamination Requirement Eletterton Basis for Relief Fabrication NDE hemark s I
apVI-W16-4 Complete volumetric cow-Support skirt at t achment Valueetric and Surf ace See Figure 2.
B-A Imwer Head erage of the weld and llette scanatas in one See Table 2. Sheet 4.
31.22 MerlJtenal Weld base estal was not location.
Emaelnation performed 9 157.5 Dog obtained. Approateately mec han t eed.
821 of the weld length j
Valueet t ic was accessible for scan-ning. See Table 2 for percent of volume coverage for each bene component.
l apVI-Wlb-5 Complete valuestric cow-Support ektre attachment Voluestric and Surface See Figure 2.
3-4 l.ower HeaJ erage of the weld and 14ette scanntsg in one See Table 2, Sheet 4.
Bl.22 N rldlonal Wald base metal was not location.
Ezeelnation perfors=J i
9 202.5 Deg obtataed. Approstsately archanl sed.
821 of the weld length Volueetric was acceselble for scan-4 ning. See Table 2
}
for percent of volume 4
e coverage for each bene H
j component.
1 l
l SpVI-Wl6-6 Complete volumetric cow-Support ektre attachment Valueetric and Surface See Figure 2.
i B-A Imwer Head erage of the weld and limits scanning in one See Table 2, Sheet 4.
I Bl.22 Merldlonal Wald base metal was not location.
Emmelnation performed
}
9 247.5 Des obtained. Approstaately mechaatsad.
}
82% of the veld length i
valueetric wee accessible for scan-
{
ning. See Table 2 j
for percent of volume f
coverage for each base j
component.
1 l
I apVI-WI6-7 Camplete valuestric cow-Support ektre attachment Volumetric and Surf ace See Figure 2.
L l
B-A Imwer Head erage of the weld and llette scannism in one See Table 2 Sheet 4.
51.22 MerlJBonal Weld base metal was not location.
Esaetnation performed i
I
- 292.5 Deg obtained. Appros taat ely mechantaed.
l 825 of the weld length Volueetric was accessible lor scan-l ning. See Table 2 I
for percent of volume coverage for each twee component.
j 4
w!
]
tairE A 21 welumetric limitation inherent to the Reactor pressure Vessel Weld Esselnatione is the result of interface notee at the sound beae entry at al.e outstJe vessel surface. See llSNRC Regulatory Culde 1.850, Revis* w 1. paragrali s.3, "Near-5urface Emmelnation and Surface d
Resuluttun.*
1 i
/h V
SYSTEM Reacter Wessel (Cost'd)
Class s
Category Esselmation Aresi identification of lire 8ks.
Esselnation Begestrement Liettation Basis for Belief Fabrication teDE semarks a
4 i
I arvi-Wl6-g complete valueetric cow-Support eLirt at t aclement volumetric and Surf ace
'See Figure 2.
}
5-A Imeer llead stage of the weld and limits scanning in une See Table 2 Sheet 5.
Bl.22 Herldtonal WelJ base estal was not location.
Esmeination performed mechanised.
i
@ 31?.5 Deg obtained. Approsteately i
321 of the weld length volumetric was acceselble f ar ocas-j ning. See Table 2 tot percent of volume coverage for each beae component.
Brvi-W9 Complete coverage of Frostetty of control rod Volueetric and Surface See Figure 2.
J B-A l.ouer tiend Dume eles base estal was not drive mechantees !!alte See Table 2, Sheet S.
31.21 Circumferential Weld obt ained. 100% of the scanntag tros below the Esamination performed weld length was acces-weld but does not appre-eechaatsed.
Volumetric alble for scanning.
clably lapact coverage.
See Table 2 for percent of volume coverage for each beam component.
I f
I arvi-W2n Complete valuestric cow-Flange configuration Valueetric and Surf ace See Figure 3.
i e-*
S-A Closure llead-to-Flange erase of the veld and prohibite scanales free See Table 2 Sheet 5.
88.48 Circumferential Wald base estal was not the flange steg of the Esaminat ion perf ormed manu-N j
obtained. 100% of the weld.
ally. Surface eseelnation l
volumetric and Surface weld length was acces-coverage was obtstneJ.
alble for scanning.
See Table 2 for percent of volume coverage for j
each beam component.
j I
prvi-U22 Complete volumetric cow-N/A.
Volueetric and Surface See Table 2, Sheet 5.
B-A Cloeure Head Ibse etage of the weld and Esselnation performed i
58.28 Circumferential Wald base metal was not manually.
1 obtained. 100% of the l
Volueetric weld length was acces-alble for scannlag.
See Table 2 for percent of volume coverage for 4
j each beae component.
)
(
I j
983TE: A 25 voteemetric llettation Inherent to tiee peactor Pressure Vessel Weld Esselnations le the result of laterf ace noise at the sound he.ae entry at the out s tJe vessel sostface. See USNRO Regulatory Guide 1.150, Revision I, Paragraph B.I. "Near-Surf ace Esaminat lose amt Sur f ace
]
mes=3ut5on."
4 l
r m
(
s SYSTEM: Reactor Vessel (Cont'd)
Class Category Esselnation Area /
Identifiestium of t e es seu.
Esamination Reiguirement Limitation Basis fur Rollef Fabrication leDIt Remarks l
Brvi-W24A 1002 ef the weld length N/A.
Volumetric and Surf ace See Table 2, Sheet 5.
t-A Closura Nead wee accsosible for scan-Esaelnation pertorned St.22 Herldsonal Wald ning. See Table 2 manually.
for percent of volume Valuestric coverage for each bene component.
1 RPVI-V24B 100% of the weld length N/A.
Valuestric and Surface See Table 2, Sheet S.
B-A Closure IlesJ was accessible for scan-Esamination performed 38.22 Ileridional Wald ning. See Table 2 manually.
+
for percent of volume volumetric coverage for each beae c c,mponeet.
I arvi-W24C 100% of the veld length N/A.
Volumetric and Surf ace See Table 2. ' Sheet 5.
S-A Closure Dwd was Mccessible for scan-Esselnation perf ormed Bl.22 HerlJBonal WelJ ning. See Table 2 manually.
for percent of volume Volueaet r ic cowarage for each bene componen t.
H I
RYVl W24D 8002 of the weld tength M/A.
Volumetric and Surface See Table 2 Sheet 5.
B-A Cle.sure llead was accessible for scan-Esaminatten performed -
31.22 Heridional Weld alog. See Table 2 manually.
for percent of values i
Valueetric coverage for each besa component.
I RPVI-W24E 100% of the wald largth N/A.
Valueetric and Surf ace See Table 2, Sheet 5.
I B-A Closure llead was accetelble foi na n-Emmelnation perf ormed Bl.22 Heridion al Wald ning. See Table 2 manually.
for percent of volume valueetric coverage for each bene com ponent.
i i
RPVI-W24r 100% of the weld length lua.
Volumetric and Surface See Table 2 Sheet 5.
B-A Clususe Ilead was accessible for scan-Esamination performed 81.22 Mettdlunal Weld ming. See Table 2 manually.
i for percent of wofume l
Valuest ric coverage for each beae component.
i j
IstTE: A 21 volumetric limitatluu luherent to the Reactor Pressure Vessel Weld Esaminations la the result of inter f ace nulse at the sound heae entry at thu outulJe vessel surface. See USHRC Regulatory Guide 5.550, Revision 't Paragraph S.), " Hear-Surface Esmelnation and Surface j
Resolutluu."
I i
n
\\
(
STSTDs: keactor vessel (Cont'd)
Class Cttegory Examination Area /
Identification of lere No.
Essegnation Requirement Liettation
_ Basis for Bellef Fabrication NDE Remarke l
I I
prVI-W24C 100% of the weld length N/A.
Volumetric ami Surf ace See Table 2. Sheet 5.
B-A Closure llead was accessible for scan-Examination performed Bl.22 Nerldtonal Weld ning. See Table 2 manually.
for percent.of volume Volumetric coverage for each beam component.
I arVl-W14is 8001 of the weld length N/A.
Volumetric and Surf ace See Table 2, Sheet 5.
B-A Closure lleaJ was acceselble for scan-f.samination performed 78.22
?8aridicnal Weld ning. See Table 2 eanually.
for percent of volume Vos;seetric coverage for each bene component.
I trvl-NIA Complete Voluestric esaa-Nozzle configuration Valueetric and Surface See Figure 5.
B-D Noaale-to-Shell Weld laatton of the Code-limite effective eseelne-See Table 2. Sheet 5.
Bl.10 required volume was not tion of the feall nosa te Esselnation performed mecha-Valuestric obtained. Approsteately forging. A welded insula-assed. Approsteately 891 of 911 of the weld length tion pad prohibits scan-the required volume as defined v
was accessible for scan-ning from a small area in the 80/W80 Edition of tie ning. See Table 2 below nosale.
Code was enseined effectively 7
for percent of volume with at least one angle beas coverage for each 1.eae component.
componeat.
t i
RrVB-NtB Crasplete voluestric esam-Nozzle configuration Voluestric and Surf ace See Figure 5.
B-D Nusale-to-Shell v ld laation of the Code-llette ef fective azariina-See Table 2 Sheet 5.
e Bl.10 required volume woe not Lion of the full naasle Examinet ton perf ormed mecha-Vulueetric citained. Approstaately forging. Interference mited. Approsteately 82% of 901 of the weld length from the bloshield door the required volume se delined was acceselble for scan-ellding rail assembly la the 80/W80 Edition of tne ning. See Table 2 Ilotta scanning in one with at least one angle beme f.et pe rcent of volume location.
component, cseverage for each bene component.
l 8
RPVI-N2A Complete volueetric esse-Natale configuration Volueetric and Surfact See Figure 6.
B-D Noaale-to-Shell Weld laatton of the Gude-lletts effecties esselna-See Table 2. Sheet 6.
81.10 required volume was not tion of the full nozzle Esaminat ion performed meche-Volumetric obtained. 100% of the forging.
ni s ed. Approsteately 912 of weld length was acces-the required volume as defined alble for scanning.
In the flO/W80 Edition of the See Table 2 f or percent Code was esamined ef f ectively of volume coverage for with at least one aut*e beam be e component.
component.
IMTE: A 21 vulueetric Ilottattuu inherent so the Reactor Pressure Vessel Wald Esaminations is the result of Interf ace suelse at the mound beam ent ry at the outalde vessel surface. See llSNRC Regislatory Geside 1.150, Revision I, Paragraph B.I. "Near-Surf ace Esaminat ion aml Sur f ace ke molut lou."
f'"
(("
P STSTEN: Riscter Vicsel (Cont'd)
Claes Categury Esselnatina Ares /
Identification of.
Ites Nu.
Examinat ten sevelsesenL Lleltation Basis for Rollef Fabrication NDE temerke I
aryl-N23 Complete volumetric exam-Humale configuration Volueetric and Surf ace See Figure 6.
t-D Nossle-to-Shall Weld laation of the Code-llette effective esselna-bec Table 2 Sheet 6.
Bl.10 required volume was'not tiun of the full nozzle t.naelnation performed mecha-alred. Approstaately 911 of Valuest ric obtaineJ. 100% of cl.a forging.
the required volume as delined weld length was acces-
' in the 80/W80 Edit lun of tue alble for scanning.
Code wee ensaisied ef f ectively See Table 2 for percent with at least one angle beam of volume coverage for component.
each beam component.
