ML17308A183
| ML17308A183 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/02/1987 |
| From: | Anderson E FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17221A373 | List: |
| References | |
| MCI-PSL-100, NUDOCS 8709090272 | |
| Download: ML17308A183 (262) | |
Text
INSERVICE INSPECTION SECOND TEN YEAR
SUMMARY
. PROGRAM DOCUMENT NO. MCI-PSL-100 REVISION NO. 0 DATE :
9/01/87'REPARED BY FLORIDA POWER & LIGHT COMPANY MATERIALS,CODES AND INSPECTIONS SECTION 700 UNIVERSE BLVD.
JUNO BEACH, FLORIDA 33408 FOR PLANT ST. LUCIE UNIT 1 P.O.BOX 128 FT ~ PIERCE, FLORIDA. 33454 COMMERCIAL SERVICE DATE : 21 DECEMBER 1976 NRC DOCKET NUMBER : 50-335 PREPARED BY : G.P.ALEXANDER
ISI SPECIALIST:
REVIEWED BY DATE ISI EN INE APPROVED BY DATE
' T ON S PE VISOR C & P I
AUTHORIZED BY DATE z 8+
MANAGER MCI 1
8709090272 870902 PDR ADOC)('5000335 ':
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ABSTRACT This document describes the basis and plans for the Second Ten Year Inservice" Inspection Summary Program for St. Lucie Unit 1. This summary addresses the requirements of the ASME B&PV Code Section XI,1983 Edition through the Summer 1983 Addenda, and is subject to the limitations and modifications stated in 10 CFR 50.55a (b)(2)(i). In addition, Code Case N 408, Alternative Examination of Class 2 Piping Section XI, Division 1 is incorporated as Rules'or applicable. Requirements for augmented examinations are also addressed. ti As requirements 'et permitted by 10 CFR 50.55a (g)(4)(iv), FP&L may elect to invoke the forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a (b),subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval.
Included in this summary are the applicable Relief Requests and tables identifying all items subject to examination by Code Category and item number.
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TABLE OF CONTENTS TITLE PAGE ABSTRACT TABLE OF CONTENTS RECORD OF REVISIONS LIST OF ABBREVIATIONS
1.0 INTRODUCTION
1.1 General 1.2 Applicable Editions &, Addenda to Section XI 1 ~ 3 System Classification 1.4 Inspection Program 2,0 Development of the Inspection Program F 1 Class 1 2.1.1 ASME Code Exemptions Employed 2.1.2 Component/Piping Examination Development 2.1.3 Component Supports 2.1.4 System Pressure Tests 2.1.5 Instrumented Inspection Technique 2.1.6 Repair and Replacement 2.2 Class 2 2.2.1 ASME Code Exemptions Employed 2.2.2 Component/Piping Examination Development 2.2.3 Component Supports 2.2.4 System Pressure Tests 2.2.5 Instrumented Inspection Technique 2.2.6 Repair and Replacement 2.3 Class 3 2.3.1 ASME Code Exemptions Employed 2.3.2 Component Supports 2.3 ' System Pressure Tests 2.3.4 Instrumented Inspection Technique
- 2. 3. 5 Repair and Replacement 2.4 Flaw Indications 2.5 Class MC Components 4
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3.0 Relief Requests 3.18c2 General 3.3 Format 3.4 Relief Request Tables 3' List of Applicable Relief Requests 4' Evaluation Criteria 4.1 Class 1 Acceptance Standards 4.2 Class 2 Acceptance Standards 4.3 Class 3 Acceptance Standards 4.4 Acceptance Standards for Supports (Class 1,2,3) 5.0 Submittal Summary 5.1 Description of ISI Plan Format 5.2 Description of Summary Submittal Tables 6.0 Records and Data Management 7.0 Appendices A CLASS 1 EXAMINATION
SUMMARY
TABLES B CLASS 2 EXAMINATION
SUMMARY
TABLES C CLASS 3 EXAMINATION
SUMMARY
TABLES D CLASS 1 HANGER
SUMMARY
TABLES E CLASS 2 HANGER
SUMMARY
TABLES F CLASS 3 HANGER
SUMMARY
TABLES G ASME CODE CASES 8.0 Code Boundary Drawings LIST OF FIGURES.
5.1.1 Inservice Inspection Plan Table 5.2.1 Summary Submittal Table
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RECORD OF REVISIONS REV. DATE SECTION PAGE DESCRIPTION APPROVAL/
NO. PARA'EASON FOR CHANGE DATE .
0 9/01/87 ORIGINAL ISSUE
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ABBREVIATIONS Listed below are the abbreviations utilized in this document:
AFW AUXILARY FEEDWATER ASME AMERICAN SOCIETY OF MECHANICAL ENGINEERS ASB AUXILIARY SYSTEMS BRANCH (formerly APCSB)
B&PV BOILER &, PRESSURE VESSEL CODE BTP BRANCH TECHNICAL POSITION CONDENSATE SYSTEM CC COMPONENT COOLING WATER SYSTEM CEDM CONTROL ELEMENT DRIVE MECHANISM CFR CODE OF FEDERAL REGULATIONS CRV CODE REQUIRED VOLUME C8r,PG CODES 8c, PROGRAMS GROUP cw INTAKE COOLING WATER SYSTEM ECT EDDY CURRENT TESTING FP&L FLORIDA POWER &, LIGHT COMPANY FINAL SAFETY ANALYSIS REPORT ISI INSERVICE INSPECTION ID INSIDE DIAMETER HPSI HIGH PRESSURE SAFETY INJECTION JNS JUNO -NUCLEAR ENERGY SERVICES LPSI LOW PRESSURE SAFETY INJECTION MSIV MAIN STEAM ISOLATION VALVE MCI MATERIALS,CODES 8c INSPECTIONS GROUP MFW FEEDWATER SYSTEM MSS MAIN STEAM SYSTEM NUCLEAR REGULATORY COMMISSION
ABBREVATIONS (cont,)
NPS -
NOMINAL PIPE SIZE OD OUTSIDE DIAMETER PAID PIPING &, INSTRUMENTATION DIAGRAM PRZR PRESSURIZER PSL-1 PLANT ST. LUCIE UNIT 1 REACTOR PRESSURE VESSEL RCP REACTOR COOLANT PUMP SRP STANDARD REVIEW PLAN THICKNESS OF COMPONENT, PIPE, ETC.
USAS USA STANDARD VT VISUAL TECHNIQUE I.E. VT-1,VT-2
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1.0 INTRODUCTION
1.1 General 1.1'.1 This Summary Submittal describes the St. Lucie Unit 1 Second Ten Year Inservice Inspection Program. This Program will be implemented for the Second Inspection Interval which starts 11 Feb.1988,and ends 11 Feb.1998.
The Inspection Program, which consists of ASME Class 1,2,and 3 systems, components, and related supports, is being developed giving due consideration to the following documents:
Section XI of the ASME Code Section III of the ASME Code Section V of the ASME Code Code Case N-408 Branch Technical Position, ASB 3-1 Standard Rreview Plan 6.6, Section USNRC Regulatory Guides I,II Regulatory Guide 1.147 Regulatory Guide 1.26 Regulatory Guide 1.14 Regulatory Guide 1.150 Regulatory Guide 1.65 Regulatory Guide 1.83 St.Lucie Unit 1 Technical Specifications St.Lucie Unit 1 Final Safety Analysis Report 1.1.2 The program for Inservice Testing of Class 1, 2, and 3 pumps and valves is addressed separately.
1.1.3 The First Ten Year Inservice Inspection was conducted in accord-ance with the following editions of Section XI.
A. First Period (40 months) 1970 Edition thru the Minter 1970 Addenda BE Second and third periods 1974 Edition through Summer -1975 Addenda for BOP Components (see reference 1 and 2).
C. RPV Examinations to 1977 Edition through S 1978 addenda, and R.G. 1.150 Rev. 01 (see reference 3).
D. System Pressure Tests, 1980 Edition through N 1981 Addenda (see reference 4 and 5)
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1.1.3(cont.)
The correspondence referenced below relates to NRC acceptance to code ch'anges:
1 .. FPM letter: L-77-302, dated 7/1/77 and 9/87
- 2. FP&L letter: L-,81-203, dated 9/21/81
- 5. NRC TAC-Nos. 59918 and 59919 1.2 Applicable Editions and Addenda to Section XI Pursuant to Title 10 of the Code of Federal Regulations, part 50, paragraph 50.55 (a),the Inservice Inspection requirements applicable to nondestructive examination and system pressure testing at St.Lucie Unit 1 are based on the rules set forth in the 1983 Edition of ASME Section XI through Summer 1983 Addenda, hereafter referenced to as ASME Section XI.
As permitted by 10 CFR 50.55a (g)(4)(iv), FP&L may elect to invoke the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a (b), subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval. Portions of editions and addenda may be used provided that all related requirements of the respective editions and addenda are met.
It is FP&L's intent to continually evaluate and apply, as appropriate changes in adopted Code editions and addenda which will improve the overall quality and safety of the ST.Lucie Unit 1 nuclear power plant.
1.3 System Classification The Construction Permit for St. Lucie Unit 1 was issued in July, 1970. The Commercial Operating License was issued in March 1976.
Florida Power and Light Company is the owner of record.
Vessels, piping, pumps,and valves were built and installed according to the rules of ASME Section III and USAS B31.7 for those systems classified as Class 1, 2, and 3.
The system classification used 'as a basis for the Inservice Inspec-tion Plan are based on the requirements of 10 CFR 50.2 (v) and the Regulatory Guide 1.26.
Class 1 System Boundaries were developed based on 10 CFR 50.2 (v).
Class 2 and 3 System Boundaries were developed based on Regulatory Guide 1.26.
Code Boundary diagrams are provided to show the specific boundaries for Class 1, 2, and 3 systems in Section 8 of this Submittal.
1.4 Inspection Program Examinations for the Second Ten Year Interval will be scheduled in accordance with Inspection Program B, as described in IWA-2400 of ASME Section XI, for all Class 1, 2,and 3 systems, components, and supports.
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2.0 DEVELOPMENT OF INSPECTION PLAN This section is the detailed description of the Inspection Plan basis for each component and/or system to be examined.
2.1 Class 1 Systems The Class 1 System Boundaries are developed based upon the require-ments of 10 CFR 50.2(v), and the St.Lucie Unit 1 FSAR. The systems/
Components to be examined in the Class 1 System are described in detail below:
2.1.1 ASME Code Exemptions Employed IWB-1220: The following components (or parts of components) are exempted from the volumetric and surface exami-nation requirements of IWB-2500:
(a) Components that are connected to reactor coolant system and part of the reactor coolant pressure boundary and are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal operating conditions is within the capacity of makeup systems which are operable from onsite emergency power; (b) component connections, piping, and associated valves of 1 inch nominal pipe size and smaller, except for steam generator tubing; (c) Reactor head connections and associated piping, 2 in. nominal pipe size and smaller, made inaccessible by control rod drive penetrations.
2.1.2 Component/Piping Examination Development Reactor Pressure Vessel The longitudinal weld seams (9), shell side of the flange to shell weld, upper shell to intermediate shell circumferential weld, inter-mediate to lower shell circumferential weld, lower shell to bottom head circumferential weld, bottom head disk weld, and bottom head meridional welds(6), nozzle to shell welds(6), nozzle inner radii(6),
nozzle to extension piece and extension piece to pipe circ.welds are examined from the I.D. surface using remote examination equipment and techniques. Those areas of the bottom head which are obstructed from a complete I.D. examination are manually examined from the O.D. surface to the maximum extent possible. The flange to upper shell weld is examined from the upper shell I.D. surface and from the flange seal surface manually(UT). The flange ligaments are exam-ined manually from the mating surface. Closure studs are manually examined using surface and volumetric techniques when removed, 11
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Reactor Pressure Vessel (cont.)
Relief Request (RR-1) covers the areas which are not examinable.
Core support lugs and the remainder of the vessel interior are examined visually utilizing remote television equipment.'A permanent visual record of these areas is recorded.
The Core Barrel including the repaired areas will be visually exam-ined during the scheduled ASME Section XI B-N-1 visual examinations to the extent possible, with the entire Core Barrel being examined at or near the end of the Inspection Interval.
The RPV examinations will be performed to meet the intent of the requirements of Regulatory Guide 1.150 and ASME Section XI.
Reactor Vessel Closure Head All ultrasonic examinations are performed manually. The flange to shell weld, dome circumferential weld, and the head meridional welds (6) will be examined from the O.D. surface to the extent practical due to obstruction by the CRDM penetrations. Refer to Relief Request (RR-2) for areas not examinable.
The peripheral CRDM welds and extension tube welds, are subject to surface examination (PT) to meet the requirements of Category B-0 inservice inspection requirements.
The RPV Closure Head examinations will be performed to meet the intent of the requirements of Regulatory Guide 1.150 and ASME Section XI.
Steam Generators (Primary Side)
All examinations are performed manually from the O.D. surface of the components. Areas to be examined include the tube sheet to extension piece wel'd, extension piece meridional welds(4), extension piece to lower head weld, lower head meridional welds, nozzle to vessel welds nozzle inner radii, support skirt to vessel weld and stay cylinder welds. Primary bolting receives a visual examination. Refer to Relief Request (RR-3) for areas not examinable.
Pressurizer All volumetric examinations are done manually from the O.D. surface.
Areas include both shell to head welds and 1 foot of their respec-tive intersecting longitudinal welds(2), nozzle to shell welds, and a visual examination of manway bolting.
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Pressurizer(cont.)
Refer to Relief Request (RR-5) for areas not examinable.
Four support bracket welds and the support skirt weld receive a surface examination.
Reactor Coolant Pressure Boundary Piping All volumetric examinations are conducted from the O.D. surface with the exception of the Reactor Vessel nozzle to extension and extension to pipe welds (as addressed under Reactor Vessel), Areas to be examined include circumferential welds, longitudinal welds, and branch connection welds.
Refer to Relief Request. (RR-6) for areas of welds not examined.
Welds on piping greater than 1 inch nominal pipe size are selected for examination in accordance with Table IWB-2500-1, categories B-F and B-J as follows:
a) All terminal ends in each pipe or branch run connected to vessels b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions:
- 1) primary plus secondary stress intensity range of 2.4S m for ferritic steel and austenitic steel;
- 2) cumulative usage factor U of 0.4.
c) All dissimilar metal welds between combinations of:
- 1) carbon or low alloy steels to high'lloy steels;
- 3) high alloy steels to high nickel alloys.
d) Additional piping welds so that the total number of circumferent-ial butt welds (or branch connectioncizcumferential or socket welds) selected butt welds (or for examination equals 25% of the branch connection or socket welds) in the reactor coolant system.
This total does not include welds excluded by IWB-1220.These addi-tional welds may be located in one loop.
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Reactor coolant Pressure Boundary Piping (cont.)
One loop as defined for PWR Plants:
a) one hot leg and one cold leg in one reactor coolant piping loop; b) one branch, representative of an essentially symmetric piping configuration among each group of branch runs that are connected to reactor coolant loops and that perform similar system functions; c) each piping and branch run exclusive of the categories of loops and runs that are part of a) and b) above, Reactor Coolant Pumps As required by Regulatory Guide 1.14, the bore and keyway areas of each reactor coolant pump flywheel are examined ultrasonically once each period. Additionally, the flywheels receive a 100Yo volumetric examination (UT) and a surface examination near the end of each Inspection Interval.
A 100% volumetric examination (RT) is required to be performed on the casing upper and lower scroll welds, and a visual examination of the 'casing internal surfaces of one (1) reactor coolant pump. These examinations are the subject of Relief Request (RR-7).
The RCP studs are examined ultrasonically from the bore hole,and the nuts are visually examined (VT-1) inplace. In the event the pump is disassembled,( see Relief Request (RR-7)) the bolting and flange surface are visually examined.
Steam Generator Tubes The Steam Generator tubing surveillance requirements are contained in the Plant Technical Specification 3/4.4.5. This specification is based on a modification of USNRC Regulatory Guide 1.83, Revision 1, as modified by St.Lucie Unit 1 Technical Specifications and contains-.
the requirements for sampling, acceptance, plugging and reporting.
Eddy current examination of steam generator tubing is conducted in accordance with Article IV of ASME Section XI.
Valve Bodies: Internal Surfaces Class 1 valves exceeding 4 inch nominal pipe size are required to receive a visual examination (VT-3) of the internal surfaces. Refer to Relief Request (HR-8) for clarification.
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Component Supports Class 1 Integral attachment welds are selected and examined per the require-ments of Table IWB-2500-1, Categories B-H and B-K-1. Class 1 compon-ent supports subject to examination are selected in accordance with Subarticle IWF-2510.Those supports selected receive a visual examin-ation (VT-3) to determine their general mechanical and structural condition. An additional visual examination (VT-4) is performed on spring type supports and mechanical/hydraulic snubbers to determine conditions relating to their operability to the extent of confirming their functional adequacy, verfication of settings or freedom of motion, as applicable.
The functional testing requirements, testing method, and extent and frequency of testing for mechanical and hydraulic snubbers shall be governed by the Plant Technical Specifications.
System Pressure Tests Class 1 System pressure tests are conducted on Class 1 systems'nd components as follows:
a) A System Leakage Test is conducted prior to plant startup following each refueling outage. The pressure retaining boundary subject to the leakage test corresponds to the reactor coolant system boundary, as established with all valves aligned as required by approved plant operating procedures for startup and normal reactor operation. The VT-2 examination boundary extends to include the second closed valve at the boundary extremity, which may be a check valve opposing Reactor Coolant system pressure. The test is conducted at system operating temperature and pressure.
b) A System Hydrostatic Test is conducted on all Class 1 piping and components within the system boundary at or near the end of the Inspection Interval. The system test boundary is determined in accordance with the requirements of paragraph IWA-5229 of the Code.
2.1.5 Instrumented Inspection Technique (IIT)
FP&L will continue to utilize the Instrumented Inspection Technique for only those portions of Class 1 systems which have been eval-uated in accordance with H.A.F.A. International Topical Report: HAFA 135(P),Section IV. The IIT, where employed, is done in lieu of both the system functional test and system hydrostatic test and is employed each period, if applicable.
Reference Letter- L-85-379, Dated Oct.4,1985(Request Documents'P8rL for approval to use Instrumented Inspection Technique)
NRC Letter, Dated Nov.8,1985 (TAC ¹59917) 15
Repair to Class 1 components, piping, and supports is done in accord-ance with the requirements of IWA-4000 and IWB-4000,ASME Section XI.
Replacement of Class 1 components, piping, and supports is done in accordance with the requirements of IWA-7000 and IWB-7000 of ASME Section XI.
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2.2 Class 2 Systems The Class 2 Systems Boundaries are developed based upon the require-ments of Regulatory Guide 1.26 and St.Lucie Unit 1 FSAR.
Specific examination requirements for components and systems are based upon the requirements of ASME Section XI and as modified by 10 CFR 50.55a paragraph (b)(2) (IV) and Code Case N-408. Supplemental examinations required by Standard Review Plan SRP 6.6,Section I-7, II-7,and ASB 3-1 are also incorporated where applicable.
Details of how all requirements are factored into the Class 2 Program are delineated below:
2.2.1 ASME Code Exemptions Employed Code Case N-408- Alternative Rules for Examination of Class 2 Piping Section XI, Division 1.
The following alternative rules are used for determining components subject to examination and for establishing examination requirements for Class 2 piping under Section XI, Division l.
a) The following components (or parts of components) of RHR,ECC,and CHR systems (or portions of systems) are exempt from the volumetric and surface examination requirements of IWC-2500:
- 1) vessels, piping, pumps, valves, and other components NPS 4 inch and and smaller in all systems except in high pressure safety injection systems of pressurize'd water reactor plants; 2), vessels, piping, pumps, valves, and other components NPS 1 1/2 inch and smaller in high pressure safety injection systems of press-urized water reactor plants;
- 3) component connections NPS 4 inch and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except in high pressure safety injection systems of pressurized water reactor plants;
- 4) component connections NPS 1 1/2 inch and smaller (including nozzles,socket fittings, and other connections)in vessels,,piping, pumps, valves,and other components of any size in high pressure safety injection systems of pressurized water reactor plants;
- 5) vessels, piping, pumps, valves, other components, and component connections of any size in statica/ly pressurized, passive,(i.e.
no pumps) safety injection systems of pressurized water reactor plants')
piping and other components of any size beyond the last shutoff valve in open ended portions of systems t)at do not contain water during normal plant operating conditions.
2.2.1
~ ~ ASME Code Exemptions Employed (cont.)
b) The following components (or parts of components)other than RHR,ECC, and CHR systems (or portions of systems) are exempt from the volume-tric and surface examination requirements of IWC-2500:
- 1) vessels, piping, pumps, valves, and other components NPS 4 inch and smaller;
- 2) component connections NPS 4 inch and smaller (including nozzles, socket fittings, and other connections ) in vessels, piping, pumps, valves,and other components of any size;
- 3) vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 degrees Fahrenheit;
- 4) piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
c) For welds in austenitic stainless steel or high alloy piping, the requirements of Table 1, Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping, (located in Code Case N-408) shall be used as an alternative to the requirements of Table IWC-2500-1.
d) For welds in carbon or low alloy steel piping, the requirements of Table 2, Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping, (located in Code Case N-408) shall be used as an alternative to the requirements of Table IWC-2500-1.
safety injection systems of 1
Note2: Statically pressurized, passive pressurized water reactor plants are typically called by such names as accumulator tank and associated system, safety injection tank and associated system, or core flooding tank and associated system.
Note3: Normal plant operating conditions include reactor startup, operation at power, hot standby, and reactor cooldown to cold shut down conditions, but do not include test conditions.
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Component/Piping Examination Development Steam Generators (Secondary Side)
All required volumetric examinations are conducted manually from the O.D. surface of Steam Generators to the extent required in Table IWC
-2500-1 of ASME Section XI.The examinations are distributed between the two generators. Specific referencing paragraphs are as follows; Code Category C-A Note 3: In the case of multiple vessels of similar design, size,and service(such as steam generators and heat exchangers) the required examinations may be limited to one vessel or distributed among the vessels.
For both generators, the steam and feedwater nozzle welds and inner radii areas are examined due to the selection criteria utilized for both the Feedwater and Main steam piping systems.
Secondary manway bolting receives a visual (VT-1) examination, in place.
Shutdown Cooling Heat, Exchangers All volumetric examinations are conducted manually from the O.D.
surface of the heat exchanger. Areas examined include the two girth welds on the primary water box and the inlet and outlet nozzles on each heat exchanger. The examinations are equally distributed between the two vessels.