I prvl-N2C Complete valueetric emaa-Nosale configuration Volumetric and Surface See Figure 6.
B-D Nossle-to-Shell Weld instion of the Code-lleita effective esseina-See Table 2. Sheet 6.
33.30 required volume was not ston of the full naaste Esamination performeJ earle-Volumetric obtained. 100Z of the forging. Prostetty of nised. Approstaately 792 of weld length was acces-N8 nozzle limits scanning the required solume as defined alble for scanning, in one location but does in the 80/W80 Edition of spy code was enseined effectively See Table 2 for percent niet appreciably limit witt. at least one angle beam o! volume coverage for volume coverage, component.
each boas component.
I Brvi-N2D Complete valuostric exam-Nostle configuration Valueetric and Surface See Figure 6.
B-D Noaale-to-Shell Weld laation of the Code-limite effective esseina-See Table 2. Sheet 6.
31.80 required volume was not tion of the full nasale Emmelnation perf ormed mecha-nl ed.
Appros taately 79% o' valuestric obtained. 100% of the forging. Prosimity of weld length was acces-N8 nozzle llette econning the required volume se defined alble for scanning.
la one location but does in the 80/WUG Edition of the Code was esamineJ effectivele See Table 2 for percent not appreciably lielt with at least one angle: beae of volume coverage for volume coverage.
component.
eacle bene component.
I krvl-N2E Complete valueetric exae-Ikassle configuration Volumetric and Surf ace See Figure 6.
B-D Hoaale-to-Shell Weld
$ nation of the Code-
!!alte effective esaalne-See Table 2. Sheet 6.
31.30 required volume vea not tion of the full natale Esselnation performed mecha-nised. Approximately 911 of Volumetric obtstned. 100% of the forging.
the required volume as defined weld length was acces-In the 80/W80 Editlon of the alble for scanning.
Code was esselned ef fectively See Table 2 for percent vitti at least one angle beam of volume coverage for component.
each beam enoponent.
l l
I l
l I
NUTE: A 2% wulumetric lleltation inherent to the Beactor Pressure Vessel Weld Eamelnatione la the result of interf ace suilse at the sound heae entry at the outside vessel surface. See USHRC Regulatory Culde 1.850, Revision I, Paragraph B.), "Near-Surf ace Emmeinstion and Surf ace f
Resolutlon."
l l
(
f U
SYSTtA seactor Wessel (Cont'd)
Cisne Category Esasinettee Areel IJentificatlon of Itse No.
Esselnation Sequirement__
Limitation Basis for Relief Fabrication NDE Remarke I
MPVl-M2F Complete valueet ric esse-Nasale configuration Volumetric and Surf ace See Figure 6.
See Table 2, Sheet 6.
B-D Natale-to-Shell WelJ instion of the Code-liests effective esseina-
. Esamination perf ormed esche-B1.80 required values was not tien of the full coaste mised. Approstaately 911 of Volumetric obtained. 100% of the forging.
the required volume as defined '
weld length was acces-In the 80/W80 Edition of the elble for scanning.
Code was esseined effeettwely See Table 2 for percent with at least oss angle beat of volume coverage for component.
each beam component.
I aPVI-N2C Complete volumetric esse-Nottle configuration Volumetric and Surf ace See Figure 6.
See Table 2, Sheet 6.
B-D Noaale-to-Shell Weld laation of the Code-lleite effective esamina-required volume was not tion of the full nozzle Esselnation performed mecha-mi s ed. Approstaately 9t* of 31.10 obtained. 100% of the forging.
Volumetric the required valuer as defined weld length was acces-In the 80/W80 Edition of the alble for scanning.
CoJe was esamined effecttwely See Table 2 for percent with at least one angle lean of wolume coverage for i
component.
each bene component.
-l RPVI-N?ll Complete volumetric asse-Nossle configuration Valuestric and Surface See Figure 6.
See Table 2, Sheet 6.
ab B-D Nozzle-to-Shell Wald laation of the Code-llette effective esseins-g Esselnation perf ormed e=cha-31.10 required volume was not tion of the full nossle mised. Approsteately 79 nf Voluestric obtained. 100% of the forging. Prostelty of tne required volumn as delined weld length was acces-N6 nosale llette scanning in the 80/WHO Edition of the elble for scanning.
In one location but does Code was esamined effecstwely See Table 2 f or percent not appreciably llelt with at least one angle heae of volume coverage for volume coverage.
component.
each beas component.
1 NPVI-N2)
Complete volumetric exae-100ssle configuration Volumetric ami Surf ace See Figure 6.
l See Table 2, Sheet 6.
i B-D Nusale-to-Shell Weld Snation of the Code-llette effective examina-Bl.10 required volume was not tion of the full nozzle Examination performed mechs-nl ed.
Approstaately 791 of Volueetric obtained. 100% of the forging. Prostelty of weld length was acces-N8 nosale llette scanning the required volume se dellned alble for scanning.
In one location t=at does in the 80/W80 Edition of the Code was esamined effecttwely See Table 2 for percent not appreciably llett with at least one angle beam of volume coverage for volume coverage.
component.
each beam component.
t t
to the Reactor Pressure Vessel Weld Esaminattens is the result of Interface noise at the sound beae NOTI' t A ?! valueet ric liettat ion inherent See USHNC Regulatury Culde l.150, Revision I, Paragraph 3.3, " Hear-Surf ace Esselnation and Surf ace entry at the outstJe wesuel surface.
kemulutlon."
W L
n..
.,N i
SYSTl38: Reactor Vessel (Cont'd)
I Clase
)
Category Essetnation Area /
Identificatt'on of
]
Ites No.
tuaminatten Requirement Liettation Basle for Rollef Fabrication NDE pesarke l
l S pV I-il2K Complete volesmet ric esse-Nosale configuration Volumetric and Surface See Figure 6.
B-D Nossle-to-Shell Weld laation of the Code-llette effective esselna-See Table 2 Sheet f,.
51.10 regulred volume was not alun of time full nostle Emmelnation performed meche-Volumettle obtained. 1001 of the forging.
nl ed.
Approstaately 917 of inelJ length was acces-the required volume as defined -
alble for scanning.
In the 80/W80 Edition of the See Table 2 for percent Code was enseined effectively of volume coverage for with at least one angle beam each beme component.
cueronent.
I Rrvi-NIA Complete voluestric exas-Nuzale configuration Volumatric and Surf ace See Figure 7.
B-D.
Nozale-to-Shell Weld laation of the Code-llette ef f ective esselna-See Table 2 Sheet 6.
31.10 required volume was not ston of the full nozzle Examination performed manu-volumetrle obtained. 100% of the forging.
all y.
Approutestely $4% of weld length inno acces-the required volume an detined elble for scanning.
In the 80/W80 Edition of the
}
See Table 2 ter percent Cnde was esaalnad effectively of volume coverage for with at least one angle beme each beas component.
component.
gu 8
RpVI-N1B Complete valueetrie exam-Nogale configuration Voluestric and Surf ace See ripure 7.
B-D Nozale-to-Shell Wald inattom of the Code-Italte effecttwo esamina-See Table 2 Sheet 6.
a l.10 required volume was not tion of the full noaale Eueelnation perf ormed manu-Volumetric obtelned. 100% of the forging.
ally. Approntaately 84* of weld length wee acces-the required valuee se defined
{
elble for scanning.
in the 80/U8J Edition of the See Table 2 for. percent Code was enseined effectively of volume coverage for with at least one angle beam each bene component.
component.
I kpvi-N3C Complete volumet ric anam-Nozale configuration Volumetric and Surface See Figure 7.
S-D Nogale-to-Shell Wald laatton of the Code-limite ef fective amaalna-See Table 2, Sheet 6.
31.10 required volume was not Lion of the full nozzle Emmeinet ton performed annu-Volumetric obtained. loot of the forging.
ally. Approsteately $4: of weld length was acces-the required volume as defined elble for scanning.
la the 80/W80 Edition of the See Table 2 for percent Code was esamined ef f nettwely of volume coverage fur with at least one angle home each beam component.
com ponen t.
NOTt.;
A 21 wulueet ric llettattun luherent to the Reactor pressure Vessel Weld Examinat ione is the result of laterf ace noise at the sound bede ent y at the outelJe vessel surface. See USNRC Regulatory CielJe 1.150, Revleton I, paragragen b.3, *Near-Surf ace Emaelnation and Surf ace Rumal ut leni."
i f
l
i
~
t SYSTENs teactor Vessel (Cont'd)
I Clase 1
Category Esselnation Ares /
IJentification of l
Ites No.
Esselnatlos Requirement Liettation Basis for Rollef Fabrication NDE Bemerke l
1
'kPvi-Nio Complete volueetric esse-Nossle configuration Valueetric and Surface See Figure 7.
I B-D Nogale-to-Sliell Wald laation of the Code-limit e ef f ective esamine-See Table 2, Sheet 6.
31.10 required volume was not tion of the full nouste Esselnattoa performed manu-Volueetric obtained. 100% of the forging. Prosletty of ally. Approslaately 841 of j
weld length was acces-NS nosale llette scannif.g the required volume as defsned slble for acanning.
In one location but does in the 80/W80 Edition of the See Table 2 f or percent not appreciably lfalt Code was enemined effectively of volume coverage for coverage.
with at least one angle beme a
]
each beam component.
component.
I RPVI-N4A Complete valuestrle esse-Nogale configuration Volueetric and Surface See Figure 8.
B-p Nusale-to-Shell leeld ination of the Code-llelts effective exaelna-See Table 2. Sheet 6.
58.40 required volume was not tien of the full possle Esselnat ion performed meche-Volumetric obtained. 100% of the forming.
mised. Approstaately 81% of 1
weld length was acces-the required volume as defined stble for scanning.
la clie 80/Wuo Edit tom of the i
See Table 2 for percent Code was esselnad ef f ectively of volume coverage for with at least one angle beam each bene component.
component.
I NPVl-N4h Complete valueetric Norste configuration Volueetric and Surf ace See Figure S.
l
[
B-D Nussle-to-Shell Weld esamination of the CuJe-lletts effective esamina-See Table 2. Sheet o.
1 31.80 required volume was not tion of the f ull nomsle Esaetnat tos. perf ormed mecha-Volumetric obtained. A,,prosteately forging. Interf erence nised. Approsleetely ill of j
d61 of the weld length f ree a cliermocouple the required volume as defined was accessible for scan-btacket limits scanning in the 80/W80 Edition of sne ning. See Table 2 in one assauth location.
Code was esseined effectively.
j for percent of volume with at least one angle beam i
coverage fae each bene component.
cceponent.
I RPVB-H%C Cumplete volumet ric Nogale configuration Vulueetric and Surf ace See Figure S.
8-l Husale-to-Shell WelJ enantnation of t he Code-llette effective enseine-See Table 2 Sheet 6.
as.lo requireJ volume is not tion of the full naasle Esamination performed mecha-Vulueetric obtained. Approximately forging. Prostetty of mixed. Approstaately 66% of 79% of the weld length Hll nossle llette scan-the required volues as defined was accessible for scan-ning in one asleuth in the 80/W80 Edit tee of the salms. See Table 2 location.
Code was enseined effectively j
for percent of volume with at least one angle bese covetage for each beam component.
component.