Main Steam and Feedwater Piping All volumetric and surface examinations on these piping systems are performed from the O.D. surface.
Piping welds are selected for examination based upon the requirements of Code Case N-408, Table 2, Code Category C-F-2. In addition, high stress welds that exceed the criteria of Note 1a, in the 1983 Edition of ASME Section XI, Category C-F shall be examined.
IWC-2500-1, Category C-F, Note 1(a): all welds at locations where the stresses under the loadings resulting from normal and upset plant conditions, as calculated by the sum of Eqs.(9) and (10) in NC-3652, exceed 0.8(1.2Sh + SA)
Welds in those portions of systems addressed in SRP 6.6 paragraph I, and SRP 3.6.1, BTP ASB 3-1 are addressed as follows; Pipe to pipe welds and longitudinal seams are required to be examined, additionally, the Code Category (C-F) boundary is extended past the code class boundary (MSIV) to the first restraint providing at least two degrees of restraint to piping thermal expansion. Welds and supports are specifically identified in the Main Steam and Feedwater examination tables.
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Austenitic Piping Systems All volumetric and surface examinations on these piping systems are performed from the O.D. surface. Piping welds are selected for examination based upon the requirements of Code Case N-408, Table 1, Code Category C-F-1.
2.2.3 Component Supports Class 2 Integral attachment welds are selected and examined per the require-ments of Table IWC-2500-1, Category C-C. Class 2 component supports subject to examination are selected in accordance with Subarticle IWF-2510 'hose supports selected receive a visual examination (VT-3)
.to determine their general mechanical and structural condition.
An additional visual examination (VT-4) is performed on spring type supports and mechanical/hydraulic snubbers to determine conditions relating to their operability to the extent of confirming, their functional adequacy, verification of settings or freedom of motion, as applicable.
The functional testing requirements, testing method, and extent and frequency of testing for mechanical and hydraulic snubbers shall be governed by the Plant Technical Specifications ~
2.2.4 System Pressure Tests Class 2 The pressure retaining components within the Class 2 system boundar-ies are subjected to System Pressure Tests in accordance with IWC 5210 and visually examined (VT-2) per IWA 5240. The tests are conducted as follows:
a) System Functional Test, IWA 5211 (b), For those systems or portions of systems,not required to operate during normal reactor operation, but for which periodic system or component are performed, as required by the Plant Technical Specific-functional'ests ations and / or the Pump and Valve (IST) program, a VT-2 examination is performed at least once each period (except in the period when a hydrostatic test is performed) during the system or component functional test. The boundary subject to pressuriza-tion during a System Functional Test includes only those pressure retaining components within the system boundary pressurized under the* test mode required during the performance of the periodic system (or component,) functional test. Nominal operating pressure of the system functional test is acceptable as the system test pressure.
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t 2.2.4 System Pressure Tests Class 2 (cont.)
b) A System Hydrostatic Test, IWA 5211 (d) is performed on Class 2 systems at least once during each Inspection Interval. The bound-ary subject to test pressurization during a System Hydrostatic Test is defined as the Class 2 system boundary and includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve(including a safety or relief valve), or valve capable of automatic closure when the safety function is required. The VT-2 examination performed during a System Hydrostatic Test is used to satisfy the system functional test requirements of a) above for the period in which it conducted.
2.2 ' Instrumented Inspection Technique (IIT)
FP&L will continue to utilize the Instrumented Inspection Technique for only those systems(or portions of systems) which have been eval-uated in accordance with H.A.F.A. International Topical Report: HAFA 135(P),Section IV. The IIT, where employed, takes the place, of; both the system functional test and the s'stem hydrostatic test and is employed each period, as applicable.
Reference Documents:
FP&L Letter: L-85-379, Dated Oct.4,1985(Request for approval to use Instrumented Inspection Technique)
NRC Letter, Dated Nov.8,1985 (TAC ¹59917) 2.2.6 Repair and Replacement Class 2 Repair to Class 2 components, piping,,and supports is done in accord-ance with the requirements of IWA-4000 and IWC-4000,ASME Section XI.
Replacement of Class 2 components, piping, and supports is done in accordance with the requirements of IWA-7000 and IWC-7000 of ASME Section XI.
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2.3 Class 3 Systems
'The Class 3 System Boundaries are developed based upon the require-ments of Regulatory Guide 1.26 and ASME Section XI.
2,.3.1 ASME Code Exemptions Employed Integral attachments of supports and restraints, to componentsExamina- that are 4 inch NPS and smaller, within the system boundaries of tion Categories D-A, D-B, and D-C of Table IWD-2500-1, shall be exempt from the visual examination (VT-3), except for the Auxiliary Feedwater Systems.
Integral attachments of supports and restraints, to components exceeding 4 inch NPS may be exempted provided:
a) the components are located in systems (or portions of systems) whose'unction is not required in support of reactor residual "core heat removal, containment heat removal, and emergency cooling; b) the components operate at a pressure of 275 psig or less and at a temperature of 200 degrees Fahrenheit(93 degrees Centigrade) or less ~
2.3.2 Component Supports Class 3 Class 3 piping and component support integral attachment welds, except those exempted by IWD-1220.1 and IWD-1220.2 are visually examined (VT-3).Other Class 3 piping and component supports are visually examined to determine their general mechanical and is structural integrity. An additional visual examination (VT-4) performed on spring type supports and mechanical/hydraulic snubbers to determine conditions relating to their operability to the extent of confirming, their functional adequacy, verfication of settings or freedom of motion, as applicable. The Class 3 supports subject. to examination have been selected in accordance with Subarticle IWF-2510 of ASME Section XI.
The functional testing requirements, testing method, and extent and frequency of testing for mechanical and hydraulic snubbers shall be governed by the Plant Technical Specifications.
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2.3
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~ System Pressure Test Class 3 The pressure retaining components within the boundary of each system specified for Categories D-A, D-B, and D-C are pressure tested and visually examined (VT-2) for leakage during the following tests:
a) For systems required to operate during normal plant operation, a System Inservice Test, IWA-5211(c) is conducted at least once each period while the system is in operation and at operating pressure. The boundary subject to test pressurization, during a System Inservice Test, extends to those 'ressure retaining components under operating pressure during normal system oper-ations; OR b) System Functional Test, IWA-5211(b), For those systems, or portions of systems, not required to operate during normal plant operation, a VT-2 examination is performed during a periodic system or component functional test, as required by the Plant Technical Specifications and/or the Pump and Valve (IST) Program.
The boundary subject to test pressurization during a System Functional Test includes only those pressure retaining components within the system boundary pressurized under the test mode required during the performance of the periodic system (or Component ) functional test. The nominal operating pressure of the system functional test is acceptable as the system test pressure.
AND c) System Hydrostatic Test,IWA-5211(d), is performed on Class 3 sys-tems once in each interval. The boundary subject to test pressurization extends up to and includes the first normally closed valve, or valve capable of automatic closure, as required to perform the safety-related system function. The system pressure requirements are defined in Subarticle IWD-5223 of ASME Section XI.
2.3.4 Instrumented Inspection Technique (IIT)
FP&L will continue to utilize the Instrumented Inspection Technique for only those systems(or portions of systems) which have been eval-uated in accordance with H.A.F.A. International Topical Report: HAFA 135(P),Section IV. The IIT, where employed, takes the, place of the system functional test and system hydrostatic test and is employcd-each period, if applicable.
Reference Documents:
FP&L Lelber: L-85-379, Dated Oct.4,1985(Request for approval to use Instrumented Inspection Technique)
NRC Letter, Dated Nov.8,1985 (TAC ¹59917) 23
2.3.5 Repair
~ ~ and Replacement Class 3 Repair to Class 3 components, piping,and supports is done in accord-ance with the requirements of IWA-4000 and IWD-4000 of ASME Section XI.
Replacement of Class 1 components, piping,and supports shall be in accordance with the requirements of IWA-7000 and IWD-7000 of ASME Section XI.
2.4 Flaw Indications Class 1 Pursuant to the ASME Section XI, subarticle IWB-2420,in the case of welds where examinations reveal the presence of flaw indications that exceed the acceptance standards and the component is evaluated as acceptable for service, the areas containing the flaw indications will be scheduled for reexamination during the next three(3)inspect-ion periods of Inspection Plan B (IWB-2410). Provided the,-.', flaw indications remain essentially the unchanged for three, successive inspection periods, the component examination schededule will revert to the original schedule of successive inspections.
Class 2 Pursuant to the ASME Section XI, subarticle IWC-2420,in the case of welds where examinations reveal the presence of'law indications that exceed the acceptance standards and the component is evaluated as acceptable for service, the areas containing the flaw indications will be scheduled for reexamination during the next inspection period of Inspection Plan B per IWC-2412. Provided the flaw indications remain essentially the unchanged for the next inspection period, the component examination schededule will revert to the original schedule of successive inspections.
24
2.5 Class MC Components
'0 CFR 50.55a presently incorporates only those portions of Section the ISI requirements for Class 1, 2,and 3 components XI that address and their supports. The regulation does not currently address the ISI of containments. Since this proposed amendment is only intended to update current regulatory requirements to include the latest ASME Code edition and addenda, the requirements of Subsection IWE would not be imposed upon Commission licensees by this amendment.
Per the above statement, Subsection IWE of Section XI is exempted and therefore will not be addressed in this Program.
Reference:
Federal Register,Vol. 53, No.123 Dated June 26,1987.
I 25
During the First Ten Year inspection Interval there were cases where component configuration and / or interferences, prohibited 100%
coverage of the Code required volume or surfaces. In each case, where such limitations were encountered, the details are documented in a Relief Request. Since those same conditions will prevail during this Inservice Inspection Interval, those Relief Requests are included that will utilized in the Second ISI Interval.
In cases where parts of the required examination areas cannot be effectively be examined, because of a combination of component design or current inspection technique limitations, FP&L will continue to evaluate the development of new or improved examination techniques, with the intent of applying these techniques where a practical improvement in the examination can be achieved.
3.1 FORMAT Relief Requests are arranged in order by Code Category, followed by those of general nature where Code Category does not apply. They are numbered sequentially. Each Relief Request contains the following information:
A) COMPONENT CLASSIFICATION: describes the Code Class, component or system description,and Code Category description (if applicable)
B) EXAMINATION/TESTING REQUIREMENTS: lists Code Category, Code Item Number, (if applicable)and describes the examination/test require-ments.
C) RELIEF REQUESTED: describes specific areas in which relief is needed,(i,e. weld i.d.and description)and gives brief descrip-tion for the reason why relief is .being requested.
D) BASIS FOR RELIEF: describes examination(s) conducted and/or eval-uated to support the reason relief is being requested.
E) ALTERNATE EXAMINATIONS: proposes alternative examinations to replace, supplement, or support the examinations/tests and evaluations required or already conducted.
F) IMPLEMENTATION SCHEDULE: proposed time frame/schedule G) ATTACHMENTS: lists drawings, tables,etc,.
3.2 Relief Request Tables Where applicable, supportive documentation in the form of Tables and Figures specifically identify each item affected by the Relief Request and describes the limitations encountered and the extent, of examination achieved during the First Ten Year ISI Interval which is expected to remain the same for the Second Ten Year ISI Interval.
26
Relief Requests known to be applicable to the ISI examinations are listed below. Additional Relief Requests, as deemed necessary, will be submitted pursuant to the requirements of 10 CFR 50.55a(g)(5).
'RR ¹ Description Code Code RR-1 Pressure Retaining Welds B-,A B1.10 in ReactorVessel B1.11 B1.12 B-A B1.20 B1 21
~
B1.22 RR-2 Reactor Pressure Vessel B-A B1.22 Closure Head B1.40 Pressure Retaining Welds B-B B2.32 in Vessels, other than B2.40 Reactor Vessel Full Penetration Welds B-D B3.130 of Nozzles in Vessels B3.140 Program B,Steam Generator Full Penetration Welds B-D B3.90 of Nozzles in Vessels B-D B3.100 Reactor Pressure Vessel RR-5 Full Penetration Welds B-D B3.110 of Nozzles in Vessels B-D B3.120 Program B Pressurizer Pressure Retaining Welds B-J B9.11 in Piping B9.31 Pressure Retaining Welds B-L-1 B12.10 in Pump Casing/Pump Casing B-L-2 B12.20 RR-8 Valve Bodies,>4 in. NPS B-M-2 B12.50 RR-9 Open Ended Systems C-H RR-10 IWF-5000 Test Requirements RR-11 Ultrasonic Calibration Blocks APPENDIX III RR-12 Class 1 &, 2 Welds 27
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 1 A. COMPONENT CLASSIFICATIONc Cl ass Reactor Pressure Vessel Pressure Retaining Welds in Reactor Vessel B. EXAMINATION REQUIREMENTS:
EXAM CAT. ITEM NO. EXAMINATION REQUIREMENTS Bi. 10 Volumetri c e:<aminati on to include Bi. 11 essenti al l y 100/ of the weld Bi. 1= 'ength of one beltline region weld.
These examinations shall be performed during each inspection interval, and may be performed at or near the end of the inspection interval .
- 81. 20 Volumetric e:<amination to include Bi 1
~
~
essentially 100/ of the weld length of one acces ible weld.
These examinations shal l be performed during each inspection interval, and may be performed at.
or near the end of'he inspection interval f or bottom head welds only.
B-A 91. Z0 Volumetric examination to include essentially 100/ of the weld length. This e:<amination shal l be perf ormed during each inspection interval, and may be deferred the end of the interval providing till that at least 50/ of the shell to flange weld is e:<amined by the end of the first inspection period and the 'emainder e:<amined by the end of the third period in conjunction with the nozzle examination of e;<amination category B-D (Program B).
ST. LUCIE NUCLEAR POWER PLANT UNIT i SECOND 1NSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST NO.: i C. RELIEF REQUESTED!
Relief is requested from the ABME Boiler and Pressure Vessel Code required volume due to the f ol lowing:
(i) Configuration and permanent attachments prohibit i00%
ultrasonic e<amination coverage of the required e:<amination volume.
(.) Interference from search unit wedge-to-component near surface interface noise, and (3) Component geometric interference with scanning equipment and/or geometric shadowing of examination areas.
Relief is requested for the following welds:
WELD I DENT1F I CAT I ON WELD DESCRIPTION 7-.03 UPPER SHELL -TO- FLANGE WELD 204-0. LOWER HEAD DOLLAR PLATE 04-03A LOWER HEAD MERIDIONAL WELDB 204-03B
.04-03C 04-03D 204-03E 204-03F 10-203 LOWER SHELL -TO- LOWER HEAD WELD 9-203 MIDDLE SHELL -TO-LOWER SHELL WELD 3-203A LOWER SHELL VERTICAL WELDS 3-203B 3-203C D. BASIS FOR RELIEF'.
i0 CFR 50.55a (g) (4) recognizes that throughout the service life of a nuclear power facility, components which are classif ied as ABME Code Class i shall meet the requirements, e;<cept design and access provisions requirements, set forth in Section XI, to the extent pr actical within the limitations of design, geometry and materials of construction of the components.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO.: 1
- 2. Configuration and permanent attachments prohibit 100/-
ultrasonic e<amination coverage of the required code vol ume.
Additional ultrasonic techniques are employed, where practical, to achieve the code, required volume.
Described below, by weld description, denotes the limitations encountered and those additional techniques employed to compensate for those areas where CRV could not be effectively covered.
- a. RPV LOWER HEAD WELDS The only e,<amination coverage limitations e;<perienced during e.<amination of the lower head dollar plate weld, no. 204-02, were due to near
'surface interface noise. Those volumes shadowed by the interface noise were completely e:<amined with the 45-degree full vee path scans. See dwg. no. 001-LIM and 001-PSLRR for location of weld.
WELD NO. EXAM ANGLE / OF VOLUME NOT FIGURE NO.
EFFECTIVELY EXAMINED
~ 04-0. 0 DEGREE 50. 0 001-LIM 45 DEGREE 0 N/A 60 DEGREE 16. 'P'P 001-LIM COMBINED COVERAGE 0
+COMBINED COVERAGE INDICATES THE PERCENT OF CODE REQUIRED VOLUME NOT EFFECTIVELY COVERED BY AT LEAST ONE CALIBRATED BEAM.
TABLE NO. 1
- b. LOWER HEAD MERIDIONAL WELDS Access for evaminations of the Lower Head Meridional Weld, Nos. 204-03A through F, was limited due to interference from the core support lugs and flow skirt Dr awing No. 001-LIM is a r ol lout plan view of the scan surface limitations for the meridional welds. These areas of inaccessibility resulted in volumetric coverage limitations quantified in Table 2 of thi= Relief.
ST. LUCIE NUCLEAR POWER PLANT UNIT i SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.:
WELD NQ. EXAM ANGLE r. QF VOLUME NOT FIGURE NQ.
EFFECTIVELY EXAMINED 204-03A 0 DEGREE 74. 82 001-LIM 45 DEGREE 63. 92 60 DEGREE 62, 24 45 DEGREE T 57. 13 60 DEGREE T 49. 56
+COMBINED COVERAGE 0 204-03B 0 DEGREE 79. 99 001" LIM 45 DEGREE 71. 34 60 DEGREE 70. 0 45 DEGREE T 63 94
~
60 DEGREE T 58.36
+COMBINED COVERAGE 204-03C . 0 DEGREE 74. 82 001-LIM 45 DEGREE 71. 75 60 DEGREE 45 DEGREE T 57. 13 60 DEGREE T 49. 56
+COMB I NED COVERAGE 0 204-03D 0 DEGREE 79. 99 001-LIM 45 DEGREE 71. 34 60 DEGREE 70 0
~
45 DEGREE T 63. 94 60 DEGREE T 58 36
~
+COMBINED COVERAGE 0 204-03E 0 DEGREE 74. 82 001-L IM 45 DEGREE 71. 75 60 DEGREE 45 DEGREE T 60 DESF(EE T 49. 56
+COMBINED COVERAGE 0 204-03F 0 DEGREE 79. 9'9 001-LIM 45 DEGREE 71. 84 60 DEGREE 70. 0 45 DEGREE T 63. 94 60 DEGREE T 58 36
~
+COMBINED COVERAGE 0 TABLE NQ.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 1
'The mechani "ed examinatian af the Lower Shell-ta-Lawer Head We 1 d, Na.10-203, was limited due to inter ference fram the care suppart. lugs and anti-rotation lugs. The near surface volume was effectively e,<amined with 45-degree scans.
full vee path Drawing Na. 001-LIM shows the inaccessible scan surfaces fram the vessel inside surface.
lists the coverage limitations for each Table beam campanent.
WELD NO. / OF VQLUME NQT FIGURE NO ~
EFFECTIVELY EXAMINED 10-203 0 DEGREE Z6. 61 001-LIM 45 DEGREE 17. 71 60 DEGREE 23. 46 45 DEGREE 2 45
~
60 DEGREE 8.73
+COMBINED COVERAGE 0 TABLE NQ.
- d. MIDDLE SHELL -TO- LQWER SHELL WELD E:<amination of the Middle Shell-ta-Lower Shell Weld, Na. 9-203, was limited due to interference fram the.
surveillance specimens. The 70-degree and 45-degree full vee path scans effectively examined the near surface volume except in those areas where scanning was limited due to the surveillance specimens.
Drawing No. 001-LIM is a rollout view showing Weld No. 9-203 and depicting areas whar e scans cauld nat be perf ormed. Drawi ng No. 001-SKT, f i gure no. 2 is a sectional view shawing the 45-degree and 60-degree transverse e:<amination limitations. Figure no. 4, same drawing shaws the 70-degree transverse e<amination beam profiles in the area of the specimen tubes.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 1 WELD NO. EXAM ANGLE / OF VOLUME NOT FlBURE NO.
EFFECTIVELY EXAMINED 9-.03 0 DEGREE 15. 8 001-LIM 45 DEGREE 60 DEGREE 29. 17 45 DEGREE T .30 001-SEi T 60 DEGREE T 14 3~ FIB ~
70 DEGREE RL 2. 41 001-SKT 70 DEGREE RLT ~ 21 FIB. 4
+COMBINED COVERAGE 0 TABLE NO. 4
- e. UPPER SHELL-TO-FLANGE WELD The Upper Shell-to-Flange Weld, No. 7-203, was e:<amined from the shell side. The 0-degree and 60-degree e:<aminations were limited due to near surface interface noise; however, this volume was effectively e<amined using the 45-degree full vee path beam. Manual examinations utilizing beams directed nearly perpendicular to the weld plane from the flange seal surface will compensate for the straight beam and angle beam examination limitations on the flange side of the weld. Due to the flange configuration, no transverse evamination scans were performed from the flange side of the weld. Drawing No. 001-SKT, figure no. 7 provides a sertion view of the l imi tat i ons to Wel d No. 7-203.
WELD NO. EXAM ANGLE / OF VOLUME NOT FIBUR NO.
EFFECTIVELY EXAMINED 7-203 0 DEGREE 80. 83 001-Sk~T 45 DEGREE 35. 0 FIG. 7 60 DEGREE 1. 32 45 DEGREE T 58. 11 60 DEGREE T 58. 11
+COMBINED COVERAGE 0 TABLE NO. 5
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 1 RPV LONGITUDINAL SHELL WELDS The e,<aminations of the Lower Shell Verti<<al Welds, Nos. 3-20 4, B, and'C, were limited very slightly due to anti-rotation lug and flow skir t interf erence. The near surface volume was effectively e:<amined with the 70-degree and 45-degree full vee path scans. Drawing No. 001-PSI RR show~ the location of those limitations due to the lug and flow skirt interference. The e;<amination of weld no. 3-2038 was also limited due to interference of a surveillance capsule. This volume was effectively e:<amined by the 45-degree full vee path beam. Drawing No. 001-LIM shows the limitation due to the surveillance capsule interference.
WELD NQ. EXAM ANGLE / QF VOLUME NOT FIGUR NQ.
EFFECTIVELY EXAMINED 2-203A 0 DEGREE 38. 56 001- LIM 45 DEGREE 5.0 60 DEGREE 28. 56 45 DEGREE T 0 60 DEGREE T 0 70 DEGREE RL 0 70 DEGREE RLT 0
+COMBINED COVERAGE 0 0 DEGREE 38. 56 001-LIM 45 DEGREE 5.0 60 DEGREE 28. 56 45 DEGREE T 60 DEGREE T 0 70 DEGREE RL 0 70 DEGREE RLT 0
+COMBINED COVERAGE 0 03C 0 DEGREE 27. 77 001-LIM 45 DEGREE 0 60 DESRFE 19. 9 45 DEGREE T 60 DEGREE T 0 70 DEGREE RL 70 DEGREE RLT 0
~COMBINED COVERAGE 0 TABLE NO. 6
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 1
- 4. Limitations to coverage of the ABME Code Required Examination Volumes were due to component configuration and interference by vessel attachments. These limitations ar e identified in figures and tables provided in this request for relief. The limitations were minimized to the maximum extent possible. ln all cases where limitations were experienced, the e,'<aminations were supplemented by additional scans using alternate sound beam components to enhance over al l coverage.
- 5. The extent of e:<amination volume achieved ultrasonically and the alternate scans performed coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
E. ALTERNATE EXAMINATIONSt
- 1) Conduct Mechani ed Ultrasonic E<aminations to the extent practical within the limitations.
~
) Perform as required supplemental beam angles to ma:<imize the percentage of code required volume achieved.
- 2) Periodic System Leakage tests per Table IWB-2500-1
- 4) Inservice Hydrostatic test per Table IWB-=500-1 F. IMPLEMENTATION SCHEDULEI SECOND INSERVICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 19'78 B. ATTACHMENTS:
001-PBLRR BT. LUCIE RPV GENERAL ARRANGEMENT DRAWING 001-LIM RP V COMPOS I TE SCAN L' M I TATI ONS 001-BKT ULTRASONIC SCAN LIMITATIONS
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.s 2 A. CONPONENT CLASSIFICATION:
CLASS 1 REACTOR PF(EBBURE VESSEL CLOSURE HEAD PRESSURE RETAININB WELDS IN REACTOR VESSEL CLOSURE HEAD TO FLANGE WELD MERIDIONAL WELDS B. EXANINATION REQUIRENENTB)
EXAN. CAT. ITEN NO. EXANINATION REQUIRENENTS 8-A 81. 22 Volumetr i c evaminat i on to include essentially 100/ of the length of one accessible e<amination shal l weld'hi be perf ormed s
during each inspection interval.
Bi. 40 Volumetric and surf ace e;<amination to include essentially 100% of the weld length. This e:<amination shall be performed during each inspection intervale C. RELIEF REQUESTED!
Relief is requested from the ABNE Boiler and Pressure Vessel Code required volume due to the following:
- 1. Conf iguration and permanent attachments prohibit 100/
Ultrasonic e:<amination of the required volume.
2~ Configuration and permanent attachments prohibit 100/
surface e;<amination of the code required surface.
ST. LUCIE NUCLEAR PQWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST NO.: 2
- 3. Relief is requested from the following welds:
WELD IDENTIFICATION WELD DESCRIPTION 209-02 CLOSURE HEAD TO FLANGE WELD 209-03A MERIDIONAL WELD 209-038 MERIDIONAL WELD 209-03C MERIDIONAL WELD 209-03D MERIDIONAL WELD MERIDIONAL WELD 209-03F MERIDIONAL WELD D. BASIS FQR RELIEF'.
10 CFR 50.55a (g) (4) recognizes that throughout the service life of a nuclear power facility, components which are classif ied as ASME Class 1 shall meet the requir ements, except design and access provisions requirements, set forth in section XI, to the extent practical within the limitations of design, geometry and material of construction of the component.
2 ~ Configuration and permanent, attachments prohibit 100/
ultrasonic and surface examination of the code required volume and surface.
Described below, by weld description, donotes the limitations encountered and those additional techniques employed to compensate for those areas where CRV could not be effectively covered.
- a. MER ID IONAL WELDB All six (6) intersecting meridional welds between the closure head to flange weld is limited to 15 1/2 inches of weld that can be examined by the ultrasonic examination method due to the closure head insulation ring. See drawing no. 001-CH-1 for insulation ring limitations.
ST. LUG IE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO.t 2
- b. CLOSURE HEAD TO FLANGE WELD Configuration of the closure head limits the examination of the weld to a one side e<amination.
Drawing no. 001-CH provides the limitations and the e:<tent of code required volume that cannot be examined.
- 4. The e<tent of e<amination volume achieved ultrasonically and the surface area achieved and the system pressure tests provide assurance of an acceptable level of quality and saf ety.
E~ ALTERNATE EXAMINATIONS:
- 1) Conduct Volumetric Ultrasonic examinations to the extent practical within the limitations.
- 2) Conduct the Surface e:<amination to the extent practical within the limitations.
- 3) Periodic System Leal<age tests per Table IWB-2500-1
- 4) Inservice Hydrostatic Tests per Table IWB-2500-1 F. IMPLEMENTATION SCHEDULEi SECOND INSERV ICE INSPECTION 1NTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1988
- 8. ATTACHMENTS>
001-CH RPV CLOSURE HEAD LIMITATIONS 001-CH-1 RPV CLOSURE HEAD MERIDIONAL WELD LIMITATIONS
l r '"n" '(
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 5 SECOND INSPECTION 1NTERVAL INSERVICE INSPECTION RELlEF REQUEST NO.:
Relief is requested for the following welds:
CONPONENT IDENTIFICATION WELD DESCRIPTION TUBESHEET TO HEAD WELD OUTLET AND INLET NOZZLE TO VESSEL WELDS OUTLET AND 1NLET NOZZLE INNER RADIUS SECTION HER I D IONAL HEAD WELDS S/G-B TUBESHEET TO HEAD WELD OUTLET AND INLET NOZZLE TO VESSEL WELD OUTLET AND 1NLET NOZZLE INNER RADIUS SECTION MERI D I ONAL HEAD WELDS D. BASIS FOR RELIEF:
- l. iQ CFR 50.55 a (g) (4) recogni"es that throughout the service life of a nuclear power facility, components which are classified as ASNE Code Class 1 shall meet the requirements, except design and access provisions requirements, set forth in Section XI, to the evtent practical within the limit ations of design, geometry and materials of construction of the components.
Configuration and permanent attachments prohibit 100/
ultrasonic e:<amination coverage of the required code volume.
- 3. Additional ultrasonic techniques are employed, where practical, to achieve the code required volume.
Described below, by weld description, denotes the limitations encountered and those additional techniques employed to compensate for those areas where CRV could not be effectively covered.
ST. LUCIE NUCLEAR POWER PI ANT UNIT NO. 5 SECOND INSPECTION INTERVAL INSERV I CE INSPECTION RELlEF REQUEST NO.:
- a. TUBE SHEET TO HEAD WELD The TUBEBHEET TO HEAD WELD is obstructed from code required volume f or the f ol lowing reasons:
- i. Primary manways obstruct a 30 inch area, located appro;<imately 14" from the center line of the tube sheet weld on the head side. The primary manways are located at the 0 and 90 degree location. Bee drawing no. 001-8$ for illustration of limitations.
- 2. Four 1 inch lines located at appro:<imately the 31", 49", 39'nd 40 foot location, clockwise from datum O. An area, 7 inches from the weld edge and 2 inches cannot be e:<amined. See drawing no. 001-BS for illustration of limitations.
An area 4 foot, 5 inches, located 14 inches is obstructed due to the Hot leg from'he weld edge Nozzle. Bee drawing no. 001-BB for illustration of scan limitations.
- b. NOZZLE TO SHELL AND INNER RADIUS SECTION Scan limitations are defined as follows:
- 1. An area 23 inches long by 14" in width is limited
.by the primary manways. See drawing no. 001-SB-i.
- 2. An area 15 inches, long by 12 foot in width is limited by the steam generator si ay base for the cold legs and an area 18 inches long on the hot leg. See drawing no. 001-88-1 for limitations.
ST. LUCIE NUCLEAR POWER PLANT UNIT NO ~ 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO. c A. COMPONENT CLASSIFICATION!
Pressure Retaining Nelds in Vessels other than Reactor Vessel Full Penetration Nelds of No'les in Vessels Program 8 Steam Generators Primary Side 8 ~ EXAMINATION REQUIREMENTS:
EXAM CAT.. ITEM NO. EXAMINATION REQUIREMENTS 8 "8 82. 40 Volumetric e;<aminati on to include essential ly 100/ of the weld length of one vessel amoung a group of vessels perf or ming a similar f unction.
Thi s e:<aminat i ons shal l be performed during each inspection interval.
8-D 83 130 Volumetric e;<amination to include 82.140 essentially 100/ of the weld length.
These e:<aminations shall be performed during each, inspection interval.
C. RELIEF REQUESTED."
Relief is requested from the ABME 8oiler and Pressure Vessel Code required volume due to the following:
(1) Configuration and permanent attachments 'prohibit 100/
ultrasonic e<amination coverage of the required e:<amination volume.
BT. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELlEF REQUEST NO.:
'. MERIDIONAL HEAD WELDS The Wive (5) meridional head welds are obstructed by the primary manways and the nozzles. See drawing no. 001-SG-2 %or limitations. The welds a%%ected are as Vol l ows".
WELD NO. LOCATION 111-A LOCATED AT 66 DEGREES 111-B LOCATED AT 138 DEGREES 111-C LOCATED AT .10 DEGREES 111-D LOCATED AT 28 DEGREES 111-E LQCATED AT 354 DEGREES
- 4. Limitations to coverage o$ the ABME Code Required E<amination Volumes were due to component configuration and inter-Ference by vessel attachments. These limitations are identified in figures and tables provided in this request for relic%. The limitations were minimized to the ma<imum e<tent possible. In all cases where limitations were e<perienced, the e;<aminations were supplemented by additional scans using alternate sound beam components to enhance overall coverage.
- 5. The e<tent of e<amination volume arhieved ultrasonically and the alternate scans performed coupled with the system pressure tests provide assurance of an acceptable level o$ quality and safety.
BT. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INBERVICE INSPECTION RELIEF REQUEST NQ.:
E. ALTERNATE EXAMINATIONS)
- 1) Conduct VOLUMETRIC Ultrasonic Examinations to the extent practical within the limitations.
~
) Perform as required supplemental beam angles to ma;<imize the percentage o$ code required volume achieved.
- 3) Periodic System Leakage tests per Table IWB-2500-1
- 4) Inservice Hydrostatic test per Table IWB-2500-1 F. IMPLEMENTATION SCHEDULEt SECOND INSERV ICE INSPECTION INTERVAL 11 FEauRARV 1eBB TO 11 FEeuRARV 1eee G. ATTACHMENTS:
001-SG STEAM GENERATOR TUBE SHEET TQ SHELL LIMITATION 001-SG-1 STEAM GFNERATOR NOZZLE SCAN LIMITATIONS OO1-88-2 STEAM GENERATOR MERIDIONAL WELD LIMITATIONS
ST. LUCIE NUCLEAR POWER PLANT UNIT SECOND INSPECTION INTERVAL INBERVICE INSPECTION RELIEF REQUEST NO. s A. COMPONENT CLASSIFICATIONS Class 1 Reactor Pressure Vessel Full Penetration Welds of Nozzles in Vessels Nozzle to Vessel Welds Nozzle Inside Radius Section B. EXAMINATION REQUIREMENTSI EXAM CAT. ITEM NO. EXAMINATION REQUIREMENTS B-D B3. 90 Vol umetri c examinati on to include al 1 nozz les wi th f ul 1 penetration welds to vessel shel 1.
These examinations shall be perf ormed during each inspection interval, and may be performed at.
or near the end of the inspection interval.
B-D B3. 100 Volumetric examination to include all nozzle inner radius sections.
These examinations shall be performed during each inspection interval, and may be performed at or near the end of the inspection interval.
C. RELIEF REQUESTEDI Relief is requested from the ASME Boiler and Pressure Vessel Code required volume due to the following:
(1) Configuration of nozzle integral extension prohibit 100/
ultrasonic examination coverage of the required ex ami nat i on vol ume.
(2) Interference from search unit wedge-to-component near surface interface noise.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. c 4 Relief is requested for the following welds:
WELD IDENTIFICATION WELD DESCRIPTION 205-05 OUTLET NOZZLE 205-10 OUTLET NOZZLE 205-01A INLET NOZZLE 205-018 INLET NOZZLE 205-09A INLET NOZZLE 205-09B INLET NOZZLE D. BASIS FOR RELIEF'.
10 CFR 50.55a (g) (4) recognizes that throughout the service life of a nuclear power facility, components which are classif ied as ASME Code Class 1 shall meet the requirements, except design and access provisions requirements, set forth in Section XI, to the extent practical within the limitations of design, geometry and materials of construction of the components.
- 2. Configuration and design of the nozzles prohibit 100%
ultrasonic examination coverage of the required code volume.
Additional ultrasonic techniques are employed, where practical, to achieve the code required volume.
Described below, by weld description, denotes the limitations encountered and those additional techniques employed to compensate for those areas where CRV could not. be effectively covered.
ST. LUCIE NUCLEAR POWER PLANT UNIT SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. I 4
- a. NOZZLE -TO- SHELL WELD The inlet and outlet Nozzle-to-Shel l Welds were examined f rom the vessel shell and -f rom the nozzle bore. The nozzle bore e<aminations were limited due to near surface interface noise; however, surface wave examinations were perf ormed on nozzle inner radius sections and shear wave beams directed from the shell supplemented no zle bore inside surf ace coverage. The shell side transverse examinations of the outlet no zles were limited due to interference from the nozzle integral e;<tensions. Transverse scans from the nozzle bore on the integral e:<tensions supplemented coverage of this volume.
Limitations to the inlet nozzle examinations and limitations to the outlet nozzle examinations are shown on drawing 001-PSLNOZ.
INLET NOZZLE WELD NO. EXAM ANGLE / OF VOLUME NOT FIGUR NO.
EFFECTIVELY EXAMINED INLET NOZZLE 0 DEGREE 20. 0 001-PSLNOZ (SHELL SIDE) 45 DEGREE 20. 0 60 DEGREE 1.0 45 DEGREE T 0 N/A 60 DEGREE T 0 N/A (FROM BORE) 15 DEGREE 2.2 001-PSLNOZ 45 'DEGREE 1.6 TABLE NO. 1 OUTLET NOZZLE WELD NO. EXAM ANGLE / OF VOLUME NOT FIGUR NO.
EFFECTIVELY EXAMINED OUTLET NOZZLE 0 DEGREE 80.0 001-PSLNOZ (SHELL SIDE) 45 DEGREE 46. 1 60 DEGREE 28. ~~
45 DEGREE T 72. 0 60 DEGREE T 72. 0 (FROM BORE) 15 DEGREE 1.5 45 DEGREE 1 ~ 5 TABLE NO. 2
, ~
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION 1NTERVAL INSERVICE INSPECTION RELIEF REQUEST NQ.t 4
- 4. Limitations to coverage of the ASME Code Required E:<amination Volumes were due to component configuration and near surf ace interf ace noise. These limitations are identified in figures and tables provided in this request for relief. The limitations were minimi ed to the ma;<imum e:<tent possible. In all cases where limitations were e:<perienced, the e<aminations were supplemented by additional scans using alternate sound beam components to enhance overall coverage.
- 5. The extent of e:<amination volume achieved ultrasonically and the alternate scans performed coupled with the system pressure tests provide assurance of an acceptable level of qual i ty and safety.
E. ALTERNATE EXAMINATIONS')
Conduct Mechanized Ultrasonic Examinations to the extent practical within the limitations.
- 2) Perform as required supplemental beam angles to maximize the percentage of code required volume achieved.,
- 3) periodic System Leakage tests per Table IWB-2500-1
- 4) Inservice Hydrostatic test per Table IWB-2500-1 F. IMPLEMENTATION SCHEDULE j SECOND INSERV ICE INSPECT IQN INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1998 8.
ATTACHMENTS'01-PSLNOZ INLET AND OUTLET NQZZLE LIMITATIONS
ST. LUCIE NUCLEAR POWER PLANT UNIT NO ~ 1 SECOND INSPECTION INTERVAL INBERV1CE INSPECTION RELIEF REQUEST NO ~ : 5 A. COMPONENT CLASSIFICATION:
Class 1 Full Penetration Welds of Nozzles in Vessels Program 8 Pressurizer (Top and Bottom head)
B. EXAMINATION REQUIREMENTS:
EXAM CAT. ITEM NO. EXAMINATION REQUIREMENTS B-D 83. 110 Volumetric e<amination to include BZ. 120 essentially 100/ o$ the weld length.
These e:<aminations 'shal l performed during each inspection interval.
C. REI IEF REQUESTED'elic+
is requested -From the ABME Boiler and Pressure Vessel Code required volume due to the following:
(1) Configuration and permanent attachments prohibit 100/
ultrasonic e;<amination coverage oW the required examination volume.
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAt INSERV ICE INSPECTION RELIEF REQUEST NO. t 5 Relief is requested for the following welds:
COMPONENT IDENTIFICATION WELD DESCRIPTION SV-A SAFETY NOZZLE LOCATED AT 180 DEGREES RELIEF NOZZLE LOCATED AT 225 DEGREE SAFETY NOZZLE LOCATED AT 270 DEGREES SAFETY NOZZLE LOCATED AT 305 DEGREES SPRAY NOZZLE CENTER OF HEAD SURGE NOZZLE CENTER BOTTOM HEAD D. BASIS FOR RELIEF:
10 CFR 50.55 a <g) (4) recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1 shall meet the requirements, except design and access provisions requirements, set forth in Section XI, to the e:<tent practical within the limitations of design, geometry and materials of construction of the components.
- 2. Configuration and permanent attachments prohibit 100/
ultrasonic examination coverage of the required code volume.
Additional ultrasonic techniques are employed, where practical, to achieve the code required volume.
Described below, by weld description, denotes the limitations encountered and those- additional techniques employed to compensate for those areas where CRV could not be effectively covered.
ST. LUCIE NUCLEAR PQNER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NQ.: 5
- a. PRESSURIZER TQP HEAD NOZZLE WELDS The NOZZLE TO SHELL NELDS are obstructed from code required volume for the following reasons:
- 1. The required scan path for each of the nozz les is appro:<imately 12" for the 0 and 60 degree angle.
Because of the close proximity of the nozzle arangements to each other the 12 inches scan path cannot, be achieved. See drawing no. 001-PRZ f or obstructions.
- b. PRESSURIZER BQTTQN MEAD NOZZLE NELDS
- 1. Ten Pressurizer Heater Penetrations on the Bottom head limit the scan distance for the 60 degree angle only. See drawing 001-PRZ-1 For scan limitations.
4 ~ Limitations to coverage of the ASNE Code Required E;<amination Volumes were due to component configuration and interference by vessel attachments. These limitations are identified in figures and tables provided in this request for relief. The limitations were minimized to the ma<imum e<tent possible. In all cases where limitations were e<perienced, the examinations were supplemented by additional scans using alternate sound beam components to enhance overal l cover age.
- 5. The e<tent of examination volume achieved ultrasonically and the alternate scans performed coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
ST. LUCIE NUCLEAR POWER PLANT UNIT NO.
SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO. < 5 E. ALTERNATE EXAMINATIONS!
- 1) Conduct VOLUMETRIC Ultrasonic Examinations to the extent practical within the limitations.
- 2) Perform as required supplemental beam angles to maximize the percentage of code required volume achieved.
- 3) periodic System Leakage tests per Table IWB-.500-1
- 4) Inservice Hydrostatic test per Table IWB-2500-1 F. IMPLEMENTATION SCHEDULE!
SECOND INSERVICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1998
- 8. ATTACHMENTS:
001-PRZ PRESSURIZER NOZZLE LIMITATIONS TOP OF PRZ 001-PRZ-1 PRESSURIZER BOTTOM HEAD LIMITATIONS
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INBERVICE INSPECTION RELIEF REQUEST NO.: 6 A. COMPONENT CLASSIFICATION!
CLASS 1 CODE CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING NOMINAL PIPE SIZE EQUAL TO OR GREATER THAN 4 INCHEB NOZZLE TO PIPE TRANSITION WELDS B. EXAMINATION REQUIREMENTS:
CODE CATEGORY EXAMINATION REQUIREMENTS B9. 11 e:<aminations performed during each B9. ~~1 inspection interval shall caver the circumference of 100/ of the weld.
Piping wel ds require valumetric and surface e:<amination methods. The area subject to e;<amination is identif ied in IWB- 500-8, See figure no. 001-PIPEBJ far examinatian requirements.
REQUESTED'he C. RELIEF Relief is requested from the ABME Code required surface area utilizing the surface e;<amination methad.
D. BASIS FQR RELIEF:
- i. Perf ormance of these evaminatians on the Reactor Pressure Nazzle ta pipe transition weld invalves e)<cessive costs) manhours and man/rem with little or no campensating increase in the level of quality and saf ety.
- 2.Section XI has reduced the volumetric portion of the e;<amination volume to the inner ane-third af the wal l thickness ( see f igure no. 001-PIPEBJ ), and stil l requires the surface e<amination af the autside surface (see f i gure no. 001-PIPEBJ ) . In most cases, this i s the most efficient and less expensive way af e;<amining these welds. In the case of the Main Reactor Coolant piping this is nat. the case due to the size of the piping, location of the welds (access), manremthe e:<posure cost af due to the close pro:<imity of the RPV, insulation removal, erecting scafolding, not to mention the increased time of the e;<aminer to canduct the surf ace examinations.
ST. LUCIE NUCLEAR PONER PLANT UNIT 1 SECOND INSPECTION INTERVAL lNSERVICE INSPECTION RELIEF REQUEST NO ~ s 6 Florida Power and Light Company feels'hat the extent of examinations conducted and the volume achieved along with the proposed ultrasonic e<amination in lieu of the surface e;<am will provide assurance of an acceptable level of Quality and Safety.
E. ALTERNATIVE EXANINATIONS AND TESTS 1 ~ Conduct volumetric e:<aminations from the inside surface of the Reactor Pressure Vessel during the Nechanized RPV ultrasonic e:<aminations of the noz"les, exam category B-D, and the remainder of the Nozzles welds at or near the end of the inspertion interval in conjunction with the RPV mechanized e<aminations.
- 2. Conduct a full volumetric ultrasonic e<amination technique to effectively examine the outside surfaces of the Reactor Vessel Nozzle Pipe to Transition welds, (OUTLET and INLET) from the I.D. surface (Figure No. 001-PSLNOZ) in lieu of the surface examinations as def ined in the proposed attachment to this relief request.
- 3. Conduct system pressure tests as required by the St. Lucie Inservice Pres ure Test Program.
4 ~ The extent of e:<amination required and the proposed e;<am coupled with the system pressure tests provide assurance of an acceptable level of qual ity arid saf ety.
F. INPLENENTATION SCHEDULEc SECOND INSERV ICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1998 The outlet nozzle pipe to transition welds to be e<amined by the end of the First period, in conjunction with the category B-D examinations.