I l
l l
NUTE: A 21 vulueetric llettation inherent to the Reactor Pressure Vessel Weld Esaminations is the result of. interface noise at the sound beae i
entry at the outsIJe vessel surface. See USNMC Regulatory Guide 1.150, Revleton I, Paragraph 5.3, "Near-Surf ace Esaminet ton amt Surf ace i
ResulutIun."
I i
i I
}
-~----w
/
\\
\\
x SYSTENs Beacter Wessel (Cent 'J)
.Clase Category Esamination Area /
Identification of lien see.
Eamelnattoe Sequirement tiettation Basle for Rollef Fabricatlon NDE Remarke I
prVI-N49 Complete volumetric Noaste configuration Voluestric and Surface See Figure 8.
8-0 Noaale-to-Shell Weld eseelmation of the Code-llette effective esamtma-See Table 2, Sheet 6.
Bl.10 required volume was not alen of the full nostle Esaalnation performed mecha-valueetric obtained. Apprestaately forging, laterference elsed. Apprestaately Il1 of 861 of the weld length from a thermocouple the required volume as defined was accessible for scan-bracket llette scanales le the 80/W80 Edition of the ning. See Table 2 in one asleuth location.
Code was esselned effectively for perceni of volume with at least one angle beam coverage for each bene component.
component.
I arVI-M4E Complete vcluestric esse-Noaale configuration Voluestric and Surface See Figure 8.
B-D Nostle-to-SheII Wald testion of the Code-llette effective examina-See Table 2. Sheet 6.
Bl.10 required volume was not tion of the full nosale Esselnation performed mecha-Volumetric obtained. 100% of the forging.
nised. Approsteately 81? of weld length was acces-the required volume se defined sible for scanning.
In the 80/W80 Edition of the See Table 2 for percent Code was essetned effectively of volume coverage for witti at least one angle bene each bene component.
com ponent.
I trVI-N4r Complete valuest ric esse-Nossle configuration Volumetric and Surface See Figure 8.
r
$3 3-D Mesale-to-Shell W.;d laattom of ti.e Code-llette ef fective emanina-See Table 2, Sheet 6.
Bl.10 required volume was not tion of the full nossle Esmelmation perf ormed mecha-Valuestric
.obtaineJ. Approstaately forging. Prostetty of alred. Approstaately 662 of 791 of the weld length Nil nossle !!alta scan-the required vs.lume as defined was accessible for scan-ning in one asleuth in the 80/W80 Edition of tne ning. See Table 2 location.
Code was enseined effectively for percent of values with at least one angle i.eam coverage for each beas component.
component.
I trVI-NSA Complete valueetric Moszte configuration Volumetric and Surface See Figure 9.
B-D Nogale-to-Shell Weld esaminatlon of the Code-limite effective essetna-See Table 2, Sheet 6.
Bl.10 required volume was not tion of the full nossle Esmalnatlas performed mecha-Valueetric obtained. 100% of the forging.
nised. Approstaately 86% of weld length was acces-the required volume as detined sible for scanalas.
la the 80/W80 Edition of the See Table 2 for percent Code was esamined ef f ectively of volume coverage for with at 'leset une angle bene each bead component.
cong.onent.
a lurfEs A 21 valueetric llettation inherent to the Reactor Pressure Vessel Wald Esaminations is the result of interface nulse at the sound bene entry at al.e outalJe vessel surface. See 13SNRC Regulatory Culde 3.150, kevision I, Paragraph g.3, " Hear-Surf ace I;samination and Surf ace kesolutlun."
(
\\
SYSTDes Reactor Vessel (Cont'd)
Clase Category Esselnation Areal Identificattom of Ites No.
Esselnation Requirement Lieltation taale for Relief FaLrication NDE Remarks I
trvi-NSB -
Complete valuestric esse-llosale configuration valueetric and Surface
'See Figure 9.
B-D Nassle-to-Shell Weld inattom of the Code-llette effective essetna-See Table 2, Sheet 6.
Bl.10 required volume vea not stun of the full nossle Esamination performed mecha-Valueetric obtained. 1001 of the forging.
alred. Approstaately 861 of the required solisme as detined weld length was acces-sible for scanning.
In the 80/W80 Edittom of the See Table 2 for percent Code was essetned ef f ectively.
of volume coverage for each beam component.
I apVI-M6A Complete valuestric esam-Nozale coa!Iguretton Volumetric and Surface See Figure 10.
B-D Nusale-to-Shet! Wald testion of the Code-liette ef fective esaetna-See Table 2 Sheet 6.
Bl.10 required volume was not tion of the full nozzle Esselnation performed meau-Volumetric obtained. 8002.of the forging.
ally. Approsteately 901 of weld length was acces-the required volume as defineJ elble for scanning.
in the 80/W80 Edition of the See Table 2 for percent Code was essetnad effectively of volume coverage for with at least one angle bene each beme component.
component.
I krvl-N6B Complete valueetric esse-Nozzle configuration Valueetric and Surface See Fleure 10.
go B-D Nossle-to-Shell WelJ ination of the Code-limite effective esselna-See Table 2, Sheet 6.
Bl.10 required volume was not tion of the full nozzle Esselnation perf ormed manu-Valueetric obtained. 100% of the forging.
ally. Approsteately 90% of weld length was acces-the required volume as defined alble for scanning.
la the 80/W80 Edition of the See Table 2 for percent Code was eseetned effectively of volume coveruse for with at least one angle bene each beme component.
component.
I trVI-N7 Complete valuestric esse-llosale configuration Volumetric set surface See Figure 11.
B-D Nossle-to-Shell Weld ination of the Code-limite effective esamina-See Table 2, Sheet 6.
Bl.10 required volume was not tion of the full mosale Esselnation performed manu-Valueetric obtained. 1001 af the forging.
ally. Approstaately 9)! of weld length was acces-the required volume as defimod sible for scanning.
In the 80/W80 Edition of the See Table 2 for percent Code was essetned ef fectively of volume coverage for with at least one angle base each beam component.
component.
leiTE: A 21 welueetric tieftetlon inherent to the Reactor pressure Vessel Wald Esselnations to the result of interface motse at the sound beae entry at the outstJe vessel surface. See IJSNMC Regulatory Culde 1.850, Revleton I, paragraph B.1, "Near-Surface Esamination and Surface Resolution."
/
I
n D
(
SYSTEM: a M eer Vassel (Cont'd)
Clase Essetnatten Areal identification of Basle for Belief fabricattaa Nht Reserks l
Category lie No.
Esamtmation Requirement Limitarfoe I
prvi-N84 Complete valmostric esse-Norale configuration Volumetric and Surf ace See Figure 12.
See Table 2. Sheet 7.
8-0 Mossle-to-bhall Wald snation of the Code-limite ef fective esamina-Esselnation perf ormed manu-required volume wee not s t un of the full nossle ally. Approstaately 925 on 31.80 volumetric obtained. 100% of the forging.
the required volume as det tned weld length was acces-to the 80/WBO Edition of tne J
alble for scanning.
Code van enseined effectively See Table 2 for percent witn at least one angle bene i
of volume coverage for j
c om ponent.
each bene component.
f' esse-Mostle configurettoo Volumetric and Surf ace See Figure 12.
I RPVI-NSB Complete valueetttC See Table 2, Sheet 7.
l 5-D Norale-to-Shell Weld tgation of the Code-llette ef fective examina-y Emmelnation perf ormed manu-required volume was not tion of the full nozzle 8
ally. Approstaately 921 o
{
Bl.10 valuest ric ebtained. 100I of the forgtPg.
the required volume an defined weld length van acces-An the 80/W80 Edition of tr.e alble for scannthd.
Code was eaamined ef f ectively See Table 2 for percent with at least one angle bene of values coverage for component.
each bene component.
J j
i RPVl-N9 Complete valuestric esse-Nosale configuretton Volumetric and Surf ace See Figure 12.
See Table 2, Sheet 7.
eJ B-O Mussle-to-Shell Weld snation of the Code-Ilmits effective esamine-Esaetnation perf ormed manu-Bl.10 required volume was not tion of the full nosale ally. Approstaately 921 of 4
4 Valueetric obtained. 100% of the forging.
the required values se defined weld length was acces-In the 80/W80 Edittun of the 4
alble for scanning.
Code wee enseined ef fectively See Table 2 for percent utth at least one angle bene 1
of volume coverage for component.
each boas component.
{
j 1
prvi-NIFA Complete volumetric esse-Nozzle configuration Valuestric and Surf ace See Figure 13.
1 See Table 2, Sheet 7.
s-D Nossle-to-Shell Weld snation of the Code-Ilmita effective exaelas-Enaminet ton perf ormed mecha.
l required volume was not ston of the full naaste 31.80 alred. Approstaately 391 of i
Valueetric obtelnet. 100% of the forging.
tho' required volume se defined l
weld length was acces-In the 90/W90 Edition of sne l
alble for meanning.
Code was emnetned ef fectively 1
j See Table 2 f or percent with at least one angle base of volume coverage for l
component.
sach beam component.
jl l
l l
1 to the Beactor Frassure vessel Weld Esaminations to the result of interf ace noise at the sound beam i
NUTE; A 2Z volumesric llettation inherent See USNaC Regulatory Culde 1.150, Sevision I, Faragraph B.3, "Near-Surf ace Examinet tun and Surf ace l
weary at the out side vessel surf ace.
be=ulution."
l' I
l
W S,Tt,tt t.r....el - t..,
Claae Category Emaninattes Area /
Identification of tree me.
Essesmattoa seguirement Liettation Basto for Relief Fabricatloa MDF.
Itamark s I
Brvl-ul78 Complete voluest ric esse-Nogale cos!!guration Voluestric and Surf ace See Figure 13.
B-D Nessle-to-Shell Wld inscion of the Code-liette ef fective essai ;-
See Table 2, Sheet 1.
33.10 required vol.as was not tion of the full nosale Emmelnation performed necke-Volumetric obtelned. 100% of the forging.
nised. Apprestaately 89% of weld length was acces-the required volume as defsned allle for scanning.
la the 80/W80 Edition el the See Table 2 for percent Code was essetned ef f ectively of volume coverage for with at least one engte beae each beam component.
component.
I arvi-ul7C Comple's volumetric exta-Nozzle configurettoa Volumetric and Surface See Figure 13.
.-O Nossle-to-Shet! Weld laation of tt.e Cude-limite effective enseine-See Table 2. Sheet 7.
s1.10 required volume was not tion of the full aciale Euselnation performed mecha-Tolumetric obtained. 1001 of the forging.
alred. Approstaately 89* of weld length was acces-the required volume as defined elble for scanning.
In the 80/W90 Edition of the See Table 2 for percent Code wee enestned ef fectively of volume coverage for with at least one angle beam each beam component.
component.
I arvl-ulTD Complets volueetric esse-Notste configuration valueetri: and Surface See Pisure 13.
y S-D Nea:Re-to-She!! Weld laattom of the Code-llette ef f ective esamine-See Table 2. Sheet 7.
31.10 required volume was not tion of the full nossle Esselnation performed mechs-Volumetric obtained. 1001 of the forging.
~
nized. Approstaately 891 of weld length was acces-the required volume as defined alble for scanning.
In the 80/W80 Edition of the See Table 2 for percent Code was esamined effectively of volume coverage 'or with at least ree engle beae each boas component.
component.
I nevl-NIAIR Complete volumetric h aale configuretton None See Figure 5.