The inlet nozzle pipe to transition welds to be examined with the mechanized e<aminations at or near the end of the inspection interval.
ST. LUCIE NUCLEAR POWER PLANT UNIT i SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. i 6
$ . ATTACHMENTSI 00l-P IPEBJ CODE REQUIRED EXAMINATION VOLUME AND SURFACE EXAM REQUIREMENTS 00i-PSLNOZ TYPICAL WELD CONFIGURATION (PSL)
ATTACHMENT ALTERNATE VOLUMETRIC EXAMINATION
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST NO.: 6 BT. LUCIE NUCLEAR POWER PLANT ATTACHMENT ALTERNATE VOLUMETRIC EXANINATION OF THE BT. LUCIE PLANT UNIT NO. i and 2 OUTLET AND INLET PIPING WELDB TO BE USED IN LIEU OF THE SURFACE EXAMINATION REQUIREMENTS
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. i 6 BACKGROUND TO PERFORM ULTRASONIC WELD EXAMINATIONS, THE ULTRASONIC SEARCH UNIT IS APPLIED TO THE PIPE BASE METAL ADJACENT TO THE WELD ~
ANGULATION WEDGES CAUSE THE ULTRASONIC BEAM TO REFRACT AT THE PIPE SURFACE AND PROPAGATE INTO THE WELD AT A PREDETERMINED ANGLE. AS THE ULTRASONIC BEAM PASSES THROUGH THE PIPE WALL AND THE VOLUME OF THE WELD METAL, THE ULTRASONIC INSTRUMENT DISPLAYS ECHOS FROM THE REFLECTING SURFACES. THE DEGREE OF SUCESS DEPENDS ON THE EXAMINATION MATERIAL, THE STRENGTH OF THE ULTRASONIC BEAM, AND BEAM ANGLE WITH RESPECT TO THE ORIENTATION OF THE REFLECTING SURFACE.
ONE HRLF VEE PRTH F l GURE NO. 1
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 6 WHEN FULL VOLUME EXAMINATIONS ARE REQUIRED, THE ULTRASONIC BEAM IS MONITORED DURING THE ENTIRE BEAM PATH, i. e. ENTRY TO INSIDE SURFACE INPINBEMENT. CONDITIONS PERMITTING THE BEAM IS FURTHER AFTER IT REFLECTS AT THE INSIDE SURFACE AND CONTINUES MONITORED TO PROPAGATE IN A VEE PATH TOWARD THE OUTSIDE SURFACE.
FULL VEE PRTH FIGURE NO. 2
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. c 6 DURING PROPAGATION THE ULTRASONIC BEAM EXHIBITS THREE MAIN CHARACTERISTICS DIVERGENCE, ATTENUATION, AND SCATTERING. THE ESTABLISHMENT OF A DISTANCE AMPLITUDE-CORRECTION DURING CALIBRATION WILL GENERALLY COMPENSATE FQR THESE BEAM CHARACTERISTICS, TO A DEGREE. A FOURTH, RECENTLY RECOGNIZED CHARACTERISTIC IS THE FACT THAT ENTRY SURFACE "NOISE" CAUSES A "BLIND ZONE" IMMEDIATELY UNDER THE ULTRASONIC SEARCH UNIT. THIS BLIND ZONE CONTAINS A MULTITUDF QF ENTRY SURFACE SIGNALS FROM; THE ANGULATION WEDGE, THE COUPLING MATERIAL, SURFACE IRREGULARITIES, AND FROM THE EXAMINATION MATERIAL GRAIN STRUCTURE. DEPENDING ON THE EXAMINATION PARAMETERS, THIS BLIND ZONE CAN REPRESENT FROM A FEW MILS TQ AS MUCH AS AN INCH OF THE ULTRASONIC BEAM PATH WHERE FLAWS COULD EXIST UN-NOTICED.
BLIND ZONE FIGURE NO. 3
ST. LUG IE NUCLEAR POWER PLANT UNIT i SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO. t 6 THERE ARE TWO WAYS TO ENHANCE THE EXAMINATION OF THE ENTRY SURFACE. THE MOST COMMONLY EMPLQYED TECHNIQUE IS TO EXTEND THE ULTRASONIC CALIBRATION TO A FULL VEE PATH OR BEYQUND. THIS ALLOWS THE OBSERVATION OF THE OUTSIDE SURFACE IN A RELATIVELY NOISE-FREE SEGEMENT OF THE ULTRASONIC BEAM. (FIGURE NO ~ 2)
SECOND, THE SIMPLEST AND LEAST EXPENSIVE APPROACH, WOULD BE TO EXAMINE THE OUTSIDE (ENTRY) SURFACE WITH ANOTHER NDE METHOD.
THUS, WE RELY ON THE ULTRASONIC METHOD ONLY FOR THAT PORTION OF THE EXAMINATION VOLUME WHERE IT HAS PROVEN RELIABILITY. THIS IS THE ESSENCE OF THE ASME SECTION XI EXAMINATION REQUIREMENTS. EVEN THOUGH THE ULTRASONIC PORTION OF THE EXAMINATION VOLUME HAS BEEN REDUCED TO THE INNER QNE-THRID OF THE WALL THICKNESS, FIGURE NO.
4 THE SURFACE EXAMINATION QF THE OUTSIDE SURFACE IS STILL MANDATED. FIGURE NO. 5 FOR MOST PIPING WELDS THIS APPROACH IS Tl-lE SIMPLEST AND LEAST EXPENSIVE, BUT THIS IS NQT SO WHEN APPLIED TO THE REACTQR VESSEL NOZZLE -TQ- PIPE WELDS. BECAUSE OF THEIR LOCATION, THESE WELDS POSE UNUSUAL PRQBLEMS.
ST. LUCIE NOZZLE TO PIPE TRANSITION WELD PROBLEMS
- i. SCAFFOLDING IS NOT POSSIBLE, QR OF LIMITED VALUE
- 2. MAN-REM EXPOSURE IS HIGH ( 5 MAN "REM)
THE REMOVAL QF THE INSULATION IS VERY COSTLY
ST. LUG IE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 6 FPL PROPOSES THE UBE OF STATE-OF-Tl-IE-ART ULTRASONIC EXAMINATION TECHNIQUES TO EFFECTIVELY EXAMINE THE OUTSIDE SURFACE OF THE REACTOR VESSEL NOZZLE-TO-PIPE TRANSITION WELDS. THIS EXAMINATION WILL ACCOMPLISH MORE THAN THE CURRENT SURFACE EXAMINATION BEING PERFORMED AT ST. LUCIE. THE ULTRASONIC EXAMINATION WILL INVESTIGATE THE OUTSIDE SURFACE OF THE WELDS IN TWO DIRECTIONS CIRCUMFERENTIALLY AND IN TWO DIRECTIONS AXIALLY COVERING l00% OF THE WELDS PLUS ONE INCH QN EACH SIDE.
NOZZLE R PIPE i/3 T D C i/9 IN 1 /'t EN..
ERRI1INRTION VOLUI1E R-B-C-D FIGURE NO.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NQ. t 6 ULTRASONIC EXAMINATION A HIGH RESOLUT ION 45 DEGREE SHEAR WAVE WILL BE PERFORMED QN THE WELDS WITH THE EXAMINATIQN SENSITIVITY ESTABLISHED USING 2/ T DEEP NOTCHES.
ULTRASON I C EXAMINATION UNACCEPTABLE OUTSIDE THIS EXAMINATION WILL BE PERFORMED TO DETECT HAVE BEEN DETECTED USING SURFACE SURFACE FLAWS THAT WOULD EXAMINATION TECHNIQUES QN THE OUTSIDE SURFACE. THIS APPROACH WILL THE WELD WHILE ALLOW EXAMINATION QF THE ENTIRE CIRCUMFERENCE OF OF RADIATION EXPOSURE BY ALSO SAVING A SIGNIFICANT AMOUNT FOR MANUAL EXAMINATIQN QF THE OUTSIDE ALLEVIATING THE NEED SURFACE.
E><RN I NRT I GN RRER E-F 1 /2" I /2" PIPE E><RNI NRT I ON RRER FIGURE NO. 5 10
ST. LUC IE NUCLEAR PONER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NQ.: 6 ONE RND ONE HRLF VEE PRTH l GURE NO. 7
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST No. 7 A. COMPONENT CLASS IF I CAT ION!
Class 1 Manuf acturer Byron Jackson Type pump DFSS Si"=e 35 x 35;< 43 Component REACTOR COOLANT PUMP B. EXAMINATION REQUIREMENTS!
II EXAM CAT. ITEM NO. EXAMINATION REQUIREMENTS B-L-1 B12. 10 Volumetric examination, to include 100/ of pressure retaining welds, of one pump in each group of pump~
performing similar function~ in a system. The examinations shall be performed during each inspection interval, and maybe perf ormed at or near the end of the inspection interval.
B-L-2 812 20
~ Visual e<amination of the internal pressure boundary surface on one pump in each of the group of pumps perf orming similar functions in the system during each inspection interval. The e:<aminations maybe performed at or near the end of the i nspecti on interval .
RELIEF REQUESTED:
II Relief is requested from the ASME Code required examinations for the f ol lowing:
100/ volumetric examination of the reactor coolant pump casing welds.
AND
- 2. 100/ visual examination of the reactor coolant pump interior pressure boundary surface.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST No. 7 Relief is requested for the following components:
PUMP IDENTIFICATION SERIAL NUMBER R. C. NUMBERS 1A1 681-N-0445 34356 1A. 681-N-0446 ~4981 181 681-N-0447 u498>
1B2 681-N-0448 34983 D. BASIS FOR RELIEF:
GENERAL St. Lucie Nuclear Power Plants, Unit No. 1, has reactor coolant pumps which were manufactured prior to the initial issuance of the ASME Boiler and Pressure Vessel Code,Section XI and the design did not provide for the disassembly and removal of fi:<ed internals. The pumps were designed to provide reliable service for the plant lifetime without internal maintenance or inspection. The impracticality of performing these e;<aminations is not unique to St. Lucie, and has initiated generic studies to evaluate the need for inspection and to develop specific examinat i on techni ques.
To date, no technique has been qualif ied and proven practical for performing inservice inspection's of the Type E pump design.
DISASSEMBLY 8c REASSEMBLY The disassembly and reassembly of the pumps is e;<tremely di f f i cul t given the i nter f erence and/or tight f i ts which need to be addressed. Without painstaking care, the disassembly / reassembly process could degrade the pump internals from an operatianal standpoint.
There is a very low probability, based upon e:<perience, to disassemble pump(s) soley for maintenance purposes. There is no requirement by the pump manufacturer (Byron Jackson) to disassemble the pump(s) as part of normal maintenance or inspection. Accordingly, Florida Power 5 Light Company's procedures do not r equire disassembly of the pump (s) f or maintenance or inspection purposes. There is no reported failures within the pump casings with these model pump(s).
Operating experience with these pumps to date has validated the designer's intent to provide for service free of major disassembly.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST No. 7 EXAMINATIONS RADIOGRAPHIC CONVENTIONAL The presence of the di f f user vanes (Fi g. No. 1 ) precludes conventional radiography, in that the vanes prevent placement of the RT f i lm casset tes insi de the pump (as does the radiation field in terms of the radiographic film and personnel radi at i on e;<posure) .
Placement of the film on the outside of the pump is feasible, but there is no radiographic source suitable for placement inside the pump. Standard isotopic radiation sources are too weak to penetrate the thick casting and background radiation from the inside surface of the pump would diminish sensi ti vi ty.
Special strong isotopic sources would be impractical to handle and position in-ide the pump without special designed handling equipment and not to mention personnel radiological exposure from the radiographic source itself.
MINIATURE LINEAR ACCELERATOR (MINAC)
The Miniature Linear Accelerator was considered, but the Type E pump design precludes positioning of the accelerator inside the pump.
Double wall radiography utilizing the MINAC has also been considered with some hope of attaining meaningful radiographs of a portion of the casing welds. This technique has not been qualified to date and appears to be some time off, possible.
if at all To per f orm thi s e<aminati on, large expenditures of manhours and man-rem are required. Based on actual data compiled from the radiographic examination of the Turkey Point Unit No.
reactor coolant pumps casing welds and the visual e'<amination of the internal pressure boundary surface on one pump, in e<cess of 5900 manhours and 46 man-rem exposure was e:<pended in the disassembly, e:<aminations and reassembly o-f the pump.
This data does not include engineering time or pre-outage job planning, nor does it include radiation protection personnel that required direct coverage and the posponement of work activities in other areas of the containment building due to the amounts of radiation being produced during the conduct of the radiography exposures of the casing welds.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST No. 7 ULTRASONIC EXAMINATION Ultrasonic e<amination is not feasible due to the material construction of the pump casing. The pump casing is fabricated from cast stainless steel ( ASTM AZ51, Grade CFSM ). The material is essentially a cast-type 316 stainless steel. The coarse grain structure inherent in thick stainless steel castings preclude the use of conventional ultrasonic e;<aminations. Future developments in ultrasonic examination techniques may provide a method to e:<amine thick stainless steel castings.
When and if a major breakthrough in ultrasonic e:<amination techniques is made that satisfies the examination requirements of the ASME code Florida Power 4 Light will comply with the intent of. the code LIQUID PENETRANT METHOD Florida power 8. light Company has considered using the liquid penetrant method of examination as a alternate to>> the volumetric examination referenced in the code, but rejected this method based on the following:
Because of the porus condition of the casting surface of the weld ones, considerable surface smoothing will be required in order to enable meaningful examination and interpretation the results.
Such weld su/"f ace f inishing operations,, if not performed prior to the preservice inspection, will be e:<tremely difficult at the time of the inservice inspection.
To further complicate the surface smoothing pr ocess, St.
Lucie's pumps have been operational since 1976, and at that time the insul ati on used on these pumps was abestos. The surface preparation would require personnel to conduct this process in a closed area with respirators, and be directly monitored by health physics personnel to control the spreading of contaimination to other areas within the containment building.
The reccommended method of penetrant is the water-washable type, using this method would require a sufficient water supply, a 'method of containing the water and disposing of the run offs after removal of the penetrant
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST No. 7 The solvent-removable type penetrant method was rejected due to the si="e of the pump and the surface roughness waul d entrap the penetrant thereby enable meaningful examination and interpretation of the results. Using this method would also require excessive manhours and man-rem.
CODE REQUIREMENTS The examination requirements for pumps (Figure IWB-2500, AGEE Code, Section XI) were originally developed for Type F, radially split, a<isymmetric casing designs. Bt. Lucie Plant has Type E pump designs (Fi g. No. 2) which have geometric configurations that. make e<amination's of the casing welds not practical or meaningf ul to perform under the current code requirements.
Florida Power 4 Light Company feels that adequate safety margins are adherent in the basic design. The structural integrity aFforded by the e<isting pump casing material will not significantly degrade over its lifetime. Pump casings are generally overdesigned ( because oF added wall thickness) to provide stabili ty under operating load. Operating stresses in the pump casings, are well below the levels associated with vessels, therefore with lower operating stresses, fatigue l i f e is signif icantly improved.
Florida Power and Light Company feels that the results achieved on our Turkey Point Plant in 1'782, satisfactory'nspection coupled with the same results conducted by (3) other utility company's will provide the additional assurance as to the pump's casing integrity.
E. ALTERNATE EXANINATIONBi As a alternate to the e:<amination,s required by the code, Florida Power 5 Light Company proposes the following:
- 1. A 100/ visual e<amination of 0he pump interior to the extent practical ( recoginizing the interference by the vanes ) ( Fig. No. 1 ) should the pump be disassembled for maintenance.
- 2. A 100/ Radiographic e:<amination of the pump casing welds to the extent practical (recogni=ing the interference by the vanes) should the pump be disassembled for maintenance.
ST. LUCIE NUCLEAR POWER PLANT UNIT 1 SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST No. 7 The reactor coolant pump shall be hydrostatical ly tested-per the requirements of the ASME Boiler Pressure Vesssel 4~
Code.
A 100% visual evamination of the external surfaces only, of one <1) pump, and one (1) weld at or near the end af i
the inspect on interval .
The alternate e;<aminations and tests provide assurance of an acceptable level of quality and safety.
F. IMPLEMENTATION SCHEDULE At or near the end of the inserv'ice inspection interval.
Interval dates: 11 Feburary 1988 to 11 Feburary 1998 G ATTACHMENTS TQ RELIEF REQUEST NO. 7 FIGURE NO. 1 HORIZONTAL CROSS SECTION OF PUMP FIGURE NO ~ 2 VERTICAL CROSS SECTION OF PUMP FIGURE NQ. Z PUMP WEI D LOCATION
ST ~ LUCIE NUCLEAR POWER PLANT UNIT NQ.
SECOND INSPECTION INTERVAL INSERV ICE INSPECT IQN RELIEF REQUEST NO.: 8 A. COMPONENT CLASSIFICATION:
CLASS 1 CODE EXAMINATION CATEGORY 8-M-2 VALVE BODY, EXCEEDING 4 IN. NOMINAL PIPE SIZE B. EXAMINATION REQUIREMENTS:
B12. 50 Perform VT-3 visual e',< ami nat 1 on of the internal surface of one valve within each group of valves that are of the same constructional design. (such as globe, gate or check valve) and manuf acturing method, and perf orm similar.
functions in the system ( such a" containment isolation and system overpressure protection).
C. RELIEF REQUESTED:
Relief is requested from the disassembly of these valves for the sole purpose of performing a visual examination.
SIZE SYSTEM VALVE ID TYPE Q II RC V-1200 SAFETY Q II RC V-1201 SAFETY g II RC V-1202 SAFETY
~
6" SI HCV-3615 GLOBE g II SI HCV-3625 GLOBE Q II SI HCV-3635 GLOBE Q
II SI HCV-3645 GLOBE Q II SI V-3114 CHECK Q II SI V-3124 CHECK Q II SI V-3134 CHECK Q II SI V-3144 CHECK
+ II SI V-3217 CHECK 12" SI V-3227 CHECk>>
1 +II SI V-3237 CHECK SI V-3247 CHECK
] 0 ll SI V-3480 BATE 10 II SI V-3481 GATE 10 II SI V-3651 GATE 10 II SI V-365 GATE 1 gll SI '-3614 BATE j.2ll SI V-3624 BATE 1+II SI V-3634 GATE 12" SI V-3*44 GATE
ST ~ LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 8 D. BASIS FOR RELIEF'isassembly of these valves f or the sole purpose of performing a visual (VT-3) e:<amination is not practical.
The process of disassembling these components will result in considerable e:<posure of personnel to radiation and significantly increase the risk of component damage or failure without providing a compensating increase in the l evel of qual i ty and saf et.y.
E. ALTERNATE EXAMINATIONS:
- 1) Conduct a visual (VT-3) e:<amination in accordance with the requirements of table IWB-2500-1, category B-M-2 in the event the components are disassembled for maintenance or repair.
- 2) Periodic inservice testing per subarticle IWV->400 and or IWV-3520 (valves) or
- 3) Periodic system leakage tests per category B-P, table IWB-2500-1
- 4) The alternative tests and evaminations provide an assurance of acceptable quality and safety.
F. IMPLEMENTATION SCHEDULEc SECOND INSERV ICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1988 G. ATTACHMENTSc
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST NO.:
A. COMPONENT CLASSIFICATION:
CLASS 2 CONTAlNMENT SPRAY SYSTEM PRESSURE RETAINING WELDS IN PIPING, 1/2" OR LESS B. EXAMINATION REQUIREMENTS'XAM CAT. ITEM NO. EXAMINATION REQUIREMENTS C5. 10 Perform a surf ace e:<amination of C5. 11 100% of each circumf erential weld requiring e:<amination.
C5. 12 Per f orm a sur f ace e:< ami nati on of 2.5 t at intersecting circum f erenti al wel d.
C. RELIEF REQUESTED!
Relief is requested from the surface examination requirements for the following lines.
I."6-CS-16 I-10-CS-12 I-12-CB-18 I
I-6-CS-17 I-10-CS-13 I-12-CS-19 I-6-CS->0 I-6-CS-21 I-6-CS-22 I-6-CS-23 I-6-CS-24 I-6-CS-25 I-6-CB-28 l-6-CS-29 Drawing 001-CB, attached provides a PAID of those line~
that are 1) Affected, 2) evempt and .) those lines to be evamined.
ST. LUCIE NUCLEAR PONER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.:
D. BASIS FOR RELIEF:
1> The containment Spray System piping is not required to operate during normal operation 2> Following initial inspection and testing, the Containment Spray piping downstream of the second isolation valve outside containment is subjected to no pressure transients and no temperature transients other than ambient containment building/auxiliary building pressure and temperature, thus, there is no mechani f
sm f or f ai lure
- 3) ASME Section XI, Table INC-2500-1, E;<amination Category C-H, Note 1, e;<empts open ended portions of systems from the Visual (VT-2) evamination.
E. ALTERNATE EXAMINATIONSc
- 1) At least once every five (5) years, the piping is tested by performing an air or smoke flow test through each spray header to demonstrate an open flow path.
(reference ASME Section XI, INC-5222(d) .
- 2) In the event that the containment spray system is operated or in the case of a significant seismic event, FPbL will evaluate this Relief Request to determine if additional nondestructive e:<aminations are warranted.
- 3) The alternative tests and e<aminations provide an assurance of acceptable quality and -afety.
F ~ IMPLEMENTATION SCHEDULE:
SECOND INSERVICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1988 G. ATTACHMENTS:
001-CS CONTAINMENT SPRAY PIPING DRAWING
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION lNTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 10 A. COMPONENT CLASSIFICATION:
CLASS 1, 2 AND ASME SECTION XI, 1983 EDITION THROUGH SUMMER 1983 ADDENDA 1 WF-5000 INSERV I CE TEST REQUIREMENTS MECHANICAL AND HYDRAULIC SHOCK ARRESTORB (BNUBBERS)
B. TEST I NB REQUIREMENTS!
IWF-5400(c) Snubbers that fail the inservice test requirements of IWF-5400 shall be repaired in accordance with IWF-4000 and retested. An additional sample of 10/
of the total number of snubbers shall be tested at that time. Additional sample testing shall be continued until all units within the sample have met the requirements of (b) above.
C. RELIEF REQUESTED!
Relief is requested from the additional sample of 10/ of the total number of nonexempt (IWF-1.30) snubbers.
D. BASIS FOR RELIEF:
- i. The Code requirements to test an additional 10% of the total snubber population in the event of a f ai lure does not take into account the di ff erence in the operating character istics of different types of snubbers and their relative susceptibili ty to various service-induced failure mechanisms.