B-D lealde Radlue Sectlen aseelnattom of the inside laterteres with scanning See Table 2. Sheet 5.
31.20 redles section was not en the nusale bees and Esselnation performed Teluestric obtelmed. See Table 2 prs %1 bits a meaningful mechaatsed.
for percent of values trierrogetton of the coverage for each base more portion 6f the j
component.
Inside redina section.
i I
arve-ultla Complete valuestric Nossle configurattu Hone See Figure 5.
{
B-D laside Radise Secties esamination of the inside laterferes with scanning See Table 2 Sheet 5.
1 31.20 radius section was not on the nozzle eoes and Examinettoa performed l'
Vol metric obtained. See Table 2 prohibite a meaningful mechentaed.
for percent of volume laterrogatten of the
{
coverage for each beam bore portion of the compoeemt.
lealde radine section.
lesTE: A 22 vieleertric Ilott at taa laborest to the teacser Pressure Vessel Wld Eneelnations la the result of interf ace notee at the sound bene entry at the e aside vessel surface. See USMac Regulatory Guide 1.150, se* *elon 1. Paragraph 3.3, *Near-Surf ace Esselnation and Surf ace menet a8."
l l
n..
f t(
V 4
SYSTEM: Reacter Tessel (Cent'd)
Clase Category Esmeinetten Areal identificatles of s
t r es eso.
Esselnatlee Beanutrement Llettarten haste for Relief Fabrication IlltE Remarbs I
RFTI-N4CIR Camplete valuestric Prestelty of N11 aossles None See Figure S.
5-D lealJe Badles Sectlee manetaatles of t*..
'aside Italte scanalog.
See Table 2. Sheet 6.
51.20 redtes secttee w.s not Esaminetten performed valuestric obt a t aed. See Table 2 sec han t t ed.
fee percent of welume coverage for each beam component.
l I
BFVB-N4 FIR Complete velueetric Fromletty of IIll mossles None See Figure S.
8-0 laelde RaJina Section esselaattoe of the taalde llette scanning.
See Table 2. Sheet 6.
Bl.20 redtee section wee mot Enseinetton performed volumetric shtalmed. See Table 2 sechselsed.
for percent of welmee l
coverage for each been component.
I BPVI-TilDF Complete valemetric esme-Due to se abrupt tranel-Ilone Esse! nation wee performed t-G-1 Reactor veneel Flange laattom coverage of the tson at the seal surface manually.
34 40 Ligaments flange ligament area was cleJding, scamated fo' See Figures le and 15.
not obtalmed.
complete coverage of the Volumetric IIgamene area cannot be performed.
H
'd I
arvt-Wss(1-B)
Complete eerf ace esael-Complete esaelnettos None Stabiliser brackete I, S. 6, B-u mescter vessel Stabiliser setten coverage of the coverage le not poselble 7 and S received surface 88.10 Brachase stabiliser atta.beest for brackets I, 5, 6, 7 i
welde wee met abastaed.
and 8 due to laterference eseelnation ecuerage on three of tha four sides.
Surface free permanent insulation Esaetnation use performed seppert brackets.
eanuall y.
.l I
i i
tlDTE: A 21 welueet ric llett at taa lnberent to the Reacter Pressure Tessel Weld Esaaleatless !? the result of laterf ace noise at the sounJ beam l
entry at the outside weasel surf ace.
See afstac Regulatory Calde 3.150 Bestelom I, F.regraph B.1, "Near-Surf ace Esaetaation asal Surf ace Besoluttoe.*
f f
\\
1
_._.~____.__._m
-__.____..-.m
....-._.m._._.
m.
{
}
l SYSTEBIs Itale Stesa i
cl.ee Category Esmeinettee Ares /
Ideettftcottee of J
l t ee lee.
Esamlesslee Seguirement Llettation Seele for Belief Febeltattoe ISE E m the 1
i i
l l-AS-30BA-0504-8 Complete eerf ace esael-A permaneet type support Velemetric and Surface Ilmee l
B-J Pipe-to-Ethew estion coverage eens est le coverleg the eseelse-39.28 ehanteed f ree 11-3/4 s tem etee f or 2 lec hee
. Surface Sachen to I loch L.
of the 12-3/4 leches of weld length.
i i
]
i i
1
}
i N
s~
e r
i 4
j i
i i
NOTE "l? desentes the erasessement free the reference sere potet estehliehed to sep ledicatleelllettettee lacettene either ereund the eletumfereace andlar along the length of s'welJ.
_ ~ - -
m g
s s
STSTENs Feedwat er Clase Category Esamination Area /
Identification of sten No.
Eumelmat ine sequittammt Limitatten Bests for Rettef Fabricetten Nid Beme rks I
l-AE-24DLA-015-4 Complete valueetric cow-Am apparent weld butidup Teluestric sed Surf ace Complete omrface esamtsation B-J Ftpe-to-Valve werese use not obtained ares laterferes with coverage une obtalmed to the 39.11 f ram 51-1/2 taches to scenelog for 16-3/4 area of the valueetric 3
Surface sad vsluestric 70-l/4 inches L.
laches of the 76-l/2 Itattatten.
j inches of weld length.
l This builJup has a tree-l sitten which results is j
less of coupling to the base material, thee J
r 1
restr8cting complete j
coverage. Due to the estensive malatemance J
suppstt requiremente fer removal of a jet lepinge-ment barrier which wee placed over this weld
} etat following PSI, thia weld to mac intended for l
eclection during embee-quent teservice saaelne-l tiene.
4 da j
tm I
l-AE-24DLA-Ol6-6 Complete surf ace esami-A support inter /etence totumetric and Surface Full welmestric enastne-
]
S-J ripe-to-Elbow nattee coverage wee not prevented surf ace esset-t8ee coverage uns obtelmed 39.11 obtained f rom 28 inches net too for 14 inche. of in the area of the outf ace Surf ace and volumetric to 42 inches t-the 76 inches of weld Itattattee.
)
length. This seppert wee i
used in the installation t he }et tapingemenc bar-j ster. Due to the esten-i 7
elve malatemance support t
regattemente for reeoval of the jet !apingemen:
barrier, this weld te not 4
{
latended f or selecttee during subsequent inaer-vics eseelsations.
t j
t 1-AE-200tA-03 5-3 Complete surface emael-Due to e peraenent clamp Velmeetric and Surf ace Full valuestric esamine-j B-3 RsJucing Tee-to-Fipe nation coverage uma not anJ air duct Inter f erence,
aten coverage use obtained 39.Il obtained f ree 13 taches a surface emmelmation to la the assa of the surf ace Surface end Volumetric to 58-1/2 tachea L.
restricted for 25-1/2 limitatten.
Anches of the 63-t /4 l
IncSea of weld length.
I.
,l
)
Nuit's "L" Jennees the measurement from the reference zero rotat established to map inJtcat ten /Itattet tee locat toes either around the circumference j
amJ/ur along t he length of a weld.
l
~
F m
i n
k s
i i
SYSTDis Reactor Sectreulation Cless C tegory Esaelnatten Areal Identification of i
Ites No.
Esaminet ten seguirmeent _
Liettation taste for Belief Fabricatlee IIDE Bemerks l
8 l-en-2OvCA-Oll-)lD Surf ace and volueerrte A permaneet whip Volumetric and Surf ace This llettatlan will restrict 7-l/2 inches ef embeequent 3-J longitudinal Seam coverage was not teatraint (anchor frase) obtained from 4-l/2 covers 15-l/2 inches of ISt-required esas area based Surface and Volumetric taches to 20 taches L.
the 41-l/4 inches of weld on selection of the 12-inc h 31.52 segment which intersects the lengte.
n circumferential weld.
I l-Be-20VCA-Ol l-5LU Complete volumetric The scan area configura-Volumetric and Surf ace Camplete surface esselmattee 3-J Longitudinal Sese coverage was not tion (see taper) pre-coverage was obtained.
obtained free O to cluden easegnation for I
99.12 Surf ace and Volumetric 2 taches L.
- 2 taches of the 20-5/16 inches of weld length.
I l-35-2 8VCA-Oll-6 Lil Surface and valuestric A permanent pipe Volumetric and Surface This Itattattaa to outside of B-J Longitudinal Sese coverage wee not restraint covers 36 f aches the 32-tech segment of toegste-obtained from 20 inches of an. 55-7/16 inches of dinal weld required to be esse-39.12 imod during ISI.
Surface and Volumetric to M inches L.
weld length, I
l-se-20VCA-Oll-FLU Surface and wolvestric A permanent pipe Voluestric and Surface This llettatten ullt restrict B-J longitudinal Sese coverage wee not restraint covers 18 taches S inches of pubsequent ISI-obtained from 4 inches of the 74-3/4 faches of
- required emme area based en selection of the 12-tech ses-N 39.82 Surface enJ Velueetric to 22 taches L.
weld length, j
ment of leasttadinal seen which intersects the circumferential weld.
l i
I-l-St-28VCA-Oll-7LDI Surface and volumetric Brasech connectione in Volumetric and Surface This llettatten la outelde of
]
B-J tangitudinal Seae coverage wee not the esselmattee area the 12-lack segment of longits-39.12 obtained f rom 19 laches preclude esamination for dinal weld requirise subsequent Surf ace and valueetric to 21 inches L.
2 taches of the 24 taches essetnattoe ISI.
of weld length.
1 I
l-BS-28VCA-Oll-8LUI Surf ace and volueetric Stanch connections te volumetric and Surf ace This llettation to outside of B-3 langstedleal Seme coverage was not slee esselnactos area the 12-inch segment of longitu-89.l2 obtained from 19 inches preclude enseinetton for dinal weld requiring subsequent Surface and volumetric,
to 21 taches L.
2 incl.es of the 25 taches asamination ISI.
of weld length, I
l-se-28VCA-Oll-JLDO Sestface sad valueetric Branch connections in Valuestric and Surf ace This tiettetten is outelde of f
8-J tongitudinal Sese coverage wee not obtained the esaminetton area the 32-inch segment of longitu-f from 41-7/8 inches to preclude esselnation of dinal weld requittag subsequent j
39.12 esselnation 151 Surface and volumetric 41-5/8 inches t 1-1/4 inches of the 41-5/8 inches of weld I
lenstli.
NuTE:
- l." denotes the measurement from tlee reference zero polns established to map indicot ton /llettatlan locatione either around the circumf erence anJ/ur along the length of a welJ.
.m._
~~
}R I
SV3ttses teactic Rectrealteten (Cent'd) i 1
l Close Esselsetten Areal Identifscattoe of Fabricatlos upE temerta taste for Belief Catesory I.le t c ar ler.
b Ites me.
Essegnatten Requirement t
I I
l-se-20VCA-Oll-8LHO Surface and voluestric Branch connectlees in Volmeetric and Surf ace This llettatten to estelde of the 12-tech sageset of leegite-I 4
B-J Longstadinal Sese coverage wee est obastned the esseinettee area dinal weld requiring subseqeent f ram 41-7/8 inches to preclude eseeinetten of essetnettee 151.
l i
39.82 Surf ace and volumetric 41-5/8 inches L.
1-1/4 taches of the j
41-5/8 laches of weld length.
l Due to the breech comaec-Surface L eplete surf ace esaminetten I
c.<erage was obtalmed. A t'
I l-DS-25WCA-Oll-9tC2 Valuestric coverage 9-J Branch Connection using 0* weld and 45' clos configuratloa, a 0*
Code-required 60* essetnattee tramoverse scans was not veld and 457 weld esse-vae perf ormed f ree the esta 89.11 l
Surf ace and voluestric obtained.
laatten caneet be rue of pipe.
obtained.
Ceeplete surf ace essetaattoe Due to the branch connec-Surface coverage was obtaleed. A
- [
j l
1-30-20VCA451-99C)
Volumetric coverage j
S-J stanch Connectton estag 0* weld and 45*
tion conftsuretton, a 0*
Code-required 60* esaetmattoe l
transverse scan wee not meld and 45T weld esen-was performed from the main
[
)
39.)t Ination cannot be Surf ace and Valuestric obtateed.
run of pipe.
obt s leed.
j Volumetric and Surf ace Complete omrf ace eseelmas tee
]
Lees than one-third of Due to branch connection coverage was obtained. 100%
,i 8
8-BS-4VCA-Oll-1 3-J Branch Connection-the Code-required cover-configurattee, a complete of the length of the weld use i
n age of the louer one-scan cannot be perfereed ecceselble for scanning.
l 4
39.11 t o-pi pe third weld volume could to provide full coverage.
See sketches, Data Sheet j
I Surface and volumetric not be obtained.
Do. 181187 for coverage plot.
l I
}
l l-BS-4WCA-Oll-2 Lees than one-fourth of Due to the flange com-Volumetric and Surf ace Complete surface eseeinettaa coverage wee obtaleed. 8002 8-J pipe-to-Flange the Code-required cover-figuration, e templete of the length of the weld was i
j age et the louer one-aces caneet be performed acceselble for scenetag.
39.11 Surface and volumetric third weld volume could
- to provide full coverage.
see sketches, Data Sheet i
not be obtained, leo. 181531 for coverage plot.
I l-85-2SVCA-cl 2-5 Surf ace esselmettoe A permanent pipe support valuestric and Surf ace volismetric coverage of the louer eme-third weld volume j
s-J p ipe-to-pipe coverage could not be interference precludes was obtained in the area of g
obtained free 10-l/2 surface assegnactee for the surface essetnettee 1
39.18 Surf ace sad Valueetric taches to 67-5/86 inches 48-11/16 inches of tI.e llettetten.
87-3/16 inches of weld l..
i tength.
I l-3B-20VCA-012-?t.pl valueetric coverage tranch connection later-Voluestric and Surf ace Camplete oestf ace esamination 1
coverage use obtained. This S-J Longitudinal Seae could not be obtained forence limite scanning tiettatlen is estelde of the
{
free 18-1/2 laches to for 2 inches of the 12-inch sessent of longitudi-t9.82 Surface and volumetric 20-l/2 inches L.
28 inches of weld length.
mal weld requiring subsequent esamtmatten ISI.
l established to esp indication /llettation locatione either around the circumference 4
{
prnE t "I" denotes the measurement free the reference sero point 1
anJ/or alous stue leastle of a weld.
4
_ _... -.. _, ~ _ __
SYSTDs: seacter hectreutet tee (Cont'd)
Claes Categnry seastnetten Ares /
Identification of I t ee ela.
Emmelnation seguirement Liettation Basis for Relief Fabrication IIDE Remarks I
l-SS-20VCA-Ol2-Fl2O Volumetric coverage Branch connection inter-Valueetric and Surface Complete surf ace esamleation S-.I longituJinal Seae could not be obtained ference Italte scanning coverage was obtained. This 89.82 from 41-1/2 taches to f or 1 inches of the limitat ion to outside of the i
Surface and Votumetric 44-l/2 inches I 44-l/2 laches of weld 12-inch esament of longitudt-length.
nel weld requiring subsequent esaminettee ISI.
I l-B&-20VCA-012-SlJM Voluestric coverage Branch connection inter-Volumetric and Surface Complete surf ace esselnation 3-J Longitudinal Sese could not be obtained ference tiette scanning coverage was obtained. Thle 39.12 free 41-l/2 inches to for 3 taches of the llettatlee is outelde of the Surf ace sad Volueetrie 44-l/2 inches L.
44-1/2 inches of weld 12-inch segment of longitudi-r length.
nel weld requiring subsequent esselnattan 151.
I l-St-25WCA-012-4tEl Valuestric coverage Branch connection inter-Voluestric and Surface Complete surf ace esamination 8-J Longitudinal Sese could not be obtained forence tintts scanolog caverage use obtained. This sp.12 from 20 inches to for 3-l/2 laches of the Itattatten is outelde of the surface and Volumetric 23-l/2 inches I 23-1/2 laches of us!d 12, tack segment of longitudt-
. length.
mal wete requiring subsequent esselnation ISI.
p i
l-BS-251CA-Ol 2-90C2 Volumetric coverage Due to the branch connec-Surfee Complete surface esamination
[
G t-J tranch Commection using 0* weld and 45*
tion weld configuration, coverage was obtained. A 39.11 transverse scans was not 0* weld and 45T weld Code-required 60* emmelnation Surface end Volumetric obt ained.
auseinstion commot be was performed free the main obtained.
run of pipe.
l' l-St-2SVCA-012-90C3 Volumetric coverage Due to the branch connec-Surface cumplete surf ace psaetnetton p-!
Stanch Conn..tton using O' weld and 45*
tion weld configuretton, coverage was obtained. A 39.11 transverse scans wee not 0* w*ld and 4ST weld Code-required 60* eseelmation Surface and Volumetric obtained.
esselnation cannot be was performed from the main obtained.
run of pipe.
I l-se-4WCA-Cl2-1 Lees than one-fourth of the to the branch connec-Volumetric and Surf ace Ceeplete surface esselnatten l
B-l Branch Connectinn-
~ the Code-required cover-tion configuration, a com-coverage was obtelned. 100E 1
89.ll to-pipe age of the louer ene-plate scan cannot be par-of the leegth of the weld was j
third weld volume could formed to provide full accesstble for scanning.
Surf ace and Volumetric not be obtained.
coverage.
See sketches Data Sheet Iso. 131121 for coverage plot.
a l
I-ta-28VCA-013-ISCI Volumetric coverage using Does to the branch con-Surface Complete surf ace esaminettoe 8-8 Branch Connection 0* weld and 45' trane-
%ction weld configure-coverage wee obtained. A 59.Il verse scene was not tion, a 0* weld and 45T Code-required 45* esaminat toe i
Serface and volumetric obt a ined.
welJ enaelmation cannot was performed f roe the main be obtained.
run of pipe.
j I
1 myrt "L" denotes the measurement from the reference aero putat established to map inJtcation/Italtation locatione either around the circumference ouJ/or along tim lengtte of a weld.
l
^ p SYSTDes teacter Bectremlat tee (Cont'd) i Class f
Category Emmelnatles Areal IdentIfIcatton of Itee see.
Esmelnattoe Seq.airement Liettattom taste for Belief pabrication ImE Remarke I
l-Be-20VCA-013-4 BCl Voluestric coverage with Due to the branch connec-Surface Complete surface esselnation B-J 2 ranch Connection the 45' treesverse scan tton weld configuration, coverage wee obtained. A 69.30 was not obtained.
a 45 transverse weld Code-required 45' esaelmation Sur f ace and Volumet ric esaetnation cannot be wa s pe r f ormed f rom the ma s a obtained.
run of pipe.
I l-tB-4VCA-011-1 Lees than one-fourth of Due to the branch connec-Volumetric and Surface Complete surface emmelnation B-J Branch Coenection-the CoJe-required cover-tion configuration, a coverage was obtained. 1003 59.11 to-Cap age of the lower one-complete scan cannot be of the length of the weld was third weld volume could performed to provide full acceselble for ocanning.
Surface and Volumetrie not be obtained.
coverage.
See sketchen. Datn Sheet ha. 181120 for coverage plot.
I l-8 B-5 2VCA-Cl 43-2 Complete valuestric Due to the weld crown con-Volumetric and Surf ace Complate surface esselnettua i
S-J pipe-to-pipe coverage could not be figuration, complete vole-coverage was obtained.
39.18 abta ned free 27-1/2 metric coverage for 6-l/2 e
Surf ace and Volumetric h.chas to 34 laches L.
laches of the 40 inches of total weld length cannot i
be obtained.
i 4
l-st-l!VCA-0143-5 Lees than one-fourth of Due to the abrupt base Volumetric sad Surface Complete surface esselnation p
B-J pape-to-Safe EnJ the Code-required cover-estal-to-weld tramattlos coverage was obtained.
89.81 age of the lower one-at S/36 to 7/8 such ni on See sketches. Data Sheet Surface and valuestric third weld volume could the upstreme side, com-llo. 181746 for coverage plot.
not be obtained.
plate volumetric coverage for the total weld length la not obtained.
I l-ES-4VCA-Ol 4-1 Less than one-third of Due to the branch connec-Surface Complete surface enantnation 1
B-J Branch Connection-the Code-required muer-tion configuration, a coverage wee obtained. 1003 j
39.88 to-cap age of the lower one-complete scan cannot be of the length of the weld was third weld volume could performed to provide full accessible for scanning.
Surface and Valuestric not be obtained.
coverage.
See sketches. Data Sheet Iso. 188116 for coverage plot.
I l
3 1-88-2084-192A-lpSI Complete surface esse-T>to integral attachment Volumetric and Surf ace Isoes B-K-I pipe Support snation could not be cause out be enseined oo Sto.IO
- obtained, the upst reme side due to Surface laterference free an espanaton joint.
i NOTEa
- l.* dee.otes the measurement free the reference Sete point estabitslied to map indicatlan/llettation locations either around the Circumference auJ/or along the length of a welJ.
i i
I
~
_~
4 s.
SVSTDt Reactse Becirtalettee (Cent'C) 1 el...
f Category Esamleat ten Areal ideettftcotten of I t ee see.
Esaessatsee seguiremoet Lietracten Baele for Relief Fahrleat See IIDE Remarks 1
1-se-20ea-192A-12 Ceeplete outf ace esse-Due to a permement pipe Volumetric and Surface lleen r
9-J Pipe-to-Velve laattee coverage could support, complete surf ace 39.28 set be obtained f ree saaetnet tom coverage f or 5erf ace 3-3/8 taches to 4-3/8 I such of the apprest-laches L.
mately 9-1/5 taches of wuld leegth commet be i
obtatsed.
l
)
I l-as-2CCA-204-3 Complete eerface same-Due to a peroament pipe Valuestric and Surface slow S-3 Pipe-to-Tee inattee coverage could empport, complete eurf ace est be obtaleed free eseeinettom coverage for 59.25 f
Serf ace 2 laches to 6 inches L.
& saches of the 7-9/16 inches of weld leegth caneet be obtained.
f l
l 1
1 1
i ta i
o i
}
j i,
l 1
l 1
I I
i 1
I I
I
}
l establis ted to esp indicatten/lleltatlee locattees ettbar around the cirewterance e
eenTE:
"L" denotes the meangrement f ree the ref erence sete point amJ/es.l.mg the length et a weld.
4 4
l, i
I
w g
i SYSTEMS Seeldest aset Semoval Claes casesery Enanteett Areal Identiftesttem of liee see.