2 ~ There are substantial di ff erences, based on manuf acture and design, specifically in functional operation and dynamic response of the load of snubbers. A snubber of one design may tend toward failure under a given set of conditions while a snubber of a different design may be essentially unaf f ected by the same condition.
In addition to item 2 above, conditions which lead to the failure of a susceptible snubber may sometimes be demonstrated to be consistent with conditions unique to the system in which it is installed.
ST. LUC IE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 10 Failure evaluation may indicate that snubbers of a certain t:ype have a tendency to fail when exposed to combination of temperature and vibration. When a'ertain this evaluation clearly establishes that this failure exists only in a certain system, then it becomes evident that the additional sample should be taken from the susceptible population. Snubbers of the same type in other syst:ems, t hat are exposed to different operating conditions, should be adequately addressed in the original test sample.
The NRC Standard Technical Specif ication for Combustion Engineering requires testing of the additianal 10% of the snubber population to be conducted on the same type of snuber as the snubber that failed.
Florida Power and Light Company feels that the additional sampling as required by Il4F-5400(c) does not adequately provide for a realistic level of confidence for locating and correcting conditions as described above.
7 ~ Florida Power and Light Company feels that these alterhative sampling methods described below are consistent with the NRC position as evidenced by the Combustion Engineering Standard Technical Specif icati one E. ALTERNATE EXANINATIONS:
Conduct a visual (VT-3) examination of all snubbers during each refueling outage.
During the scheduled functional test, if a snubber failure is identified, an additional 10/ sample of the same type of snubber as that which failed will be tested as r equi red by plant. technical specifications.
An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The I esults of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the operability of other snubbers irrespective of type which may be subject to the same failure mode.
ST. LUClE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO ~: 10
- 4) Should the results of the evaluation indirate that f ai lure was caused be ei ther manuf acturer or design def iciency, further action shall be taken, if needed, based on manufacturer or engineering recommendations.
- 5) The alternative e:<aminations and tests provide assurance of an acceptable level of quality and safety.
F. IMPLEMENTATION SCHEDULE:
SECOND INSERVICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1988
- 8. ATTACHMENTS'one
BT. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO.! 11 A. COMPONENT CLASSIFICATION!
CLASS 1 and CLASS 2 CODE EXAMINATION CATEGORY N/A ULTRASONIC CALIBRATION BLOCKS ASME SECTION XI, APPENDIX III B. EXAMINATION REQUIREMENTS>
III-3400 The basic calibration blocks shall be made fr om the same nominal diameter and naminal wall thickness or pipe schedule as the pipe to be el< ami ned I I I-3411 The calibration block shall be f abri cated f r om one af the materials specif ied f ar the piping being joined by the weld.
C. RELIEF REQUESTED:
Relief is requested I'l-3400 from the ASME Cade, Appendi;<
III-3411 which requires 1) the III, requirements, AND calibration block to be the same nominal diameter and wall thickness or pipe schedule and 2) be fabricated fram ane of the same materials as the piping being joined. Relief is requested for the fallowing:
CAL. BLOCK COMPONENT DEVIATION FROM CODE I.D. NUMBER DESCRIPTION UT-4A PRIMARY COOLANT PIPING THE BLOCK IS NOT CURVED HOT LEG DIFFERENT MATERIAL UT-S PRIMARY COOLANT PIPING THE BLOCK IS NOT CURVED COLD LEGS UT-45 MAIN STEAM PIPING NELDS DIFFERENT DIAMETERS DIFFERENT THICKNESS UT-4 REACTOR PRESSURE VESSEL THE 3/4t HOLE IS TOO CLOSE FOR THE STRAlGHT BEAM<0 deg.) EXAM REACTQR PRESSURE VESSEL THE HOLES ARE DRILLED WITHIN 3/4" OF THE END OF THE BLOCK.
BT. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO.: ii D. BASIS FOR RELIEF:
- 1. UT-4A PRIMARY COOLANT PIPING, HOT LES FPSL has determined that SA-533 Grade A is comparable to SA-516 Grade 70 (piping material), as provided by ASMF Section XI, Appendi:< II I, Article III-3411 (c).
Article 5 of the ASME Section V allows flat blocks for items greater than 20 inch diameter, as does Article 4 of ABME Section V.
- 2. UT-6 PRIMARY COOLANT PIPING, COLD LEG The block. material is identical to the coolant piping material, therefore it is preferred over a curved block of different material.
Article 5 of the ABME Section V allows flat blocks for items greater than 20 inch diameter, as does Article 4 of ASME Section V ~
P th a half vee e:<amination technique, curvature is not I'i a major source of error. Bound path calibration is used with full scale plots of indications.
- 3. UT-45 MAIN STEAM PIPING NELDS The subject piping welds sre of two sizes:
a) 34" diameter, 1. 250 " wal 1 b) 36.6 5" diameter, 1.234" wall. The requirements of ASME cod are such that two blocks, one of each diameter would be required.
c) The wall thickness is essentially the same, therefore there is little or no change in the sensitivity.
d) The small difference in diameter is not ultrasonically noticable.
ST. LUCIE NUCLEAR POWER PLANT UNIT NQ. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECT lQN RELIEF REQUEST NO.: i1
- 4. UT-4 AND UT-5 REACTOR PRESSURE VESSEL The, closeness of the 3/4 t hole to the end of the block, satisfies the requirements of the code to which they were f abl 1 cated e The condition noted does not interfere with the calibration performed on these blocks.
- 5. The proposed calibration blocks have been in use since the plant was bui l t, their continued use would tend to provide cons i s tent r esul ts.
E. ALTERNATE EXAMINATIONS')
Perform the Code required e:<aminations using the proposed calibration blocks as def ined above.
- 2) Periodic system leakage tests per category B-P, and C-H tables IWB-2500-1 and lWC-2500-1.
- 3) The alternative tests and e.'<aminations provide an assurance of acceptable quality and safety.
I F. IMPLEMENTATION SCHEDULEs SECOND INSERV ICE INSPECTION INTERVAL 11 FEBURARY 1988 TO 11 FEBURARY 1988 G. ATTACHMENTS<
None
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: 12 A. COMPONENT CLASSIFICATION:
Cl ASS 1 NELDS CLASS 2 WELDS SECTION XI 198K EDITION THRU SUMMER 198K ADDENDA TABLES; IWB-2500-1 TABLES; INC-2500-1 B. EXAMINATION REQUIREMENTSc CLASS 1 E:<aminati on volumes and surfaces shall be performed in accordance with the applicable f igures as referenced in Tables INB-2500-1.
CLASS 2 E;<amination volumes and surfaces shall be performed in accordance with the applicable f i gures as ref erenced in Tables INC-2500-1.
C. RELIEF REQUESTED:
Relief is requested from the ASME Code,Section XI, Division 1, code required volume and surface e<amination requirements f or Class 1 welds INB-2500 or Class 2 welds INC-2500 that cannot be e:<amined.
D. BASIS FOR RELIEFc
- 1. 10 CFR 50.55a (g) (4) recogni es that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1 shall meet the requir ements, e:<cept design and access provisions requirements, set forth in Section XI, to the e:<tent practical within the limitations of design, geometry and materials of construction of the components.
- 2. St. Lucie Nuclear Plant, Unit No. 1, Operating License was issued on March 1, 1976, and the initial Inservice Inspection Program was prepared to meet the ASME Code 1'770 Edition through the Ninter 1970 addenda, which only addressed class 1 components. Interference by another component or part geometry which reduces the evamination coverage was not taken into consideration for the remainder of the components class 2 and class
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. 1 SECOND INSPECTION INTERVAL INBERVICE INSPECTION RELIEF REQUEST NO.: 12 3 ~ Interf erences are common throughout the industry for older constructed plants. Even wi th added e:<aminati ons to compensate for these interf erences smal l parts of an e:<amination volume or surface area st i l 1 cannot be fully e:<amined as required by later Editions and Addenda of the code ~
- 4.Section XI, does not address or even recogni e relief from any of the code requirements, therefore only the Nuclear Regulatory Commission through 10 CFR 50 can approve reliefs from any of the code requirements.
- 5. The NRC representatives at the ASME'ommittee meetings e:<pressed concern as to the amount of Utility requests for relieF that they were recieving and the lack of manpower to .r eview and approve these request in an evpiedient manner.
- 6. A proposed ABME Code Case is currently being discussed within the ASME Code committees that would reduce the e:<amination coverage by a certain percentage and be acceptable for compliance with the code requirements.
still To date this Code case has not been issued.
- 7. In order to provide some relief in these areas, FP@L proposes the following alternative action that will not only provide ease to FP8<L and the NRC, but still maintain the required documentation necessary .For enforcement and review of Inservice Inspection obstructions to assul e that the Quality and safety level has not been r educed beyound the minimum standards.
E. ALTERNATE EXAMINATIONS:
- 1) FPhL proposes that up to a 20/ reduction in e:<amination coverage on any given Class 1 or ~
weld may be accepted provided:
ST. LUCIE NUCLEAR POWER PLANT UNIT NO. i SECOND INSPECTION INTERVAL INSERV ICE INSPECTION RELIEF REQUEST NO.: i2 condign a) The reduction in coverage is due to access or conf i gurat i on i ons.
b) The reduction in coverage is required to be for discrete volumes or areas. A general reduction in coverage for the complete length of a weld is not acceptable.
c) The length of any discrete volume or area of missed coverage shall not exceed 8 inches along the weld length or 20/ of the total weld length, whichever is less.
d) For ultra. onic e<amination, if multiple angles (e.g.
0 deg., 45 deg., and 60 deg.) or scan directions
.(e.g. parallel to the weld and perpendicular to the weld) are required, and the examination cannot: be per.formed using all ,the required angles and scan directions, then the e.<amination volumes that missed coverage by any required angle or scan direction shall be included i'n the total volume of missed coverage.
e) For volumetric or surface e<amination, the 20/
reduction limit applies to the sum of all discrete volumes or areas of missed coverage for each weld.
f) When the reduction in coverage is less than .0/, the coverage of greater than 80/ is assumed to be essentially 100%, and acceptable by the code.
- 2) When the reduction in coverage is equal to or greater t:han 20/, A relief request shall be filed with the Regulatory Authority pursuant to the requirements of i0 CFR 50.55 a.
- 3) When the reduction in coverage is less than .0/, the r eduction in coverage shall be fully document:ed in a format consistent wi th the -format f or a rel i ef and included within the applicable Inservice Inspection Program in accordance with IWA-6000.
ST ~ LUCIE NUCLEAR POWER PLANT UNIT NO.
SECOND INSPECTION INTERVAL INBERV ICE INSPECTION RELIEF REQUEST NO.: 12
- 4) Qn 'a periodical bases all documented reductions in coverage shall be submitted to the Regulatory Authority as part o.F the Program update submittal.
- 5) Periodic system leakage tests per category B-P, and C-H tables INB-2500-1 and INC-2500-1 ~
- 6) The alternative tests and e:<aminations provide an assurance of acceptable quality and saFety and assure the that all reductions in coverage are documented and included in evisting programs as required by ASNE Code.
a F. INPLENENTATIQN SCHEDULE!
SECOND INSERV ICE INSPECT I QN INTERVAL 11 FEBURARY 1988 TQ 11 FEBURARY 1988 B. ATTACHNENTSt
- 4. 0 EVALUATION CRITERIA 4.1 Acceptance Standards Class 1 Class..1 examination acceptance standards are in accordance with the requirements of ASME Section XI 1983 Edition, through and including the Summer of 1983 Addenda-Examination Components and Part Acceptance C t o n d S a d B-A Welds in Reactor Vessels IWB-3510 B-B Welds in Other Vessels IWB-3511 B-D Vessel Nozzle Welds IWB-3512 B-E Partial Penetration Welds IWA-5250 in Vessels B-F Dissimilar. Metal Welds IWB-3514 B-G-1 Bolting ) 2" in Diameter IWB-3515 B-G-2 Bolting < or = to 2" Diameter Integral Attachments for Vessels IWB-3516 B-J Welds in Piping IWB-3514 B-K-1 Integral Attachments for Piping IWB-3516 Pumps, and Valves B-L-1, B-M-1 Welds in Pump casings &, Valve Bodies IWB-3518 B-L-2, B-M-2 Pump Casings 5 Valve Bodies B-N-1, B-N-2 Interior Surfaces & Internal B-N-3 Components of Reactor Vessels B-0 Control Rod Drive Housing Welds IWB-3523 B-P All Pressure Retaining Components IWA-5250 2
B-Q Steam Generator Tubing IWB-3521 4 ASME Section XI Acceptance Standards are in the course of preparation,use Mfg. Code &, Applicable Standards.
28
..4.~ Acceptance Standards Class 2 Class 2 examination acceptance standards are in accordance with the requirements of ASME Section XI 1983 Edition, through and including the Summer of 1983 Addenda. Article IWC-3000, Acceptance 'Standards for Flaw Indications, are in course of preparation. The rules of IWB-3000 may be used.
Examination Components and Part Acceptance Ca o d S an a C-A Welds in Pressure Vessels IWB-3511 C-B Vessel Nozzle Welds IWB-3512 C-C Integral Attachments for Vessels IWB-3516 Piping, Pumps, and &, Valves C-D Bolting > than 2" IWB-3515 C-F Welds in Piping IWB-3514 C-G Welds in Pumps and Valves IWB-3518 Oc-H All Pressure Retaining Components IWA-5250
4 .3 Acceptance Standards Class 3 Class 3 examination acceptance standards are in accordance with the requirements of ASME Section XI 1983 Edition, through and including the Summer of 1983 Addenda. Article IWD-3000, Acceptance Standards for Flaw Indications, are in course of preparation. The rules of IWB-3000 may be used.
Examination Components and Par't Acceptance D-A Integral Attachment Welds on IWB-3516 Systems in Support of Reactor Shutdown Function Pressure Retaining Components IWA-5250 D-B Integral Attachment Welds on IWB-3516 Systems in Support of ECC,CHR Atmosphere Cleanup,and RHR Pressure Retaining Components IWA-5250 D-C Integral Attachment,Welds on IWB-3516 Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool Pressure Retaining Components IWA-5250 30
4.4 Acceptance Standard for Supports Class 1,2,&, 3 The acceptance standards for the examination of Class 1, 2, and 3 supports are in accordance with the requirements of ASME Section XI, 1983 Edition, through and including the Summer 1983 Addenda as follows:
4.4.1 Acceptance Standards IHF-3400 Component Support Structural Integrity (a) Component support conditions which are unacceptable for continued service shall include the following;
- 1) deformations or structural degradations of fasteners, springs clamps, or other support items;
- 2) missing, detached, or loosened support items;
- 3) arc strikes, weld spatter, paint, scoring, roughness, or general corrosion on close tolerance machined or sliding surfaces;
- 4) fluid loss beyond specified limits or lack of fluid indication, (hydraulic snubbers only);
- 5) improper hot or cold positions,(snubbers and spring supports).
(b) Except as defined in a) above, the following are examples of nonrelevant conditions-
- 1) fabrication marks (e.g.,from punching, layout, bending, rolling and machining);
- 2) chipped or discolored paint;
- 3) weld spatter on other than close tolerance machined or sliding surfaces;
- 4) scratches or surface abrasion marks;
- 5) roughness or general corrosion which does not reduce the load bearing capacity of the support;
- 6) general conditions acceptable by material, Design,and/or Construc-tion Specifications.
(c) Component supports whose examinations reveal conditions as defined in a) above, shall be unacceptable for continued service until they have been repaired, replaced, or evaluated as meeting the acceptance standards found in 4.4.2 of this Summary.
31
- 4. 4. 2 Acceptance IWF-3122.1 Acceptance by Examination, Component supports whose examinations do not reveal conditions described in IWF-3400(a) shall be acceptable for continued service. Verified changes of indications from prior examination shall be recorded in accordance with IWA-6220 IWF-3122.2 Acceptance by Repair, Component supports whose examination reveal conditions described in IWF-3400(a) shall be unacceptable for continued service until such conditions are repaired and re-examined in accordance with IWF-3123 Acceptance requirement of IWF-3122 ',
by Replacement, a component As an alternative to the
'WF-3122.3 support or portion of a component support which is unacceptable for continued service may be replaced in accordance with IWA-7000.
IWF-3122.4 Acceptance by Evaluation or Test, As an alternative to the requirements of IWF-3122.2, a Component support or portion of a component support which is unacceptable for continued service may be analyzed and/or tested to the extent necessary to substantiate it' integrity for it's intended service. Records and reports shall meet the requirements of IWA-6000.
4.4.3 The Inservice testing of hydraulic and mechanical snubbers is performed'in accordance with Section XI requirements as augmented by the St.4ucie Unit 1 Technical Specifications which contain the test-ing and acceptance criteria.
32
5.0 SUBMITTAL
SUMMARY
5.1 Description of ISI Plan Format The Second Ten Year Inservice Inspection Plan Tables are being prepared for the components and piping systems which are subject to examination per the requirements of ASME Section XI.The examination Tables have been designed to provide the information necessary to effectively implement the examination program.
For the purpose of efficiency and control the inspection plan has been divided into smaller areas of interest called zones. Each zone is developed from an isometric drawing of a specific component,sys-tem, or portion of a component or system which identifies all the welds and any other examination areas for that zone. The inspection plan tables that are generated from these isometrics (in conjuction with the isometrics) contain the information necessary for qualified examiners to perform the required examinations. The following is a description of the format used in the tables-A.Table Header The table header contains, but is not limited to-a) Plant name and unit no.
b) Plan revision no.
c) Code Class d) Component or system description e) Zone no.
B.Summary Number Each examination area(i.e.,weld, valve, support) is assigned an item number for administrative use only.
C.REF. DWG. NO.
Lists isometric drawing for the zone D.Examination area identification Lists unique identification number, description of examination area, calibration block, and location within the plant.
E.ASME Section XI Item number F.ASME Section XI Code Category G.NDE Method(to be used)
H.Plan Status Lists scheduling information for when each item is scheduled for examination by interval, period, and outage. also shows when the item was last examined.
I.Instructions Gives specific details for each item,i.e.,material type and thickness, relief request number(if applicable),and any other inform-ation which will aid in the examination of the item.
33
5.2 Description of Summary Submittal Tables The tables included in this submittal (appendices A, B, &, C for Class 1, 2, &, 3 respectively) summarize by code category and code item number the total number of each item in the plant. Further definition is given as to the number of items to be selected for examination during the Second Ten Year Interval.
The tables in appendices D, E, & F summarize by code catergory and code item number the hangers and supports subject to examination per Subsection IWF for Class 1, 2, &, 3 respectively.
Also included in the summary tables are the piping systems which were subject to examination during the First Ten Year Inservice Inspection Interval but are exempted for examination per Code Case N-408.These items are identified with "dummy" item numbers for correlation purposes only.
All tables and isometric drawings used for in the Second Ten Year Inservice Inspection Program are developed from the Plant "As Built" Drawings and from the First Ten Year Inservice Inspection Program.
34
t DATE:
REVISION:
08/26/87 REACTOR VESSEL HEA9 PLANT INSPECT!0N !N:ERVAL ST.LJCIE U"!IT I INSERV!CE INSPECTICN LGNS TER" PLAN C'SS I
I 1 COiiPDNENTS FlRST OUTASE YEAR SECOND THIRD PPESERVICE YEAR I
L P R!09 PER10D PERIOD 9 ASNE ASNE I SUNNARY GANINAi!ON AREA 0 SEC.I! SEC. !(I NDE OUTASE OUTASE GUTASE NiJNSER !O'NTIPICATICN P ITEN 4 CATBY ilETH i 1 2 3 4 I 2 3 4 1 2 3 4 INS;RUC IONS RPVCH REF. DNS NO 000023 RPV-CH-209-03C 91.2 8-8 UT I 87"- " Enn!NE >OX OF NELD.
NERID. NEED 0 180 2-4-
87 - 10X OP WELD LE1(STH EKANINED L
P X &L}R:M
DATEl OB/25/87 ST. LUCIE HUCLEAR PLANT UNIT 1 PAGEOS 1 REVISIONS 1 'NSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTIOH XI
SUMMARY
TABLE B CATESORY C-A - PRESSURE RETAININB HELDS IK PRESSURE VESSELS ASME 0 OF COMPOHENTS SEC XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTIDH EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS RED. 1ST PER 2HD PER 3RD PER
6.0 Records and Data Management Records of the ISI Plan, schedules, calibration standards, examination procedures, examination results and reports, certifications, and corrective actions required and taken, will be developed, submitted and maintained in accordance with the requirements ASME Section XI, Article IWA-6000.
35
RPPENDIN R CLRSS 1 ENRMINRT ION SUMMRRY TRBLES
DATE: OB/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 1 REVISION: I INSERVICE INSPECTION PLAN FOR tHE FIRST INTERVAL CLASS I SECTION XI SUtlttARY TABLE A T
CATEGORY B-A - PRESSURE RETAINING MELDS IN REACTOR VESSEL ASNE 4 OF CDNPONENTS SEC. Xl NUHBER OF RELIEF SCHEDULED/COMPLETED ITEN tt ITEN DESCRIPTION EXAM HETHOD SYSTEN DESCRIPTION IONE COMPONENTS REQ. IST PER 2ND PER 3RD PER 81.11 CIRCUttFERENTIAL SHELL MELDS VOLUHETRIC RCS RPV I RR-1 0/0 0/0 1/0 Bl. 12 LONGITUDINAL SHELL MELDS VOLUttETRIC RCS RPV 9 RR-1 0/0 0/0 I/O BI 21
~ CIRCUMFEREttTIAL HEAD MELDS VOLUMETRIC 'RCS RPV 1 RR-1 0/0 0/0 1/0 B1.21 CIRCUNFERENTIAL HEAD MELDS VOLUt!ETRIC RCS CLOSURE HEAD 1 0/0 0/0 1/0 B1.22 MERIDIONAL HEAD MELDS VOLUttETRIC RCS RPV 6 RR-I 0/0 0/0 1/0 B1.22 ttERIDIQNAL HEAD MELOS VOLUMETRIC RCS CLOSURE HEAD 6 RR-2 0/0 I/O 0/0 81 ~ 30 SHELL-TO-FLANGE MELD VOLUttETRIC RCS RPV 1 RR-1 I/O 1/0 1/0 NOTE:EXAMINE 1/4 IST PERIOD, 1/4 2ND PERIOD, I/2 3RD PERIOD BI.40 VOLUHETRIC RCS CLOSURE HEAD 1 RR-2 1/0 1/0 . I/0 SURFACE
<4>4% NOTE lEXANINE 1/3 1ST PER) 1/3 2ND PERy I/3 3RD PER B1.50 REPAIR MELDS VOLUMETRIC RCS RPV 0/0 0/0 0/0 B1.51 REPAIR MELDS-BELTLltiE REGION VOLUMETRIC RCS RPV 0/0 0/0 0/0
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 2 REVISION'. I INSERVICE It(SPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION Xl SUt(t(ARY TABLE A e CATEGORY B-B - PR.'SSURE RETAINING MELDS IN PRESSURIZER AsrE a OF CDNPONENTS SEC. Xl tlVt(BER OF RELIEF SCHEDULED/COMPLETED ITEN 4 ITEN DESCRIPTION EXAM i";ETHOD SYSTEM DESCRIPTION ZONE COt(PONENTS RED. IST PER 2ND PER 3RD PER B2. 10 PRESSURIZER-SHELL-TO-HEAD VOLUt(ETRIC RCS 0/0 0/0 0/0 MELDS B2. 11 PRESSURIZER-CIRCUMFERENTIAL VDLU)(ET1(IC RCS 1/0 1/0 0/0 SHELL-TO-HEAD MELDS B2. 12 PRESSURIZER-LONGITUDINAL SHELL VOLU)(ETRIC RCS 1/0 . 1/0 0/0 MELDS 82 '1 CIRCUt(FERENTIAL HEAD MELDS VOLUMETRIC RCS 0/0 0/0 1/0 82.22 t(ERIDIONAL HEAD MELDS VOLU))ETRIC RCS 0/0 0/0 1/0 82.31 STEAN GENERATORS (PRI)(ARY VOLUMETRIC RCS SG-IA 4 RR-3 1/0 I/O 1/0 SIDE)-CIRCUMFERENTIAL HEAD t
MELDS
%%%4m NOTE ; EXANINE I/3 1ST PERIOD, 1/3 2ND PERIOD, 1/3 3RD PERIOD 82.31 STEAt( GENERATORS (PRIMARY VOLU)(ETRIC RCS SG-18 0/0 0/0 0/0 SIDE)-CIRCUMFERENTIAL HEAD MELDS 82.32 STEAN GENERATORS (PRI)(ARY VOLUMETRIC RCS SG-1A 9 RR-3 1/0 I/O 2/0 SIDE)-iMERIDIONAL HEAD MELDS
%%%%a NOTE lNU)(BER OF CONPDNENTS INCLUDES 4 LONG. SEAMS IN EXTENSIOtt RING, ALL FOUR EXANINED MHEN TUBESHEET TO HEAD DOt(E 82.32 STEAN GENERATORS (PRINARY VOLUMETRIC RCS SG"18 4 9 0/0 0/0 0/0 SIDE)-t(ERIDIONAL HEAD MELDS 44+4+ NOTE lNU)(BER OF COt(PONENTS INCLUDES 4 LOt(G. SEAMS IN EXTENSIOH RING, ALL FOUR EXAMINED MHEN TUBESHEET TO HEAD DONE.
82.40 STEAN GENERATORS (PRlt(ARY VOLU)(ETRIC SG-IA 1 RR-3 1/0 1/0 I/O SIDE)-TUBESHEET-TO-HEAD MELD w%w44 t(OTE:EXAMINE 1/3 1ST PERIOD, 1/3 2ND PERIOD, I/3 3RD PERIOD 82.40 STEAN GENERATORS (PRINARY VOLU)(ETRIC SG-18 0/0 0/0 0/0 SIDE)-TUBESKEET-TO-HEAD MELD 82.50 HEAT EXCHANSERS (PRIMiARY SIDE) VOLUMETRIC RCS N/A 0/0 0/0 0/0
-HEAD-HEAD MELDS 82.5) HEAT EXCHANGERS (PRlt(ARY SIDE) VOLU)(ETRIC RCS N/A 0/0 0/0 0/0
-HEAD-CIRCU)(FERENTIAL HEAD MELDS
ST. LUCIE NUCLEAR PLANT UNIT ( PAGE:
DATE: 08/25/87 REVISION( ( INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS ( SECTION Xl SUNNARY TABLE A 4 OF COMPONENTS ASNE NUNBER OF RELIEF SCHEDULED/CONPLETED SEC. XI EXAN NETHOD SYSTE)( DESCRIPTION ZONE CONPONENTS RED IST PER 2ND PER 3RD PER ITEN 4 ITEN DESCRIPTION B2 52 HEAT EXCHANGERS (PRINARY SIDE) VO(.Ui(ETRIC RCS N/A 0/0 0/0 0/0
-HEAD-NERIDIONAL HEAD MELDS B2 F 60 HEAT EXCHANGERS (PRINARY SIDE) VOLUNETRIC N/A 0/0 0/0 0/0
-SHELL-TUBESHEET-TO-HEAD MELDS B2.70 HEAT EXCHANGERS (PRINARY SIDE) VOLUNETRIC N/A 0/0 0/0 OIO
-SHELL-LOi'(GITUDINAL MELDS B2.80 HEAT EXCHANGERS (PRINARY SIDE) VOLUNETRIC WIA 0/0 0/0 0/0
-SHELL-TUBESHEET-TO-SHELL MELDS
DATE'. 08/25/87 ST. LUCIE t(UCLEAR PLANT UNIT 1 PAGE:
REV IS IOHl I INSERVICE INSPECTION PLAtt FOR THE FIRST INTERVAL C(.ASS I SECTION XI SUt(NARY TABLE A CATEGORY B-D
- FULL PENETRATION MELDS OF NOZZLES KH REACTOR VESSEL (INSPECTION PROGRAN A) 4 OF CONPONENTS ASNE HUNGER OF RELIEF SCHEDULED/COt(PLETED SEC. Xi EXAN t(ETHOD SYSTE)( DESCRIPTION ZONE CONPONENTS RED. KST PER 2ND PFR 3RD PER ITEN 4 ITEN DESCRIPTION 83.90 REACTOR VESSEL-t(OZZLE-TO VOLUt(ETRIC RCS RPV 6 RR-4 2/0 0/0 4/0
-VESSEL MELDS 83, 100 REACTOR VESSEL-NOZZLE IHSIDE VOLUt(ETRKC RCS RPV 6 RR-4 2/0 0/0 4/0 RADIUS SECT IOH B3.110 PRESSURIZER-NOZZLE-TO-VESSEL VOLUNETRIC RCS 6 RR-5 2/0 2/0 2/0 MELDS
- 83. 120 PRESSURIZER-NOZZLE It(SIDE VOLUNETRIC RCS 6 RR-5 2/0 2/0 2/0 RADIUS SECTKDN 83.130 STEAN GENERATORS (PRIKARY VOLUMETRIC RCS SG-1A RR-3 2/0 1/0 0/0 SIDE)-NOZZLE-TO-VESSE(. MELDS II 83.130 STEAN GENERATORS (PRINARY VOLUNETRIC RCS SG-18 4 3 RR-3 0/0 I/O 2/0 SKDE)-NOZZLE-TO-VESSEL MELDS
- 83. 140 STEAN GENERATORS (PRINARY VOLU)(ETRIC RCS SG-1A RR-3 2/0 1/0 , 0/0 SIDE)-NOZZLE INSIDE RADIUS SECTION
,83. 140 STEAN GENERATORS (PRINARY VOLUt(ETRIC RCS SG-18 RR-3 0/0 1/0 2/0 SIDE)-NOZZLE INSIDE RADIUS SECTION
- 83. 150 HEAT EXCHANGERS (PRIHARY SiDE) VOLUNETRKC RCS N/A , 0/0 0/0 0/0
-NDZZLE-TO-VESSE(. MELDS 83, 160 HEAT EXCHANGERS (PRINARY SIDE) VOLUMETRIC RCS N/A 0/0 0/0 0/0
-NOZZLE INSIDE RADIUS SECTIOH
QATEl 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PASEl 5 REVISION: INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUNNARY TABLE A CATEGORY B-E - PRESSURE RETAININS PARTIAL PENETRATION NELDS IN VESSELS 4 OF CONPONENTS ASNE SEC. ZI NUNBER OF RELIEF SCHEDULED/CONPLETED ITEN DESCRIPTION EKAN NETHOD SYSTEN DESCRIPTION ZONE CONPONENTS REQ ~ 1ST PER 2ND PER 3RD PER ITEN II B4. 10 PARTIAL PLNETRATIOH MELOS VISUAL VT-2 RCS 0/0 0/0 0/0 B4. 11 VESSEL NOZZLES VISUAL VT-2 RCS N/A 0/0 0/0 0/0 B4. 12 CONTROL ROD DRIVE HOZZLES VISUAL VT-2 RCS CLOSURE HEAD 2 91 0/0 0/0 23/0 B4. 13 INSTRUNENTATION HOZZLES VISUAL VT-2 RCS CLOSURE HEAD 2 10 0/0 0/0 3/0 B4.20 PRESSURIZER-HEATER PENETRATION VISUAL VT-2 RCS PRESSURIZER 5 120 0/0 0/0 120/0 NELDS
DATE, '08/25/87 ST. LUCIE NUCLEAR PLANT UNIT I PAGE: 6 REVISIONS I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUNNARY TABLE A e CATEGORY B-F - PRESSURE RETAINING DISSINILAR METAL MELDS IN REACTOR VESSEL ASNE 4 OF CONPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/CONPLETED ITEN N ITEN DESCRIPI'ION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ. 1ST PER 2ND PER 3RD PER 85 10 REACTOR VESSEL-NOZZLE-TO-SAFE VOLUMETRIC RCS RPV 0/0 0/0 0/0 END BUTT MELDS >= 4 INCHES SURFACE NONINAL PIPE SIZE 85.20 REACTOR VESSEL-NOZZLE-TO-SAFE RCS RPV 0/0 0/0 0/0 END BUTT MELDS < 4 INCHES NOMINAL PIPE SIZE B5.20 REACTOR VESSEL-NOZZLE-TO-SAFE SURFACE RCS RPV 0/0 0/0 0/0 END 'BUTT MELDS < 4 INCHES NOMINAL PIPE SIZE 85.30 REACTOR VESSEL-NDZZLE-TO-SAFE SURFACE RCS RPV 0/0 0/0 0/0 END SOCKET MELDS 85.40 PRESSURIZER-NOZZLE-TO-SAFE END VOLUMETRIC RCS PRESSURE 1/0 1/0 1/0 BUTT MELDS >= 4 INCHES NOMINAL SURFACE e 85,50 PIPE SIZE PRESSURIZER-NOZZLE-TO-SAFE END SURFACE RCS PRESSURIZER 0/0 0/0 0/0 BUTT MELDS < 4 INCHES NOMINAL PIPE SIZE B5.60 PRESSURIZER-NOZZLE-TO-SAFE END SURFACE RCS PRESSURIZER 0/0 0/0 0/0 SOCKET MELDS 85.70 STEAN GENERATOR-NOZZLE-TO-SAFE SG-lA, SG-18 3,4 0 0/0 0/0 0/0 END BUTT MELDS >= 4 INCHES NONINAL PIPE SIZE 85 70 STEAN GENERATOR-NOZZLE-TO-SAFE VOLUMETRIC SG-IA,S6-18 3,4 0 0/0 0/0 0/0 END BUTT MELDS >"- 4 INCHES SURFACE NOMINAL PIPE SIZE B5 F 80 STEAN GENERATOR-NOZZLE-TO-SAFE SG-1A,S6-18 3,4 0 0/0 0/0 0/0 END BUTT MELDS < 4 INCHES NOMINAL PIPE SIZE 85 80 F STEAN GENERATOR-NOZZLE-TO-SAFE SURFACE SG-1A)SG-18 3,4 0 0/0 0/0 0/0 END BUTT MELDS < 4 INCHES NOMINAL PIPE SIZE 85.90 STEAN 6ENERATOR-NOZZLE-TO.SAFE SURFACE RCS SG-IA,S6-1B 3,4 0 0/0 0/0 0/0 END SOCKET MELDS
DATE: 08/25/87 ST ~ LUCIE NUCLcAR PLANT UNIT 1 PAGE: 7 INSERVICE iNSPECTION PLAN FOR THE FIRST INTERVAL t
REVISION:
CLASS 1 cECTION XI SUNNARY TABLE A CA'KEGORY 8-F - PRESSURE RETAINING DISSINKLAR METAL MELDS IN REACTOR VESSEL ASNE 4 OF CONPONENTS SEC. Xl tjUttBER OF RELIEF SCHEDULED/COHPLETED ITEN tt ITEN DESCRIPTION EXAM METHOD SYSTEN DESCRIPTION ZONE CONPOttENTS RED. IST PER 2ND PER 3RD PER B5. 100 HEAT EX'HANGERS-NOZZLE-TO-SAFE RCS N/A 0/0 0/0 0/0 END BUTT WELDS >= 4 INCHES NONINAL PKPE SIZE
- 85. 100 HEAT EXCHANGERS-NOZZLE-TO-SAFE SURFACE RCS N/A 0/0 0/0 0/0 END BUTT MELDS >= 4 INCHES NOMINAL PIPE SIZE
- 85. 110 HEAT EXCHANGERS-NOZZLE-TO-SAFE SURFACE RCS N/A 0/0 0/0 0/0 END BUTT MELDS < 4 IttCHES NONINAL PIPE SIZE
- 85. 110 HEAT EXCHANGERS-NOZZLE-TO-SAFE RCS N/A 0/0 0/0 0/0 END BUTT MELDS < 4 INCHcS NONINAL PIPE SIZE 85.120 HEAT EXCHANGERS-NOZZLE-TO-SAFE SURFACE RCS N/A 0/0 0/0 0/0 END SOCKET MELDS B5.130 PIPING-DISSINILAR NETAL BUTT VOLUNETRIC RCS NCP I/O 0/0 0/0 MELDS >= 4 INCHES NOMINAL PIPE SURFACE SIZE 85.130 PIPING-DISSINILAR NETAL BUTT VOLUMETRIC RCS NCP 0/0 0/0 1/0 MELDS >= 4 INCHES NOMINAL PIPE SURFACE SIZE 85.130 PIPING-DISSINILAR MEtAL BUTT VOLUHETRKC RCS ttCP 10 1/0 0/0 0/0 McLDS >= 4 IttCHES NONINAL PIPE SURFACE SIZE
- 85. 130 PIPING-DISSIttILAR METAL BUTT VOLUMETRIC RCS ttCP 0/0 0/0 1/0 WELDS >= 4 INCHES NONINAL PIPE SURFACE SIZE 85.130 PIPING-DISSINKLAR ttETAL BUTT VOLUttETRIC RCS tlCP 12 1/0 0/0 0/0 MELDS >= 4 INCHES NOtlINAL PIPE SURFACE SIZE 85.130 PIPING-DISSINIK.AR NETAL BUTT VOLUMETRIC RCS 0/0 1/0 0/0 NCP'ELDS
>= 4 INCHES.NONINAL PIPE SURFACE SIZE
08/25/87 ~ ST. LUCIE NUCLEAR PLANT UNIT I PAGEOS 8 DATE:
REVISION: ! INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUHtlARY TABLE A CAIEGORY 8-F - PRESSURE RETAININ6 DISSIMILAR ttETAL MELDS IN REACTOR VESSEL AGEE 4 OF COMPONENTS SEC Xl NUttBER OF RELIEF SCHEDULED/COMPLETED ITEN 4 ITEi! DESCRIPTION EXAti METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ. !ST PER 2ND PER 3RD PER 85.130 PIPIN6-DISSINILAR NETAL BUTT VOLUMETRIC RCS i1CP 1/0 0/0 0/0 MELDS >= 4 INCHES NONINAL PIPE SURFACE SIZE
- 85. 130 ?IPING-OISSKNILAR HETAL BUTT VOLUtlETRIC RCS MCP 15 0/0 1/0 0/0 MELOS >= 4 INCHES NOHIttAL PIPE SURFACE SIZE 85.130 PIP IN6-DISSINILAR METAL BUTT VOLUMETRIC RCS SURGE LINE 16 1/0 I/O 0/0 MELOS >- "4 INCHES NOMINAL PIPE SURFACE SIZE 85,130 PIPIttG-DISSIHILAR METAL BUTT VOLUttETRIC RCS Sl NOZZLE 21 1/0 0/0 0/0 MELOS >= 4 INCHES NOMINAL PIPE SURFACE SIZE 85.130 PKPItiG-DISSKttILAR ttETAL BUTT VOLUtlETRIC RCS Sl ttOZZLE 1/0 0/0 0/0 MELOS >= 4 INCHES NOMINAL PIPE SURFACE SIZE 85.130 PIPING-DISSIHILAR ttETAL BUTT VOLUHETRIC RCS SI NOZZLE 23 1/0 0/0 0/0 MELDS >= 4 INCHES NOHINAL PIPE SURFACE SIZE
- 85. 130 P IP ING-DISS INILAR NETAL BUTT VOLUMETRIC RCS Sl NOZZLE 24 0/0 0/0 1/0 MELDS >= 4 INCHES NOHINAL PIPE SURFACE SIZE .