Esselsatsee togetresset Llattetsee Basle for Belief Fabricassen MBE Bomart e i
B-3C-6984-001-21 Complete velametric Ihse to the weld jetot Volumetric and Surface Complete eerface exantastica 5-J Velve-to-Flange coverese could met be conftserattee, the 45*
coverage woe obtained. A 0*
39.11 ebtalmed.
esamtmattee coeld not veld and 45T weld esaminettee Surf ace and Telemetric he pertermed.
wee perfereed.
i l
3 1-tC-200LA-Oto-16 Complete volumetric
& breach commectise Volumetric and Surf ace Complete surf ace esselnettee B-J Pipe-to-Wales coverage could est be lleIts ocamelag for coverage wee s'atateed.
1 89.11 ehteleed M-l/2 tachee 4 taches of the 61-1/4 l
Serf ace and Wolmestric to 34-1/2 inches L.
taches of total weld teogth.
I 4
I l-3C-8 29tA4128-4 Complete velametric
& branch commectlee Velemetric and Serface Complete surface esmetaattee
)
3-3 Telve-to-Ftpe eeverage.ceold met be Itatte scanetag for coverage was obtateed.
39.38 abtalmed 19 inches to 3 taches of the 41-2/8 Serf ace and Telemetric 22 inches L.
taches of total weld i
length.
I l-SC-12Dt.A-OS6-Il Camplete surf ace esee-A permaneet empport Telmestric and Serface Complete volumetric coverage B-J Ftpe-to-Ethee teettee coverage could covere the esamtmation to obtalmed.
39.18 met be obtained free area for 18 taches of the Serf ace and Wel= metric 15 taches to 26 Inchee L.
40-l/2 taches of total l
ta weld length.
e*
I l-BC-82CCA-Il5-5 1.ees then eme-third of thee to the weld joint Volumetric and Serface Complete surface esaminettee d
S-J Flye-to-Bedectes Tee the Ceee-retatred cover-configurettaa, a complete coverage was obtateed. 1002 39.18 age of the lower eme-scae cannet be performed of the length of the weld was i
j Serf ace seJ Velmeetric third weless coverage to provide felt coverese.
accessible for scanning.
l could not be obtalm 4.
See sketches Data Sheet I
see. 188148 for coverage plot.
j l
1-ec-2 Dea-120-3 Complete eerface esse-A peroament pipe.
Telemetric and Serf ace This esamleetten eres le
&-3 Fire-to-Walee inattee coverage could restratet covers the esempt booed on the 80/nf88 89.23 set be obtataed free esaetmaties area ter Edities of the Code.
$=rf ace 2 taches to 5-l/2 taches 3-l/2 taches of the L.
6-l/2 tachee of total weld length.
I l-ac-2 Dea-120-5 Surface someteattee a permement pipe Volumetric and Surface This esseinettee area to j
n-J pape-to-medecer coverage could not be restratet covers the e sempt based as the 50/USl I
B9.2%
ebtelseJ.
essegnation area pre-EJiatem of the Cede.
Serface clading eastf ace esael-j matten.
I l
1 i
asuTEz
- L" 4. net ee the measurement free the ref erence aere potat established to map indicaties/lleitet toe locattees either areenJ the circumference aeJ/er along the length et a weld.
i 4
_.l
..se..d, Claes Caseseep
.teselsettee Areet identtiteettee et Fabricettee est temerke s
Lseaseelee teste for Bettet tsee me-Eeesteet toe new reemet I
l-3C-2 Dea-123-3 Complete eerface esentes-A pereeneet pipe Telemetric and Seef ace This meenteetten eten to esempt beoed em the as/ust time ceeermee emeld met restratet covers 2 seches Edis tas of the Cede.
0-3 valve-to-Ftpe he ehteleed free 1-1/2 of the apprestemtely 99.28 taches to 3-l/2 sechee L. ht/2 taches et tetet Serf ace meld length.
I l-3C-29en-323-4 Complete eerf ace esentes-A pereneemt pipe Telemetric and Serf ace Thte eseeleotten eres to sesept bened en the 09/WSt stem coverage coeld met restratet covere 2 taches Edittee of the Code.
B-3 pipe-to-tedecer he ehtetead from 1-1/2 et the apprestostely 39.21 taches to 3-1/2 tachee L.
Fl/2 taches of total Serf ace meld leagth.
4.s Os estehltebed to up ledicottes/llettettee Iecettees either eremad the carceeference ImaTV.:
- L" dresses the mee.oreers; free the reference sete ymset med/es steeg the temeth of a weld.
D e
_ m SYSTSN: Seector IAnter Clees WP Clase Category teamteettan areef Identifteetles of t r ee she.
seemseettee me,srement Llettettee teste fee settet Fabricet taa unt semerke 1
3-tG-4CE44t t-OL Lees them eme-half of Dee to the breech ese-Telemetric and Seeface Complete eerf ace esenteet ten 3-J beidelet-to-Ftpe the cede-regelred cover-eacties cemitgerettee,
coverage esse ehteleed. len:
39.33 age of the lower eme-a complete ocas comeet of the leagth of the useld ese Serface end Telemettle third esamteettee selssos he performed to provide acceselble for ocasales.
wee est obtateed.
felt coverage.
See ehetchee. Data Sheet Ite. 481644 for coverage plot.
I l-sc-4CEa-et 2-8 Lees thee see-third of Dee to the branch com-Telmestric and Seeface Complete eerface esamleetlee B-J Ifeldelet-to-Ftpe the Code-regelred cover-eecates configerettee, coverage esas obtelmed. 3002 39.11 ese of the Raeer eme-a complete ocas caseet of the leegth of Else meld esse Serface med valuestric third esenteet tee velame he performed to provide accessible for oceentes.
uses met etteleed.
felt coverage.
See obeschee, note Sheet tie. 1819 39 for coverage plot.
a.a se ItJTE:
"L* denetee the measerement free the reference sete potet established to map ledicot teelltettat tee lacet tsee either areemd the circumference and/se along the tength of a wetJ.
. -, _ ~..
(
\\
l SYSTtues age meat Cachenger Clase Cat egory Esmeleattee areef Identificettee of S t ee h.
Emmetaatsee Begetrasser Llettattee haste for Bellef Fabricarten Inf Semarks i
1 2
Ret 3182 Ceeplete wetametric Bus to the coeftgeretten Ilees Insee C-O assa Beat techaeGet
'A' esmeteattee coverage of of the 306 seas te, com-C2.29 the see maaste temer plate immer redtes cover-j Velemetric redine une est e6talmed.
age cammet he ehtateed f rom 4 taches to j
33-11/16 leches L and l
41-11/16 taches to i
F1-S/S leches L.
Esamteettee of the 104 eerste anser redtes to performed from the out-side surf ace bienJ i
radise. Due to the large moszte and vesset diameter ratie, and the sealI messte blend 6
radtse at the entside j
eerf ace, a meaalmsf at
+
esamleatlan et the 90*
end 270* episadraete commet he performed, to these
, ~.
g areas, the bleed radise coatIgeretSee tecreasee j
eigetiscantly due to car-t watere of the vessel unit. This, le caettaa-tien eith the correspeed-tag increases to estat j
path and regetred searen unit angle, preweets auf-
)(
fletent eltraeeand eeergy free Setersectlag the temer sedtes esamtmattee area, practedlag a esse-taoist osaetnettee.
i 1
l i
i ta3TE:
"L* Jemeses the meae.nreeent free the reference sere pelat estehllehed to esp ledicottee/ttestatten locattoes either atomed slee circumference aeJ/or eteeg the teegth of a weld.
a i
l
l
}w
(\\
i J
SYSTEBIs EIIS teet Eschenger 1
Cleee
}
Category feesteettee areef.
Identificet tee of lies me.
Esasseet see segelreesee Lt.Itatsee seate for tellet Fabricotles ISE Beesche
)
2 BIIEIS2 Complete velemetric Den to the configuretten itsee Isoaa 1
C-8 BIIR meet techenger
'A' esenteettee coeerage of of the M sessle, cam-l C2.20 the 106 assale tener plate tener reJtes cover-1 Velemetric redtes use est ehteleed.
ese caeeet he ehteleed 4
free 4 sechee to l
31-53/lb taches L and j
64-31/16 taches to i
78-5/8 seches L.
}
Enestaattaa of the IB6 measle tener redise to i
perfereed free the set-side eerface bleed redtee. Dee to the 1erse nossle end vessel dieseter rette med the emelt eerste hieed j
redtes et the estelde
[
eerface, e monetegfel esenteettee et the 98*
eed 270* quadreets caemet i
he perfereed. la these n
u
]-
cesfIgeretten theressee ten etees, the blend radies elselftcently Ane to car-watere of the weseel melt. This, to combies-
]j stem with the correspeed-l tag sacrosses la estel path and regelred eserch j
melt eagle, preweets esf-j f acteet altreameed emergy 1
free setersecting the tener redtes esenteetten area, practedtog a mese-2 8egfet seesteetten.
1 d
i i
l l
l l
ge2TE:
- L* denotes the messes eeems free the reference sure potet estehltehed to esp ledicottee/Ilottatten lacettene alther eroemd the circumference j
ee4/ar steeg the tresth of a weld.
4 N
O I
f SYSTesta age meet Bachanger (Cent'd) l Cle.e Category Esasteetion areal fdeettitcottaa of tese me.
taamsmettee negatresset Llet t et ten Seele for sellet yebrtestsee seg nemarke
{
nor cas,iete wei - tric w to the ca.figer.al.a mene name C-5 Bet beat Eschenger
'B' esmaleettee coverage of of the le6 eessle, cam-C2.20 the p6 motste sneer plate laser reAtos coeer-telemetric redine esse not ektelmed.
ese cannet be etteined from 4 taches to 11-13116 leches L and 41-13186 tachee to f
71-115 taches L.
Emmeteettee of the II4 I
mossle tener redtes le 1
perteamed free the est-l eiJe serface blend I
redten. Dee to the large ensale med vessel f
diameter rette, and the omall measle bleed j
reJ8me et the estelde ser,.c.. e
.t la.ttas.t t-,.-
I and 270* goedreets commet a.s he perfereed. la these
}
i arose, the bleed redine l
canfIgeretles Secreasee essetticantly des to cor-4 watere of the weseel l
isoll. This, to cambine-a I
ttan with the correspeed-I tag tecreeems to estal
)
path end regelred eserch I
eats angle, prevents omf-ficleet ultresemed emergy I
i free Setersecttag the
)
temer redine esseteatten j
area, practedtog a esse-lesful esamleattom.
4 I
i
)
i I
3 i
j eengEs
- t? Jemetes the erasereeest f ree the ref erence sete potes estahlteheJ to map indicat tem /Itattatlee locat taes alther aroemd the ctrewalerence
,I medles alang the leegth of a weld.
1 I
i i
m vw N
u"'N r
.. haes.. _..e C8.
Saoerhe Esenteettem areal Ident8fIcestem of Fabricotsee UDE teels f or Better Casegory Lietrattaa Isee me.
Esaelmetten Beestresset Name See to the setersecting alene i
Complete velemetric l
C-a age meet Eschenger 'A' consage coeld est be leegstedteal weld coettr-2 enIWla ekselmed free 1 %-314 mat tee, complete vote-Cl.le
$ bell-to-5helt taches to 133-1/8 taches estric coverage to met L and 92 tsches to 93-1/8 shteleed tot 2-1/2 tachee j
telemetste et the 157-7/8 tsches of tachee L.
total weld length.
i teses see to the totersecting uses l
Complete volumetric l
C-a tem meat Enchanger
'A' coverage caste est he lengstedteal weld coef tr-2 augv2 ehaaleed trea 90-118 estles, complete vels-Cl.l0 Shell -to-Shel t taches to 91-114 tacheo L estric coverage is est ehtstead for 2-l/2 Saches j
and IM-3/4 taches ce telemetric of the 114-l/2 taches of 138-118 tachen L.
tasal weld length.