- 85. 130 PIPING-DISSIMILAR ttETAL BUTT RCS PR. SPRAY 25 2/0 0/0 MELDS >- "4 INCHES NONINAL PIPE SIZE 2/0'5.130 P IP IN6-DISS IHILAR HETAL BUTT RCS 6 ~ D ~ C, 28 1/0 0/0 0/0 ME!.DS >= 4 INCHES NONINAL PIPE SIZE 85 130 PIPING-DISSINILAR HETAL BUTT RCS S AD.C. 29 1/0 0/0 0/0 MELDS >= 4 INCHES NONKNAL PIPE SIZE 85.130 PIPING-DISSKHILAR METAL BUTT RCS PR ~ RELIEF 38 0/0 0/0 1/0 MELDS >= 4 INCHES NOMIttAL PIPE SIZE
ST. LUCIE NUCLEAR PLANT UNIT I PAGE: 9 OATEN'8/25/87 REV IS ION: I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUNttARY TABLE A e CATEGORY 8-F - PRESSURE RETAINING DISSINILAR ttETAL MELDS IN REACTOR VESSEL 4 OF COttPOttENTS ASHE NUttBER OF RELIEF SCHEDULED/COMPLETED SEC. Xl EXAM ttETHOD SYSTEN DESCRIPTION ZONE COttPONENTS REQ. 1ST PER 2ND PER 3RD PER ITEN tt ITEN DESCRIPTION
- 85. 140 PIP lttG-DISSIMILAR ttETAL BUTT SURFACE RCS NCP OIO OIO 1/0 MELDS < 4 INCHES ttONINAL PIPE SIZE 85.140 PIPING-DISSIMILAR ttETAL BUTT SURFACE RCS PRESSURE SPRAY 26 0/0 1/0 0/0 MELDS < 4 INCHES ttONINAL PIPE SIZE
- 85. 140 PIPING-DISSIMILAR NETAL BUTT SURFACE RCS PRESSURE SPRAY 27 0/0 0/0 I/O MELDS < 4 INCHES NOMINAL PIPE SIZE 0/0 0/0 . 1/0 85.140 PIPING-DISSINILAR NE'TAL BUTT SURFACE RCS CHARGING MELOS < 4 INCHES NOMINAL PIPE SIZE 85.140 PIPING-DISSittILAR METAL BUTT SURFACE RCS CHARGING 0/0 . I/O 0/0 MELDS < 4 INCHES NONINAL PIPE SIZE PIPItiB-DISSIIIILAR ttETAL SURFACE RCS DRAIN 1/0 OIO 0/0 85.140 BUTT MELDS < 4 INCHES NQNINAL PIPE SIZE PIPING-DISSINILAR ttETAL BUTT SURFACE RCS DRAIN 0/0 1/0 0/0 85,140 MELOS < 4 INCHES NONlttAL PIPE SIZE SURFACE RCS DRAltt 35 1/0 0/0 0/0
- 85. 140 P IP ING-DISS INILAR METAL BUTT MELDS < 4 INCHES NONINAL PIPE SIZE RCS DRAIN 0/0 0/0 1/0 85.140 P IP I WG-DISS INILAR METAL BUTT SURFACE MELDS < 4 INCHES NONINAL PIPE SIZE 85.140 PIPING-DISSIMILAR ttETAL BUTT SURFACE RCS PRESSURE RELIEF 38 I/0 0/0 0/0 MELDS < 4 INCHES NONINAL PIPE SIZE PIPING-DISSIMILAR ttETAL RCS N/A 0/0 0/0 0/0
- 85. 150 SOCKET MELDS
M 08/25/87 ST LUCIE NUCLEAR PLANT UNIT 1 PAGE: 10 DATE: ~
REV IS IQNl INSERVICE INSPECTION PLAit FOR THE FIRST INTERVAL CLASS I SECTION XI SUttMARY TABLE A CATEGORY 8-6 PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMETER IN REACTOR VESSEL 4 OF COMPONENTS ASNE SEC. XI NUMBER OF RELIEF SCHEDULED/CQNPLETED ITEt1 4 ITEN DESCRIPTION EXAN ttETHOD SYSTEN DESCRIPTION ZONE CONPONENTS REQ. IST PER 2ND PER 3RD PER Bb. 10 REACTOR VESSEL-CLOSURE HEAD SURFACE RCS RPV 18/0 18/0 !8/0 NUTS 86 '0 REACTOR VESSEL CLOSURE STUDS) VOLUNETRIC RCS RPV 0/0 0/0 0/0 IN PLACE 86.30 REACTOR VESSEL-CLOSURE STUDS, VOLUNETRIC RCS RPV 18/0 18/0 18/0 WHEN REMOVED SURFACE 86.40 REACTOR VESSEL-THREADS IN VOLUNETRIC RCS RPV 18/0 18/0 18/0 FLANGE
>>~>> NOTE lEXANINE I/3 IST PERIOD, I/3 2t(D PERIOD) I/3 3RD PERIOD 86.50 REACTOR VESSEL-CLOSURE MASltERS VISUAL VT-1 RCS RPV 18/0 18/0 18/0
) BUSHINGS 86,60 PRESSURIZER-BOLTS AND STUDS VOLUMETRIC RCS PRESSURE 0/0 0/0 0/0 86.70 PRESSURIZER-FLANGE SURFACE, VISUAL VT-I RCS PRESSURE 0/0 0/0 0/0 MHEN CONNECTION DISASSEMBLE)D 86 ~ 80 PRESSURIZER NUTS) BUSHINGS) VISUAL VT I RCS PRESSURE 0/0 0/0 0/0 AND MASHERS 86.90 STEAtt GENERATORS-BOLTS AND VOLUMETRIC SG-1A,SG-18 3,4 0 0/0 0/0 0/0 STUDS
- 86. 100 STEAN GENERATORS-FLANGE VISUAL VT-1 RCS SG-IA,SG-IB 3,4 0 0/0 0/0 0/0 SURFACE, MHEN COttNECTION DISASSENBLEO
- 86. 120 HEAT EXCHANGERS-BOLTS AND VOLUMETRIC RCS N/A 0/0 0/0 0/0 STUDS 86.130 HEAT EXCHAttGERS-FLANGE SURFACE VISUAL VT-I RCS N/A 0/0 0/0 0/0
, MHEN CONtiECTIQN DISASSEMBLED Bb. 140 HEAT EXCHANGERS-NUTS, BUSHINGS VISUAL Vl'-1 RCS N/A 0/0 0/0 0/0
) AND MASHERS
ST. LUCIE NUCLEAR PLANT UNIT PAGE: 11 DATE: 08/25/87 1 REVISIONS 1 INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI
SUMMARY
TABLE A 4 OF CONPONENTS ASNE SEC. XI NUMBER OF RFLIEF SCHEDULED/COMPLETED EXAM METHOD SYSTEN DESCRIPTION ZONE COMPONENTS REQ. IST PER 2ND PER 3RD PER ITEN 4 ITEN DESCRIPTION B6.150 PIPING-BOLTS AND STUDS VOLUMETRIC RCS N/A 0/0 0/0 0/0 86.160 PIPIttG-FLANGE SURFACE, MHEtt VISUAL VT-I RCS N/A 0/0 0/0 0/0 CONNECTION DISASSEMBLED B6.170 PIPltiG-NUTS, BUSHINGS, AttD VISUAL VT-1 RCS N/A OIO 0/0 0/0 MASHERS 86.180 PUNPS-BOLTS AtiD STUDS VOI.UMETRIC RCS RCP" 1A1 17 16 16/0 0/0 0/0
- 86. 180 PU11PS"BOLTS AND STUDS VOLUNETRIC RCS RCP-1A2 18 16 0/0 0/0 16/0 B6.180 PUNPS-BOLTS AND STUDS VOLUMETRIC RCS RCP-181 19 16 0/0 16/0 0/0 PUMPS-BOLTS AND STUDS VOLUNETRIC RCS RCP-lB2 20 16 0/0 0/0 16/0 B6. 180 86 190 PUMPS FLANGE SURFACEs WHEN VISUAL VT-1 RCS RCP-1AI 17 RR-7 0/0 0/0 OIO CONNECTION DISASSEMBLED aaaaa NOTE CSEE RELIEF REQUEST PUNPS-FLANGE SURFACE, MHEN VISUAL VT-1 RCS RCP-1A2 18 RR-7 0/0 0/0 0/0 Bb. 190 CONNEC'CION DISASSENBLED
%%%%a NOTE :SEE RELIEF REQUEST PUNPS-FLANGE SURFACE, 'AHEN VISUAL VT-1 RCS RCP-181 19 1 RR-7 0/0 0/0 0/0 Bb. 190 CONNECTION OISASSENBLED I+awa NOTE:SEE RELIEF REQUEST Bb ~ 190 PUMPS-FLANGE SURFACE, NHEN VISUAL VT-I RCS RCP-182 20 I RR 7 0/0 0/0 0/0 COtiNECT ION DISASSENBLED
~fwa+ NOTE CSEE RELIEF REQUEST 86.200 .PUMPS-tiUTS, BUSHIN6S, AND VISUAL VT-1.RCS RCP-lAI 17 16 16/0 0/0 0/0 NASHERS 86.200 PUMPS-NUTSs BUSHIN6S, AND VISUAL VT-I RCS RCP-IA2 18 16 0/0 0/0 16/0 NASHERS PUMPS-NUTS, BUSHltiGS, AND ViSUAL VT-I RCS RCP-181 19 16 0/0 16/0 0/0 Bb 200 NASHERS VISUAL VT-I RCS RCP-182 20 16 0/0 OIO 16/0 86.200 PUMPS-tiUTSs BUSHINGS, AND MASHERS
ST. LUCIE tiUCLEAR PLANT UNIT 1 PAGE: 12 t
INSERVICE INSPECTION PLAN FOR THE FIRST ItiTERVAL CLASS 1 SECTION XI SUttttARY TABLE A CATEGORY B-G-1 - PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES Iti DIANETER IN REACTOR VESSEL ASNE 4 OF COilPONENTS SEC ~ Xl NUNBER OF RELIEF SCHEDULED/CDHPLETED ITEN 4 ITEtt DESCRIPTION EXAN tiETHOD SYSTEN DESCRIPTION ZONE COttPONENTS RED. 1ST PER 2ND PER 3RD PER B6.210 VALVES-BOLTS AND STUDS VOLUNETRIC RCS N/A 0/0 0/0 0/0 Bb.220 VALVES-FLANGE SURFACE, NHEN VISUAL VT-1 RCS ti/A 0/0 0/0 0/0 CONNECTION DISASSEHBLED 86.230 VALVES-NUTS, BUSHINGS, AND VISUAL VT-1 RCS N/A 0/0 0/0 0/0 USHERS
ST. LUCIE ttUCLEAR PLANT UttlT PAGE: 13 DATE: 08/25/87 1 REVISION: INSERVICE IHSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI
SUMMARY
TABLE A
,CATEGORY B-G"2 - PRESSURE RETAIHING BOLTlttG, 2 INCHES AND LESS IN DIAMETER IN REACTOR VESSEL D OF COMPONENTS ASME SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRiPTION ZONE COMPONENTS RED. 1ST PER 2ttD PER 3RD PER 87 '0 REACTOR VESSEL-BOLTS, STUDS) VISUAL VT-1 RCS RPV 0/0 0/0 0/0 AND ttUTS 87.20 PRESSURIZER-BOLTS, STUDS, AND VISUAL VT-I RCS PRESSURE 5 20 7/0 7/0 6/0 NUTS
%%+a+ NOTE :NUMBER OF ITEMS "- 20 HUTS, 20 STUDS. EXAMINE 1/3 1ST PERIOD, 1/3 2HD PERIOD, 1/3 RD PERIOD.
87.30 S'TEAM GENERATORS-BO'S, STUDS, VISUAL VT-I RCS PRESSURE-1A 40 20/0 0/0 20/0 AND HUTS 4ft~4 NOTE ,'NUMBER OF ITEtlS = 40 ttUTS, 40 STUDS. EXAMlttE 20 EACH 1ST PERIOD, 20 EACH 3RD PERIDD.
87,30 STEAM GENERATORS-BOLTS, STUDS, VISUAL VT-I RCS PRESSURE-18 4 40 0/0 20/0 20/0 AND NUTS a~a+~ NOTE ;NUMBER OF ITEMS = 40 t<UTS, 40 STUDS. EXAMINE 20 EACH 2HD PERIOD, 20 EACH 3RD PERIOD.
87.40 HEAT EXCHAHGERS-BOLTS, STUDS, VISUAL VT-1 RCS H/A 40 13/0 13/0 14/0 AND HUTS a%%%% NOTE lNUMBER OF ITEMS = 40 NUTS, 40 STUDS. EXAMINE 1/3 IST PERIOD, I/3 2ND PERIOD, 1/3 3RD PERIOD 87.50 PIPING BOLTSi STUDSi AND NUTS VISUAL VT 1 RCS 33 2 1/0 I/O 0/0 aaeaa NOTE lttUMBER OF ITEMS ARE FLANGES.
87.50 PIPIttG-BOLTS, STUDS, AHD NUTS VISUAL VT-1 RCS 0/0 1/0 '/0
%%%%% NOTE lNUMBER OF ITEMS ARE FLANGES.
PIPING-BOLTS, STUDS, AND NUTS VISUAL VT-1 RCS 0/0 0/0 1/0 87o50
%%alt NOTE ;NUMBER OF ITEMS ARE FLAN6ES.
VISUAL VT I 1/0 0/0 0/0 87.50 PIPING BOLTS) STUDS) AND NUTS RCS tweak+ NOTE ;NUMBER OF ITEMS ARE FLAN6ES ~
VISUAL VT-I RCS 0/0 1/0 0/0 87.50 PIPING-BOLTS, STUDS, AND NUTS wat%w NOTE :NUMBER OF ITEMS ARE FLAH6ES.
87.60 PUMPS-BOLTS, STUDS, AND HUTS VISUAL VT-1 RCS 17 1/0 i/0 1/0
~~ ~+ NOTE lEXAMINE I/3 1ST PERIODS 1/3 2ND PERIOOi I/3 3RD PERIOD AND NUTS VISUAL VT RCS 18 1/0 1/0 1/0 87 ~ 60 PUMPS BOLTS> STUDS) 1
%%%a+ NOTE:EXAMINE 1/3 1ST PERIOD, 1/3 2ND PERiOD, 1/3 3RD PERIOD VISUAL VT-1 RCS 19 1/0 1/0 1/0 87,60 PUMPS-BOLTS, STUDS) AND NUTS a%aaa NOTE :EXAMIHE 1/3 1ST PERIOD, 1/3 2ND PERIOD, 1/3 3RD PERIOD
08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 14 DATE:
t REVISIOH: INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS I SECTION Xl SUNNARY TABLE A CATEGORY 8-8-2 - PRESSURE RETAIHINB BOLTINB, 2 INCHES AHD LESS IN DIANETER IN REACTOR VESSEL AStiE 4 GF CONPOttEtlTS SEC ~ Xl NUNBER OF RELIEF SCHEDULED/CONPLETED
!TEN DESCRIPTION EXAti NETHOD SYSTEN DESCRIPTION ZONE CONPOHENTS RED 1ST PER 2ND PER 3RD PER ITEtt 4 87.60 PUNPS-BOLTS, STUDS, AND HUTS VISUAL VT"1 RCS 20 I/O I/O 1/0
<%w<+ NOTE:EXANltiE I/3 1ST PERIOD, I/3 2ND PERIOD, I/3 3RD PERIOD 87.70 VALVES-BOLTS, STUDSs AHD NUTS VISUAL VT-1 RCS 12'ALVES 1/0 I/O I/O
>>>>+ NOTE 'EXANINE 1/3 IST PERIODs I/3 2ND PERIODs 1/3 3RD PERIODS 87 ~ 70 VALVES BOLTS) STUDS) AND NUTS VISUAL VT 1 RCS 10 VALVES I/O 1/0 1/0
%>><a NOTE '.EXANIHE I/3 IST PERIOD) 1/3 2ND PERIODs 1/3 3RD PERIOD.
87.70 VALVES-BOLTSs STUDS, AtlD NUTS VISUAL VT-1 RCS 6'ALVES I/O I/O 1/0
~i~~~ NOTE '.EXANINE I/3 1ST PERIODs 1/3 2HD PERIOD, 1/3 3RD PERIODS 87.70 VAt.VES-BOLTS, STUDS, AND NUTS VISUAL VT-I RCS 3'ALVES 1/0 I/O I/O w44fw NOTE:EXANINE 1/3 IST PERIOD, 1/3 2ND PERIODs 1/3 3RD PERIOD.
- 87. 70 VALVES-BOLTS) STUDS) AND NUl'S VISUAL VT-1 RCS 2.5'ALVES I/O 1/0 I/O
~w4~w NOTE ."EXANIHE 1/3 1ST PER!OD, 1/3 2ND PERIOD, 1/3 3RD PERIOD.
87 '0 VALVES BOLTS) STUDSs AHD NUTS VISUAL VT 1 RCS 2 VALVES 25 1/0 1/0 1/0
%law% NOTE '.EXANIHE 1/3 IST PERIOD, 1/3 2HD PERIGD, 1/3 3RD PERIGD.
B7.80 CRD HOUSINGS-BOLTSs STUDSs AND VISUAI. VT-1 RCS tt/A 0/0 0/0 0/0 NUTS
DATE.'8/25/87 ST. LUCIE NUCLEAR PLANT UNIT I PAGE: 15 REVISIONS 1 INSERVICE INSPECTION PLAN FOR THE FIRST IttTERVAL CLASS 1 SECTION Xl
SUMMARY
TABLE A CATEGORY B-H
- INTEGRAt. ATTACHMENTS FOR REACTOR VESSEL ASME 4 OF COMPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM tt ITEM DESCRIPTION EXA}1 METHOD SYSTEM DESCRIPTION ZONE COMPONENTS RED, IST PER 2ND PER 3RD PER BB. 10 REACTOR VESSEL-INTEGRALLY VOLUMETRIC RCS N/A PER 88.10<1) 0/0 0/0 0/0 MELDED ATTACHMENTS OR SURFACE B8.20 PRESSURIZER-INTEGRALLY NELDED VOLUMETRIC RCS PRESSURE 5 I/O 1/0 1/0 ATTACHMEttTS OR SURFACE
%4ff% NOTE :EXAMINE 1/3 IST PERIOD, 1/3 2ND PERIOD) 1/3 3RD PERIOD 88,30 STEAM GENERATORS-INTEGRALLY VOLUMETRIC RCS 1/0 I/O 1/0 NELDED ATTACHMENTS OR SURFACE
+a>%% NOTE lEXAMittE 1/3 IST PERIOD, 1/3 2ND PERIOD) 1/3 3RD PERIOD B8,30 STEAM GENERATORS-INTEGRAI.LY VOLUMETRIC RCS 0/0 0/0 0/0
'AELDED ATTACHMENTS OR SURFACE 88.40 HEAT EXCHAttGERS-INTEGRALLY VOLUMETRIC RCS N/A 0/0 0/0 0/0 NELOED ATTACHMENTS OR SURFACE
ST. LUCIE ttUCLEAR PLANT UNIT 1 PAGE: 16 DATEl 08/25/87 IHSERVICE INSPECTION PLAN FOR THE FIRST IHTERVAL t
REVISION: 1 CLASS 1 SECTION XI SUNtlARY TABLE A CATFGORY 8-J - PRESSURE RETAINING MELDS IN PIPING 0 OF CONPONENTS ASNE NUMBER OF RELIEF SCHEDULED/COtlPLETED SEC. XI ITEtl DESCRIPTION EXAM tlETHDD SYSTEM DESCRIPTION ZONE COtlPONENTS REQ. IST PER 2ND PER 3RD PER ITEN 4
- 89. 11 CIRCUMFERENTIAL MELDS VOLUtlETRIC RCS ttAltl COOLANT 42'-NPS 10 RR-6 1/0 1/0 2/0 SURFACE IRCUtlFERENT IAL MELDS VOLUllETRIC RCS HAIN COOl.ANT 30'-HPS 44 RR-6 5/0 4/0 4/0 89 ~ 11 C SURFACE
- 89. 11 CIRCUNFERENTIAL MELDS VOLUMETRIC RCS PIPING t 12'-NPS 19 5/0 5/0 5/0 SURFACE DUE TO EXCEEDING STRESS CRITERIA OR ARE TERMINAL ENDS PER TABLES
- NOTE 1.
<<<<<<<<<< NOTE :NUllBER TO EXAtlINEl GREATER THAH 25X VOLUMETRIC RCS PIP Itt6:10"-NPS 0/0 0/0 1/0
- 89. 11 CIRCUtlFERENTIAL MELDS SURFACE
- 89. 11 CIRCUtlFEREN'AXIAL MELDS VOLUMETRIC RCS PIPING-NPS 19 2/0 2/0 2/0 SURFACE
<<<<<<<<<< EXAttlttEl GREATER THAN 25X DUE TO EXCEEDIH6 STRESS CRITERIA OR ARE TERtllNAL ENDS PER TABLES
- NOTE 1.
NDTE :NUMBER TO CIRCUNFERENTIAL MELDS VOLUMETRIC SI PIPING'2'-tlPS 49 16/0 16/0 17/0 SURFACE TERNIHAL ENDS PER TABLES
- NOTE 1.
<<<<<<<<<< NOTE :NUMBER TO EXANINEl GREATER THAN 25X DUE TO EXCEEDING STRESS CRITERIA OR ARE
- 89. 11 C IRCUtlFERENT IAL MELDS VOLUMETRIC Sl PIPING'0'"tlPS 1/0 1/0 2/0 SURFACE CIRCUtlFEREHT IAL MELDS VOLUtlETRIC Sl It(6: 6'-NPS 162 'Q/Q 5Q/0 62/0 89.11 PIP SURFACE
<<<<<<<<<< tlOTE ;NUMBER TO EXAttINE! GREATER THAN 25X DUE TO EXCEEDING STRESS CRITERIA OR ARE TERMINAL ENDS PFR TABLES NOTE 1
- 89. 12 LONGITUDINAL MELDS VOLUNETRIC RCS HAIN COOLANT 42'-HPS 2/0 2/0 4/0 SURFACE 89 ~ 12 LONGITUDINAL MELDS VOLUNETRIC RCS tlAIN COOLANT ZO'-NPS 56 6/0 6/0 8/0 SURFACE 89 ~ 21 C IRCUNFERENT IAL MELDS SURFACE RCS P IP INDE 3'-HPS 47 4/0 4/0 4/0'9.21 CIRCUttFERENTIAL MELDS . SURFACE RCS PIPING'.5'-NPS 19 4/0 4/0 6/0
<<<<<<<<<<NO'TE tNUt}BER TO EXANIHEl GREATER THAN 25X DUE TO EXCEEDIHG STRESS CRITERIA OR ARE TERMINAL EttDS PER TABLES - NOTE 1.
- 89. 21 CIRCUMFERENTIAL MELDS SURFACE RCS PIPING: 2'-NPS 1/0 1/0 1/0 B9. 21 CIRCUMFERENTIAL MELDS SURFACE CH PIPING: 2'-NPS 4 1/0 1/0 2/0
PAG"": 17 DATE'. 08/25/87 ST. LUCIE tiUCLEAR PLANT UtilT 1 REVISIOtt INSERVICE INSPECTION PLAN FOR TRE FIRST INTERVAL C~ASS I SECTIOti Xl SuttttARY TABLE A CATEGORY 8-J - PRESSURE RETAINING MELOS IN PIPING'SttE 0 OF COttPOHEHTS SEC, XI NUMBER OF RELIEF SCHEDULED/CottPLETED ITEtt 4 ITEN DESCRIPTIOH EXAtt METHOD SYSTEit DESCRIPTIOH ZONE COttPONENTS RED. 1ST PER 2HD PER 3RD PER 89.21 CIRCUttFERENTIAL MELDS SURFACE Sl PIPING: 3'-NPS 20 6/0 6/0 8/0 m+www ttOTE :NUMBER TO EXAttIHE: GREATER THAtt 25X DUE TO EXCEEDING STRESS CRITERIA OR ARE TERMINAL ENDS PER TABLES
- NOTE 1 ~
B9. 21 C I RCUHFERENT I AL MELDS SURFACE S I PIP IttG! 2'-HPS 1/0 1/0 2/0 B9.22 89 31 89.32 LOHSII'UDIHAt. MELDS NOMINAL PIPE SIZE HOMINAL PIPE SIZE <4
)= 4 IH IH.
SURFACE RCS 2'5 RCSrSI N/A 12'CS 0/0 0/0 0/0 0/0 I/O I/O 0/0 1/0 1/0 2'9 2'CS 89.32 NOttINAL PIPE SIZE <4 IH. 0/0 I/O 0/0 3'l B9.32 ttOttltiAL PIPE SIZE <4 IH. 0/0 0/0 I/O B9.40 SOCKET MELDS SURFACE RC 6/0 6/0 6/0 e 8/0 8/0 9/0 2'URFACE 8'9,40 SOCKET MELDS CH 97
DATEt 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 ?AGE: 18 REVISIONS INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUtttlARY TABLE A ASHE 5 OF COttPOttEMTS SEC. XI NUttBER OF RELIEF SCHEDULED/COti?LETED ITEN 4 ITEN DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ. 1ST PER 2ND PER 3RD PER 810, 10 P IP ING-INTEGRALLY NELDED VOLUMETRIC Sl 6'-SI-110 1/0 1/0 2/0 ATTACHttENTS SURFACE ttOTE:NUMBER OF CONPOttENTS: LUGS, LOCATED AT A PENETRATION.
810.10 PIPING-IMTEGRALI.Y NELDED VDLUttETRIC Sl 6'-Sl-111 0/0 1/0 1/0 ATTACHNENTS SURFACE mwa%f ttOTE,'NUMBER OF COMPONENTS: LUGS, LOCATED AT A PENETRATION.
810. 10 PIPING-INTEGRALLY NELDED VOLUtlETRIC Sl 6'"Sl-112 1/0 I/O 0/0 ATTACHNENTS SURFACE
%aw<w NOTE cNUttBER OF CONPONENTS'. LUGS, LOCATED AT A PENETRATION.
810.10 PIPING" INTEGRALLY NELDED VOLUMETRIC Sl 6"-S1-113 1/0 0/0 I/O ATTACHNENTS SURFACE t+a+a NOTE .NUMBER OF CONPONENTS ~ LUGS, LOCATED AT A PENETRATIOM.
t B10.20 810,20 PUMPS-INTEGRALLY NELDED ATTACHMENTS
~w%w+ NOTE lNUtlBER OF COMPONENTS:
PUttPS-INTEGRALLY NELDED ATTACHNctiTS
. VOLUMETRIC SURFACE LUGS VOLUMETRIC SURFACE RCP RCP IAI IA2 4/0 0/0 0/0 0/0 0/0 4/0
~law+ NOTE :NUttBER OF COttPONENTSl LUGS 810,20 PUNPS-INTEGRALLY NELDED VOLUMETRIC RCP 181 0/0 4/0 0/0 ATTACHMENTS SURFACE
%wwt+ NOTE lNUttBER OF COttPONENTS! LUGS 810.20 PUttPS-INTEGRALLY NELDED VOLUMETRIC RCP 183 0/0 0/0 4/0 ATTACHMENTS SURFACE
<wwwa MOTE :NUMBER OF CONPONENTS: LUGS 810.30 'VALVES-INTEGRALLY NELDED VOLUMETRIC RCS N/A 0/0 0/0 0/0 ATTACHNENTS SURFACE
REVISION.'T, OATEN'8/25/8/ LUCIE NUCLFAR PLANT UNIT INSERVICE INSPECTION >LAN FOR TOE CLASS 1 SECTION XI SUNNARY 1
FIRST INTERVAL PAGE: 19 TABLE A CATEGORY 8-L-I - PRESSURE RETAINING MELDS IN PUNP CASING ASNE 4 OF CONPONENTS SEC. XI NUNBER OF RELIEF SCHEDULED/CONPLETED ITEN 0 ITEN DESCRIPTION EXAN NETHOD SYSTEN DESCRIPTION ZONE CONPONENTS REQ 1ST PER 2ND PER 3RD PER 812 ~ 10 PUNPS-PUNP CASING WELDS . VOLUNETRIC RCS RCP-IA1, lA2,181,182 4 RR-7 0/0 0/0 0/0 wf>%4 NOTE:SEE RELIEF REQUEST.