Nees Lees than see-half of the Due to the flange-to-Telemetric 1
2 RN1-W4 est meat Enchanger
'A' Code-regelred fell wele-shett coeftgerattee, a l
metrac coverage could met complete ecos cammet he C-a Cl.te Shell-to-Flasse perfereed to prov8de the he ehtsteed.
iall coverage.
f Telemetate Less than ear-third of See to the coeftgeretten Velemetric Issee t.a C-8 ana meat Enchanger
'A' the Code-regelred cover-et the mesale-to-oheit.
<> 2 RNI-Wh C2.20 shasale-tv-Shell
.ege of the leser eme-a complete scan, commet he third weld velene could perfereed to provide felt I
est be obtatead.
coverage.
velametric Isome Lees then eme-half of the Due to the flaege-to-Volumetric
)
2 REE-W4 C-4 sina lemat Eschenger '8*
Code-required fell sele-shell configeractee, e metrte coverage could met complete aces commet be Ct.no Shell-to-Flasse perf ormed to provide the he ektelmed.
fell coverage.
valueesrle 14ee then see-half of pas to the coeftgeracten valueetric Isone I
2 aux-u6 C-3 aus usat Eschanger
'B' the Cade-regelred cover-of the nossie-to-ahell, C2.20 mesa te-to-SI.e t t age of the lower one-a complete ocas connet he third weld volume could perf ormed to' preside fell
(
met he ektelmed.
coverage.
Velemetric i
1 l
I 1
)
established to esp f adicot tes/ttestat ten lacettene either areemd the circumference sonTE:
L" desetes the messerement free the reference sete potet l
end/or aleeg the leasth of a weld.
4
f
[~'g m
m
\\
V SYSTDI: Ceca specy pumps Cissa teamtmatten areef Identtiteettee of taee so.
Esmelmettaa Seguirement _
Liefeattae Saale for Selief Fabricattee emE Romarbe Category l
Surface esselmetten This esaminetten area to Vetuestric and Surface 18eme 2
CSP-WI made Inaccesetble due to C-C Core Spray Pump 'A' coverage una mot abtained.
the pump lower section C&,80 betes withle a concrete 5erface j
pump pedestal.
2 C5P-W2 Ceeplete surface esse-Only 22 inches of the Valueetric stone C-C Core Spray pump ' A' taattee coverage une not weld length is accessible
- obtatsad, for esaetaatten. The C6.to balance of the esseine-Surface tlaa area to eaJe lasccee-sible by the concrete pump pedestet.
2 CSP-h%
Surf ace essetnetton Esselsation area le made Valueetric This esselsation will be performed when cles flange le inaccessible by flange C-C Core Spray Pump
'A' coverage wee not disassembled.
obtataed.
botte.
Cb.50 Seriace Surface esselsation This esamtmattee area is Volumetric and Surface stone 2
C5p-UX made inaccesell.le des to l
C-C Core Spray Puer 'B' coverage was not obtained.
the pump lower section y
C6.80 being withtm a concrete j
Serface pump pedestal.
i Volumetric Ilone 2
CSP-W2 Complete surf ace esse-Only 22 inches of the C-C Core Spray Pump
'R' inattom coverage was not weld length is acceselbte obtstmed.
for esselnattoa. The C6.to balance of the essetna-Serface tion area to ende inacces-sible by the concrete pump pedestal.
2 csp-US Surface esselsattoe Essetnetton area la ende Volmestric This enseinetton will be performed when the flange is inacceselble by flange i
C-C Care Spray Pump 'B' coverage was not disassembled.
obcatnad.
bolts.
Cb.10 Surface 2
CSP-WI Surf ace essetention This esamination area le valueetric an.t Surf ace sfone made inacceselble due to C-C Core Spray Pump 'C' coverage wee not abtained.
tlur pump tower section Ct.80 l
betag within a concrete 5.ar f ac e pump peJestet.
I f rom the ref erence aere polac estabitehed to esp ledicationlltettattom locatione either around slie circumf erence ente:
"L* deansee the measurement anJ/or almag the length of a weld.
i t
.~
\\
h.
h 5YSTDes Core Spray Pumpe (Cent'd) l Clase Category Esaminetten areaf IJenttiteettom of Ites No.
Esmelnattaa aequirement Lie t t at too asete for Relief Fabricettne NDE Romarb o I
2 C5p-U2 Complete surface esam-Only 22 inches of the valuestric Mene 1
C-C Core Spray Pump
'C' ination coverage use not veld length to accesalble l
C6.10 obtsteed.
for esselnation. The 1
Surface balance of the esselnation area to sede taaccessible by the concrete pump pedestal.
j 2
C5p-WI Surf ace saaetnation This essetnation area te volumetric and Surface None j
C-C Core Spray Pump 'D' coverage use not made inaccessible due to i
C6 30 obtained.
the pump louer section Surface being utthin a concrete pump pedestal.
I 2
C5p-v2 Complete eurface esam-Only 25 taches of the valuestric None C-C Core Spray Pump
'D' inatten coverage use not unto length to acceselble C6.50 obtained.
for esaminettoa. The Surf ace balance of the esamination 1
area is made inaccessible I
by the concrete pump 1
pedestal.
i i
t.a 2
C5p-US Surface esaelnation Emmetnettoe area le made Volueetric Thte essetnation util be C-C Cose Spray Pump 'D' coverage use not inaccessible by' flange performed when the flenge to j
j C6.10 ebtained.
bolte.
diesseeabled.
t Surface i
i l
i I
}
I i
I NuTE:
"I" denotes the measurement f ree the reference sete point established to map ladication/Italtation locattone either around the circumference j
enJ/or along the length of a weld.
e
E h
SYSTut Beeldual Neat Demow;l Pumpe Class Esselsatten Areal Identificattom of 8.leteatfoe Basle for Rollet Fabrication NDE nemarb e Craesory 1,
Ites No.
Esselnattee Requirement i
Surface eseelsation This emmelnation area te valueetrte and Surface Nome 2
BM-WI made inaccessible due to C-C Desidual Neet Removal coverage wee not l
CO lO Pump
'A' obtained.
the pump. lower sectlee being within a concrete i
pump pedestal.
surface I'
l 2
pier-W2 Complete surface esam-Only 30 faches of the Valuestric None C-C SestJuel least henovel ination coverage was not veld length is accessible CS.10 rump
'A' obtained.
for enastaattoa. The balance of the enseinstion 1
area to made inaccessible Surface by the concrete p.sep pedestal.
i Surface esamination Thle emaalastian area le valuestric and Surface' None j
2 RNP-WI made inaccessible due to C-C aseidual Nest Resovel coverage was not j
Cbl0 Pump
'S' obtained.
the pump lower section being within a concrete pump pedestal.
1 Surface f
2 anr-W2 Complete surface esse-Only 31-l/2 taches of the valueetric None e
C-C Seeldual Neat teenval inattom coverage was not weld length to accessible w
j C4.10 Pump 'a' obtained.
for eseelmattoa. The balance of the eseelmaties area le made inacceselbte I
Surface by the concrete pump
,edestal.
Voluestric None j
2-ater-W1 Complete surface esee-Surface esaminattoe C-C Beeldeal Neat Removal ination coverage was not coverage le met obcataed l
C4.to Pump
'8' obtained.
13 taches to 80-l/8 inches L due ts the concrete pump pedestal encaseeemt.
l Surface l
2 attP-WI Eurface ensegnation This exaeInstion area is Volumetric and Surface Ilone l
j C-C Reeldmal Neat Removal coverage was not made inaccessible due to C6.10 Fump
'C' obtained.
the pump lower section j
being within a concrete pump pedestal.
Surface j
I
)
free the reference sero point established to map indication /ttattation locatione either around the circualerence surTE:
~5 denotes the meae.erement anJ/or along the length of a weld.
l t
,M SYSTEN: geeldnel Ilset Demoval Pumps (Cent'd)
Close Cases *ty Enamtmation Area /
Identtiteetion of lies sea.
Eeeelmation Requirement Liefeatfoe Baate for Relief Fabrication IIDE tenettu 2
star-U2 Complete surface esse-Only M laches of the valuestric IIene C-C Realdwel Heat Demoval testion coverese wee not veld length is acceostble C6.10 Ney 'C' obtained.
for easetnation. The belance of the essetnettee area le made inaccemelble Surface by the concrete pump pedestal.
2 sper-JI Surface esentsation This eneminetton area la Volumetric and Surface Home C-C RealJuel IIeet menoval coverage wee not made teacceecible due to C6.10 Pump
'D' obtaleed.
the pump tower section betag within a concrete Surface pump pedestal.
2 Bitr-W2 Complete surface esam-Surface examinetton Voluestric Ilone C-C Reeldeal lleat kemoval laation coverage vos not coverage le not obtained C6.10 Pump 'D' obtaleed.
from 14 taches to 139 laches L due to the coa-crate pedestal anoneesent.
Surtace p
2 RitP-U)
Complete errisco esse-Surface eseelmaston Volumetric None O
C-C Beeldual Neat Removal inattom coverage wee not coverage la mot obtained C6.10 fuep 'O'
- obtained, from 15 inchee.to 80-1/4 inches L due to the con-Surface crate pedestal encasement.
180TE:
"t." denotes tl.e measurement from the reference sera point established to map indication /llettet tua locatione either around the circuaterance anJ/or along alw length of a weld.
2 l
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REACTOR VESSEL EIAMINATICN VOLUME COVERAGE 1
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Sheec 1 l
Table 2 REACTOR VESSEL ELWJNAIION VOLLM COVERAGE Weld Description Exam Forcent of Code Figure ag_W ljJo.
43gJe hing_IdtsiES$
No +
i RPV1-W3 45 80.65 1&4 Shell to Tiange 60 91.72 circumferencial Weld 0
58.00 45T 42.13.
60T 42.15 Cumulative
- 91.72 RPV1-WA 45 89.06 1
Shell to Shell 60 92.42 Circumferencial Wald 0
74.71 45T
- 90. 4 9 60r 91.59 Cumulative 92.59 RPV1-W5 45 46.07 i
Shell to Shell 60 52.87 Circumferencial Wald 0
- 43. 44 45T 45.42 60r 46. 2 8 Cumulative 52.87 RPV1-W6 45 43.74 1
Shell to Shell 60 51.51 O'
Circumferencial' Weld 0
35.00 45T 44.6 9 60I 52.73 Cumulative 52.73 RPv1-W7
-45 96.3 0 2
Shell to Shell 60 98.15 Circumferencial Weld C
77.20 45T 96. 3 0 60I 98.15 Cumulative 98.15 RPVI-W8 45 77.02 2
Lower Hesd To Shell 60 84.15 Circumferencial Wald 0
62.76 45T 89.58 60T 91.3 0 Cumulative 91.3 0 RPVI-W11-1 45 96.30 I
longitudinal Weld 60 98.15 3 30 Dog 0
77.78 45T 96. 3 0 6 CT 98.15 Cumulative 98.15
- Cuzolative Coverags is : hat percentage of the Coda required examinacien volu=e s canned with at lesse one angle beam.
42
Sheet 3 Table 2 REACTOR VESSEL EIMi1 NATION, VOLUME COVERAGE (CCNT'D)
Weld Description Ezan Percent of Code Figure V 1Bi_lB Ei22d No.
and Weld No.
4,g313 2
EPV1-W13-3 45 96. 3 0 1
Longitudinal Wald 60 98.15 6 275 res 0
77.6 9 45T
%.30 60T 98.15 Cumulative 98.15 RPY1-W1421 45 96. 3 0 2
Lee.gitudinal Weld 60 98.15 8 90 Des 0
77.78 45T 96. 3 0 8
60T 98.15 Camulative 98.15 RPV1-W14-2 45 96.3 0 2
Longitudinal Weld 60 98.15 8 210 Des 0
77.78 45T 96. 3 0 60T 98.15 Cumulative 98.15 4
RPY1-W14-3 45 91. 91 2
)
Longitudinal Weld 60 93. 6 7 l '(\\j 8 330 Deg' 0
74.23 45T 92.12 60T 93. 8 0 Cumulative 93. 80 EPV1-W15-1 45 64.31 2
Longitudisal Weld 60 67.10 I.
8 18 Des 0
75.92 45T 79.55 l
60T 81.5 8 l
Cumulative 81.5 8
. RPVI-W15-2 45 96. 3 0 2
I l
Longitudinal Wald 60 98.15 8 138 Des 0
77.73 i
45T 96. 3 0 6 0T 98.15 l
Cumulative 98.15 t
EPV1-W15-3 45 96. 3 0 2
Longi:udinal Weld 60 98.15 0 258 Des 0
77.78 l
AST 96. 3 0 60; 98.15 Cumulative 98.15 t
1 44
Shent 2 Table 2 REACTOR VESSEL EXAMINATION VOLUME COVERAGE (CONT'D) f Wald Description Ezan Percent of Code Figure and Weld No.
43312 M B1 3 23 DES $
J9 %
EPV1-W11-2 45 96.3 0 1
Longitudinal Wald 60 97.3 5 8 150 Dog 0
77.78 45T 96. 3 0 60f 98.15 Cumulative 98.15 EPVI-W11-3 45 96. 3 0 1
Longitudinal Wald 60 95.3 0 0 270 Des 0
77.78 45T 96.3 0 60T 98.15 Cumulative 98 13 IFV1-12-1 45 96. 3 0 1
Longitudinal Weld 60 98.1 5 8 110 Dog 0
- 90. 77 43T 96. 3 0 60I 98.15 Cummlative 98.15 kPY1-W12-2 45 84.26 i
Longitudinal Weld 60 80.3 1 8 230 Dog 0
85.52 95.40 45T t
6' 97.23 Cumulative 97.23 12Vl-W12-3 45 96.3 0 1
Longitudinal Wald 60 98.15 8 350 Des 0
- 87. 87 45T 96. 3 0 60r 98.15 Casulative 98.15 RPY1-W13-1 45 78.93 1
Longitudinal weld 60 77.73 8 35 Des 0
67.32 45T 72.79 6 02 74.18 Cumulaeive 78.93 RFY1-W13-2 45 62.38 1
longitudinal Weld 6J 63.58 8 155 Des 0
50.30 AST 59.82 60T 61.48 Cumulative 63.58 O
43
__- -__, _ ~.
Sheet 4 Table 2 O
REACTOR VESSEL EI4MINATION VOLUME COVERAGE (CONT'D)
Wald Description Exam Percent of Code Figure and Weld No.
43g13 Volume Egggjggd No.
EPV1-W16-1 45 6 1. 96 2
Lower Head 60 63.16 Meridional Wald 0
50.18 6 22.5 Des 45T 62.87 60r 64.88 Ceaulative 64.88 EPV1-W16-2 45 59.61 2
Lower Head 60 62.69 Meridional Weld 0
50.43 6 67.5 Dog 45T 64.40 60r 64.40 Cumulative 64.40 RPY1-W16-3 45 62.27 2
Lower Head 60 63.46 Neridional 0
51.05
@ 112.5 Des 45T 62.73 60T 65.18 Cumulative 65.18 EPY1-W16-4 45 62.27 2
O lower Head 60 63.44 Meridional Weld 0
51.05 6 157.5 Des 45T 62.73 60T 65.18 Cumulative 65.18 RPV1-W16-5 45 62.74 2
Lower Head 60 63.94 Meridional Weld 0
51.43 6 202.5 Des 4Fr 63.64 60T 65.66 Cumulative 65.66 l
2PY1-W16-6 45 62.74 2
l Lower Head 60 63.94 Meridional Weld 0
51.43 l
45T 63.64 6 247.5 Des j
60T 65.66 Cumulative 65.66 RPY1-W16-7 45 62.74 2
Lower Head 60 63.94 Meridional Weld 0
51.43 6 292.5 Dog 45T 63.64 60I 65.66 Cumulative 65.66 O
1 f
45
Shut 5 Table 2 REACTOR VESSEL W M N TION VOLUME COVERAGE (CONT'D)
Wald Description Exas Percent of Code Figure sad Weld No.
M Y2] gg h iggd No, IPV1-W16-8 45 62.74 2
laver Baad 60 63.94 Meridional Weld 0
51.43 8 337.5 Des 45T 63.64 6CT 65.66 Caulative 65.66 IPv1-W9 45 94.46 2
laver Head Dome 60 72.25 Circumferencial Weld 0
78.98 45T 96.3 0 60r 98.15 Cumulative 98.15 RPV1-W20 45 80.06 3
Closure Head to Flange Weld 60 88.45 0
48.34 45T 46.6 0 60r 47.50 Cumulative 88.45 EPVI-W22 45 96. 3 0 NA Closure Head Dome 60 98.15 t O Circumferential Wald 0-77.78
- 45T
%.30 6CT 98.15 Cumulative' 98.15 RPV1-W24 through E 45
%.30 NA Closure Head 60 98.15 Meridional Welds 0
77.78 45; 96.3 0 60r 98.15 Cumulative 98.15 RPV1-NIA 45 42.83 5
Nozzle to Shell Wald 60 55.62 ~
0 20.14 Nozzle Inside Radius 24 & 34aL 85.72 RPY1-N13 45 42.97 5
Nozzle to Shell Weld 60 56. 0 9 0
17.61 Nozzle Inside Radius 24 & 34aL 85.72 EPv1-N2A.3.E.F.C.& E 45 59.45 6
Nozzle to Shell Welds 60 68.47 0
29.39 i
Nozzle'Inside Radius 18 & 23RL 100.00 46
Shent 6 Table 2
~
REACTOR VESSEL EIAMINATION VOLUME COVERAGE (CONT'D)
Weld Description Ezan Percent of Code Figure and Weld No.
Agg13 7,gj g d g g f No.
RPVI-N2C & R 45 59.45 6
Nozzle to Shell Walds 60 68.30 0
29.39 sozzle Inside Radius 18 & 23RL 100.00 RPY1-N2D & J 45 59.45 6
Nozzle to Shell Welds 60 68.37 0
29.39 Nozzle Inside Radius 18 & 23EL 100.00 RPY1-N34.3.C.& D 45 37.03 7
Nozzle to Shell Welds 60 43.88 0
15.29 Nozzle Inside Radius 25EL 100.00 RPY1-N4A & E 45 43.36 8
Nozzle to Shell Welds 60
$3.39 0
23.38 Nozzle Inside Radius 19 & 26EL 100.00 RPY1-N45 & D 45 40.16 8
Nszzle to Shell Welds 60 48.45 l
0 19.12 l
Nozzle Insida Radius 19 & 26EL 100.00 RPY1-N4C & T 45 32.64 8
Nozzle to Shell Welds 60 40.18 0
17.61 Nozzle Insica Radius 19 & 261L 38.75 l
I l
RPV1-N54 & 3 45 57.80 9
Nozzle to Shell Welds 60 66.87 0
25.97 Nozzle Inside Radius 17 & 2"RL 100.00 RPY1-NGA & B 45 78.10 10 Nozzle to Shell Weld 60 83.58 0
37.94 Inside Radius Section 60 100.00 RPV1-N7 45 72.49 11 Nozzle to Shell Wald 60 77.40 0
64.06 Inside Radius Section 60 100.00 O
47
Shve 7 Table 2 REACTOR VISSII. EXAMINATION VOLQfE COVERAGE (CONT'D)
Weld Description Ezam Percent of Code Figure and Veld No.
h ig f h ggf L,
RPV1-N8A & B 45 81.73 12 Nozzle to Shell Velds 60 87.27 0
59.54 Inside Radius Section 60 100.00 i
RPV1-N9 45 81.73 12 Nozzle to Shell Weld 60 87.27 3
0 59.54 Inside Radius Section 60 100.00 RPVI-N17A.B.C. & D 45 56.11 13 60 64.18 Bozzle to Shell Wald O
~ 21. 5 9 Insida Radius section 18 & 23R7.
100.00 0
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Class Category Esamtsettaa Areal Identificattaa of I tee sto.
Essetnetton Rep trement Liettation Baels for Retter Fabricetton IIDE Reserke I
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provide beam component coverage to two direc-tiene se regelred by procedure.
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I l-se-29VCA-Ol1-1 The Code volume 4tJ not th:e to the pump-to pipe 18one B-J rump-to-ripe receive two-directional teeld ccattgesration, a 59.ll coverage.
complete scan could not l
Surface and Volumetric be performed to provide two-directional ham j
component coverage of_the Code volume.
I l-te-2sVCA-Ol3-2 The Code volume did not Ihse to time pipe-to-valve IIone B-I ripe-to-Valve receive two-directional configieration, a complete 89.11 coverage.
scan could not be per-Serf ace and volumetric formed to prov8de two-directional beam cneponent coverage of tlie Code volisme.
i i
l-te-20VCA-Oll-1 Apprestastely eme-third thee to the valve-to-elbow None j
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Esselsatton Requirement I. imitation taala for Roller Fabricattoe NDE Remarks 5
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39.81 Ftpe directlanal coverage.
atng was Italted, preclud-tag complete procedural l
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l 5
t-te-4TCA-Ot4-2 The procedure volome Due to the branch connec-Ttse-directional coverage of t-J Branch Connection-to-did not receive two-tion configurstloa scan-the Code volume wee obtained.
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gemeinettae Requirement Liettation toela for Ret tef Fabrication HDE Romerh o i
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i l-ac-20CCA-It4-1 Apprestaately one-half Diee to Llee reducing tee-Ilone B-l med.actas Tee-to-Fire of the Code votiene to pipe configuration, 39.18 did not receive two-a complete scan co.ald not Serface and Valuestric directional coverage.
be performed to provide j
beam component coverage 4
in two directions as regelred by procedure.
I l-SC-12CCA-ll6-5 Approutmetely one-half Dies to time pipe-to-Ilone a-t Flee-to-Reductas Tee of the Code volume reJucing tee configeste-39.81 did not receive two-tion, a complete sean Surface and Votuestric d;rectional coverage, could not be performed to provide been component j
coverage in two direc-ttone as required by I
procedure.
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ATTACHMENT 2 i
HOPE CREEK GENERATING STATION ISI BOUNDARY DIAGRAMS i
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Inservice Inspection Boundary Diagrams are not available at this time.
They will be provided no later than December 15, 1986.
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