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 20 INSERVICE INSPECTION PLAtt FOR THE FIRST INTERVAL t
REV I SION l I CLASS I SECTION Xl SUttNARY TABLE A CATEGORY B-L PUMP CASINGS 0 OF CONPOttENTS ASNE SEC. Xl NUttGER OF RELIEF SCHEDULED/CONPLETED EXAtt HETHOD SYSTEN DESCRIPTION ZONE COttPONEHTS REQ 1ST PER 2ND PER 3RD PER ITEtl tt ITEN DESCRIPTION B12. 20 PUHPS-PUtlP CASINGS VT-3 RCS RCP-1A1,1A2,1B1,1B2 4 RR-7 0/0 0/0 0/0
>~>~> NOTE :SEE RELIEF REQUEST.
DATEt 08/25/87 ST, LUCIE ttUCLEAR PLANT UNIT 1 PAGE: 21 REVISION: I INSERVICE INSPECTION PLAN FOR THE FIRST IttTERVAL CLASS I SECTION II
SUMMARY
'ABLE A CATEGORY B-N-I - PRESSURE RETAINING MELDS IN VALVE BODIES ASifE 0 OF COMPONENTS SEC. TI NUMBER OF R'ELIEF SCHEDULED/COMPLETED ITEN 4 ITEN DESCRIPTION EXAM ttETHOD SYSTEN DESCRIPTION ZONE COMPONENTS RED. IST PER 2ND PER 3RD PER 812,30 VALVES-VALVE BODY MELDS ( 4 SURFACE RCS,SI NONE 0/0 OIO 0/0 INCHES ttDNINAL PIPE SIZE 812,40 VALVES-VALVE BODY MELDS >= 4 VOLUttETRIC RCS)SI NONE 0/0 OIO 0/0 INCHES NONINAL PIPE SIZE
DATE: Oa/25/87 ST, LUCIE NUCLEAR PLANT UNiT I PAGE: 22 REVISION! 1 INSERVICE INSPECT'ION PLAlt FOR THE FIRST INTERVAL CLASS I SECTIOtl XI
SUMMARY
TABLE A CATEGORY 8-M-2
- VALVE BODIES 0 OF COttPOtlEtlTS ASME SEC. XI tlUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTION EXAM METHOD SYS'IEtt DESCRIPTION ZONE COMPONENTS RED. IST PER 2ND PER 3RD PER B12.50 VALVES-VALVE BODIES EXCEEDING INTERN VT-3 RCS,SI 12'ALVES 8 RR 8 0/0 0/0 0/0 4 INCHES NOMINAL PIPE SIZE
%+e+w NOTE :NUMBER TO EXAMINE! EXAMINE NHEN DISASSEMBLED.
812. 50 VALVES-VALVE BODIES EXCEEDING INTERtl VT-3 RCS,SI 10'ALVES 4 RR-8 0/0 0/0 0/0 4 INCHES ttOMINAL PIPE SIZE
%%saw NOTE :NUMBER I'0 EXAMIttE: EXAMINE NHEN DISASSEMBLED.
B12.50 VALVES-VALVE BODIES EXCEEDING INTERN VT-3 RCS,SI 6'ALVES 8 RR-8 0/0 0/0 0/0 4 INCHES NOMINAL P!PE SIZE
+<a<w tlDTE !NUMBER TO EXAMINE! EXAMINE MHEN DISASSEMBLED.
DATE: 08/25/B7 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 23 t
REV IS ION t IttSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS I SECTION Xl SUNttARY TABLE A CATEGORY B-N-I - INTERIOR OF REACTOR VESSEL ASttE I OF CONPDNEttTS SEC. XI NUNBER OF RELIEF SCHEDULED/CONPL'ETED EXAti ttETHOD SYSTEtt DESCRIPTION XONE CONPONENTS RED, 1S'I PER 2ND PER 3RD PER ITEtt tt ITEtt DESCRIPTION B13.10A REACTOR VESSEL-VESSEL INTERIOR VISUAL VT-3 RCS RPV 1/0 1/0 1/0 www4w NOTE lEXAttlttE ACCESSIBLE AREAS EACH PERIOD.
B13. 10B REACTOR VESSEL - CDRE BARREL VISUAL VT-3 RCS RPV 1/0 I /0 I/0 t%wia NOTE ;EXAttINE ACCESSIBLE AREAS EACH PERIOD.
DATE:
REV IS IOtt.'I 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS I SECTION Xl SUN))ARY TABLE A PAGE: 24 CATEGORY B-N-2 " INTEGRALLY MELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO BMR VESSEL AS)tE 0 OF COMPONENTS SEC. Xl NUMBER OF RELIEF SCHEDULED/COMPLETED ITEN 4 ITEN DESCRIPTION EXA)t METHOD SYSTEtt DESCRIPTION ZONE COMPONENTS REQ. IST PER 2ND PER 3RD PER 813,50 REACTOR VESSEL (PMR)-INTERIOR VISUAL VT-I RCS RPV 0/0 0/0 0/0 ATTACH)(ENTS MITHIN BELTLINE REGION afaaw NOTE:EXAMINE AL). MELDS EACH INTERVAL.
B)3.60 REACTOR VESSEL (PMR)-INTERIOR VISUAL VT-3 RCS RPV 0/0 0/0 0/0 ATTACH)(ENTS BEYOND BELTLINE REGION w>w~w NOTE '.EXAt)INE ALL MELDS EACH INTERVAL.
DATE. 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT I REVISION: I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS I SECTION XI SUtNARY TABLE A e CATEGORY 8-N-3 - RENOVABLE CORE SUPPORT STRUCTURES IN 8'AR VESSEL ASNE 4 OF CG)(PONENTS SEC. Xl ttUt(BER OF RELIEF SCHEDULED/COt(PLETED ITEt( 4 ITE)( DESCRIPTION EXA)( NETHOD SYSTEN DESCRIPI'ION ZONE CONPONENTS REO. lST PER 2ttD PER 3RD PER 813.70A REACTOR VESSEL (PNR)-CORE VISUAL VT-3 RCS RPV 0/0 0/0 0/0 dI SUPPORT STRUCTURE
<>,t(OTE;EXA))lt(E SURFACES EACH INTERVAL, B(5.70B REACTOR VESSEL (P)(R)-CORE VISUAL VT-3 RCS RPV 0/0 0/0 0/0 BARREL a+wtw NOTE HEXA)(INE 100X UPON REt(OVAL FROH RPV
ST. LUCIE NUCLEAR j'LANT UNIT I PAGE: 26 DATE: 08i 25/87
' INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL REVISION:
CLASS I SECTION XI
SUMMARY
TABLE A CATEGORY B-0 - PRESSURE RETAINING NELDS IN CONTROL ROD HOUSINGS 4 OF COMPONENTS ASHE NUMBER OF RELIEF SCHEDULED/COMPLETED SEC. Xl EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ IST PER 2ND PER 3RD PER ITEN 4 ITEN DESCRIPTION BI4.10 REACTOR VESSEL-MELDS IM VOLUMETRIC RCS RPV-CLOSUR 12 0/0 0/0 }/0 CONTROL ROD DRIVE HOUSIilGS SURFACE NOTE '.EXAMINE 10X OF PERIPHERAL HOUSINGS, END OF INTERVAL
ST ~ LUCIE NUCLEAR PLANT UHIT 1 PAGE: 27 t
IHSERVICE INSPECTION PLAN FOR THE FIRST IHTERVAL CLASS 1 SECTION XI
SUMMARY
TABLE A CATEGORY B-P - ALL PRESSURE RETAININ6 COMPONENTS IN REACTOR VESSEL ASME 0 OF CDMPONENTS SEC, XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTIOH ZONE COMPDNENTS RED 1ST PER 2HD PER 3RD PER B15. 10 REACTOR VESSEL-SYSTEM LEAKAGE VISUAL VT-2 ALL CLASS 1 1/0 1/0 1/0 TEST
~~>>+ NOTE :EXAMINE ALL CLASS 1 COMPONENTS AND SYSTEMS. EACH REFUELIHG OUTAGE.
B15. 11 REACTOR VESSEL-SYSTEM VISUAL VT-2 ALL CLASS 1 0/0 0/0 1/0 HYDROSTATIC TEST
~wwww NOTE :EXAMINE ALL CLASS COMPOHENTS AHD SYSTEMS. OHE TEST AT OR HEAR END OF 1 INTERVAL, 815.20 PRESSURIZER-SYSTEM LEAKAGE VISUAL VT-2 ALL CLASS I 1/0 1/0 1/0 TEST
>%+++ NOTE lEXAMINE ALL CLASS 1 COMPOHENTS AND SYSTEMS. EACH REFUELIHB OUTA6E ~
INTERVALED B15 21 PRESSURIZER-SYSTEM HYDROSTATIC VISUAL VT-2 ALL CLASS 1 0/0 0/0 1/0 TEST
+>+++ NOTE :EXAMINE ALL CLASS 1 COMPOHENTS AND SYSTEMS. ONE TEST AT OR HEAR END OF 815 30 STEAM 6EHERATQRS-SYSTEM 'ISUAL VT-2 ALL CLASS I 2/0 2/0 2/0 LEAKAGE TEST wwaa~ NOTE .'EXAMINE ALL CLASS 1 COMPDNENTS AND SYSTEMS. EACH REFUELIHG OUTAGE B15.31 STEAM GENERATORS-SYSTEtl VISUAL VT-2 ALL CLASS 1 0/0 0/0 2/0 HYDROSTATIC TEST
+++w~ HOTE :EXAMINE ALL CLASS I COMPONENTS AHD SYSTEMS. OHE TEST AT OR NEAR EHD OF INTERVAL B15.40 HEAT EXCHAH6ERS-SYSTEM LEAKAGE VISUAL VT-2 ALL CLASS 1 4/0 4/0 4/0 TEST
>ww+w NOTE :EXAMINE ALL CLASS 1 COMPONENTS AND SYSTEMS. EACH REFUELING OUTAGE.
B15, 41 HEAT EXCHAHGERS-SYSTEM VISUAL VT-2 ALL CLASS 1 0/0 0/0 4/0 HYDROSTATIC TEST w<>>+ NOTE :EXAMIHE ALL CLASS 1 COMPONENTS AND SYSTEMS. ONE TEST AT OR HEAR END OF INTERVAL.
B15.50 PIPING-SYSTEM LEAKA6E TEST VISUAL VT-2 ALL CLASS 1 4 4/0 4/0 4/0 w4wf~ NOTE:EXAMINE ALL CLASS I COMPONENTS AHD SYSTEMS ~ EACH REFUELIH6 OUTAGE
- RCS, RC, CVCS) Sl B15 51 PIPING-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 1 4 0/0 0/0 4/0
~++~+ NOTE:EXAMINE ALL CLASS 1 COMPONENTS AHD SYSTEMS. ONE TEST AT OR NEAR END OF INTERVAL.
- RCS} RC} CVCS) SI INTERVALED i'15 60 PUMPS-SYSTEM LEAKAGE TEST VISUAL VT-2 ALL CLASS 1 4 4/0 4/0 4/0
~%H~ NOTE;EXAMINE ALL CLASS 1 COMPOHENTS AHD SYSTEMS, EACH REFUELIHG OUTAGE, 615.61 PUMPS-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 1 4 0/0 0/0 4/0
~~~~+ NDTE :EXAMINE ALL CLASS 1 COMPOt(ENTS AND SYSTEMS. OHE TEST AT OR NEAR EHD OF
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 28 REVISIONS 1 IHSERVICE INSPECTION PLAN FOR THE FIRST IHTERVAL CLASS 1 SECTION XI
SUMMARY
TABLE A CATEGORY B-P - ALL PRESSURE RETAINIHG COMPONENTS IH REACTOR VESSEL ASME I OF COMPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTIOH EXAM METHOD SYSTEM DESCRIPTIOH ZONE COMPONENTS REQ 1ST PER 2HD PER 3RD PER B15,70 VALVES-SYSTEM LEAKAGE TEST, VISUAL VT-2 ALL CLASS 1 ALL 1/0 1/0 1/0 w~w~a NOTE :EXAMINE ALL CLASS 1 COMPONENTS AHD SYSTEMS. EACH REFUELING OUTAGE.
- PART OF PIPING SYSTEM 815 '1 VALVES-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 1 ALL 0/0 0/0 I/O
~wl~w NOTE ;EXAMINE ALL CLASS 1 COMPOHENTS AND SYSTEMS, ONE TEST AT OR NEAR END OF INTERVAL, APART OF PIPING SYSTEM
OATEN'8/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGE: 29 t
)EVI SION: I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI
SUMMARY
TABLE A CATEGORY B-Q
- STEAM GENERATOR TUBING ASME 0 OF COMPONENTS SEC, XI NUMBER OF RELIEF, SCHEDULED/COMPLETED ITEM tt ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ, 1ST PER 2ND PER 3RD PER Blb.20 STEAl1 GENERATOR TUBING IN U . VOLUMETRIC RCS SG-IA 0/0 0/0 0/0
-TUBE DESIGN
>>>>+ NOTE :EXAMINE PER TECH. SPEC. REQUIREMENTS.
B16,20 STEAM GENERATOR TL'BING IN U VOLUMETRIC RCS SG-IB 0/0 0/0 0/0
-TUBE DFSIGN
>>>>w tkDTE:EXAMINE PER TECH. SPEC. REQUIREMENTS.
RPPENOI 8 B CLRSS 2 EXRMINRTION SUMMRRY TRBLES
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UttIT 1 PAGE: I REV IS ION: I IttSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTlOtt Xl
SUMMARY
TABLE 8 CATEGORY C-A
- PRESSURE RETAlttING ttELDS IH PRESSURE VESSELS ASNE 4 OF COt!POHENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEN 4 ITEN DESCRIPTION EXAN NETHOO SYSTEN DESCRIPTIOtl ZONE COt!PONEHTS RED. 1ST PER 2ttD PER 3RD PER Ci.!0 SHELL CIRCUMFERENTIAL TELOS VOI.UMETRIC ttSS S/6 1A 41 0/0 0/0 0/0 Cl 10 SHELL CIRCUttFERERTIAL ttELDS VOLUMETRIC t!SS S/6 18 42 1/0 I/O 1/0 C! 20
~ HEAD CIRCUMFEREttTIAL ttELDS VOLUNETRIC NSS S/6 lA 41 2 0/0 0/0 0/0 C1,20 HEAD CIRCUttFEREHTIAL TELOS VDLUMETRIC NSS S/6 18 42 2 0/0 1/0 0/0 C!.20 HEAD CIRCUNFERENTIAL ttELDS VDLUMETRIC NSS SHE !A 0/0 1/0 0/0 C!,20 HEAD CIRCUMFEREltTIAL HELDS VOLUMETRIC NSS SHE 18 56 0/0 0/0 0/0 C1.30 TUBESHEET-TO-SHEI.L ttELDS VOLUMETRIC MSS S/G !A 1/0 0/0 0/0
. C1.30 TUBESHEET-TO-SHELL MELDS VOLUMETRIC NSS S/G 18 42 0/0 0/0 0/0 I C!.30
- 1.30 TUBESHEET-TO-SHELL MELDS TUBESHFET-TO-SHELL 'AELDS VOLUMETRIC VOLUNETRIC Sl SI SHE 1A SHE 18 0/0 0/0 0/0 0/0 0/0 1/0
DATE. '08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAB.": 2 REViSION: 1 INSERVICE INSPECTION PLAN FGR THE FIRST INT RVAL CLASS 2 SECTION Xl SU<st(ARY TABLE 8 CATE GRY C-8 - PRESSURE RETAININ6 NOZZLE MELDS IN VESSELS ASNE 4 OF CGt(POt(Et(TS SEC. XI t(UMBER QF RELIEF SCHEDULED/COMPLETED ITEN 4 ITEt( DESCRIPTION EXAM t(ETHOD SYSTEN DESCRIPTION ZONE CQt(PDNEt(TS RED. 1ST PER 2ND PFR 3RD PER C2 ~ 10 NGZZLES Iit VESSELS (= 1/2 IN. iiSS, FM, SI, N/A 0/0 0/0 0/0 tiQNINAL THICKtiESS C2 ~ 11 NOZZLE-TO-SHELL (GR HEAD) MELD SURFACE NSSi FM, Sl 0/0 0/0 0/0 C2.21 NOZZLE-TO-SHELL (OR HEAD) MELD SURFACE S/6 IA 1/0 1/0 0/0 VOLUMETRIC C2.21 NOZZLE-TO-SHELL (OR HEAD) MELD SURFACE S/6 18 42 0/0 0/0 2/0 VOLUt(ETRIC C2.21 NOZZLE-TO-SHELL (QR HEAD) MELD SURFACE Si SHE 1A 0/0 0/0 0/0 VGLUNETRIC C2.21 NOZZLE-TO-SHELL (OR HEAD) WELD SURFACE Sl SHE 18 0/0 0/0 0/0 VOLUMETRIC C2 ~ 22 NOZZLE INSIDE RADIUS SECTION VOLUt(ETRIC S/6 1A 41 I/O 1/0 0/0 C2.22 NOZZLE INSIDE RADIUS SECTION . VOLUMETRIC S/6 18 42 0/0 0/0 2/0 C2 ~ 22 NOZZLE INSIDE RADIUS SECTION VOLU)(ETRIC SI SHE IA 0/0 0/0 0/0 C2.22 NOZZLE INSIDE RADIUS SECTION VOLUNETRIC Sl SHE 18 56 0/0 0/0 0/0 C2.30 NOZZLES MITH REINFORCIN6 PLATE N/A 0/0 0/0 0/0 IN VESSELS > 1/2 IN. NONlttAL THICKNESS C2.31 REINFORCINB PLATE MELDS TG SURFACE N/A 0/0 0/0 0/0 NOZZLE AND VESSEL C2.32 NOZZLE-TO-SHELL (OR HEAD), VOLUt(ETRIC N/A 0/0 0/0 0/0 WELDS WHEN INSIDE OF VESSEL IS ACCESSIBLE C2.33 ttOZZLE-TO-SHELL (OR HERD) VISUAL VT-2 N/A 0/0 0/0 0/0 MELDS WHEN INSIDE OF MELD IS INACCESSIBLE
DATE'. 08/25/87 I L""'UCLEAR PLA'tT U"IIT 1 ?AG-:l REVISIONl I It<SERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTION XI
SUMMARY
TABLE 8 CATEGORY C C INTEGRAL ATTACHHENTS FOR PRESSURE VESSELS ASt!E 4 OF COt!PONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED KTEtl 4 KTEH DESCRIPTIDN EXAM HETHOD SYSTEM DESCRIPTION ZONE COttPONENTS R Q. 1ST PER 2ND PER 3RD ?ER C3 IO PRESSURE VESccLS INTEGRALLY SURFACE S/6 1A 41 2/0 OIO 2IO WELDED ATTACH"ENTS C3. 10 PRESSURE VESSELS-INTEGRALLY SL'RFAC'E S/6 18 0/0 2/0 2/0 WELDED ATTACHttENTS C3 ~ 20 PIPING INTEGRALLY WELDED SURFACE t!SS 0/0 ~ 2/0 2/0 ATTACHHENTS C3 ~ 20 P IP ING-INTEGRALLY MELDED SURFACE HSS 0/0 5/0 0/0 ATTACHMENTS C3.20 PIPING-INTEGRALLY MELOED SURFACE iHSS 0/0 0/0 0/0 ATTACHMENTS C3.20 PK Pl ttG-IttTEBRALLY WELDED SURFACE t!SS 0/0 "0/0 0/0 ATTACHttENTS
".3.20 PIPING-INTEGRALLY MELDED SURFACE FM 67 I/O 0/0 0/0 ATTACHMENTS C3.20 PIPING-INTEGRALLY WELDED SURFACE FW 68 1/0 0/0 0/0 ATTACHMENTS C3. 20 PIPING-INTEGRALLY WELDED SURFACE FW 71 0/0 1/0 0/0 ATTACHMENTS C3.20 PIPING-INTEGRALLY WELDED SURFACE FW 72 0/0 0/0 0/0 Al'TACHt!EHTS C3.30 PUMPS-INTEGRALI.Y WELDED SURFACE Sl LPSI PUi'IPS 0/0 I/O 1/0 ATTACHHcHTS C3.30 PUMPS-INTEGRALLY WELDED SURFACE SI HPSI PUttPS 1/0 I/O 1/0 ATTACHMENTS C3 30 PUttPS-INTEGRALLY WELDED SURFACE SI CHARGING PUMPS I/O I/O 1/0 ATTACHHENTS C3.40 VALVES-INTEGRALLY WELDED SURFACE ALL N/A 0/0 0/0 0/0 ATTACHHENTS
DATE: 08/25/G7 ST. LUCIE NUCLEAR PLANT UNIT I PAGEOS 4 REVI SION,' INSERVICE INSPECTION PLAN FOR TH" FIRST INTERVAL CLASS 2 SECTION XI
SUMMARY
TABLE B CATEGORY C-D - PRESSURE RETAINING BOLT'ING GREATER THAN 2 INCHES IN DIAMETER IN PRESSURE VESSELS ASME 0 OF COMPONENTS SEC. XI NUMBER OF RELIEF SCHFDL'LED/COMPLETED ITEM 4 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ, IST PER 2ND PER 3RD PER C4. 10 PRESSURE VESSELS-BOLTS AND VDLUMETRIC ALL N/A 0/0 0/0 0/0 STUDS C4.20 PIPING-BOLTS AND STUDS VOLUMETRIC ALL N/A 0/0 0/0 0/0 C4 ~ 30 PUMPS-BOLTS AND STUDS VOLUMETRIC ALL N/A 0/0 0/0 0/0 C4.40 VALVES-BOLTS AND STUDS VOLUMETRIC ALL N/A 0/0 0/0 0/0
GATE: 08/25/87 ST. LUCIE ttUCLEAR PLANT UHIT 1 PAGE: 5 REVISION: INSERVICE INSPECTION PLAN FOR THE FIRST !ttTERVAL CLASS 2 SECTION X! SUNiNARY TABLE 8 CATEGORY C-F-I - CODE CASE N-408 TABLES ASttE 4 QF COMPONENTS 6'4 SEC. Xi tlUNBER OF RELIEF SCHEDULED/CQNPLETED ITEN tt ITEit DESCRIPTIGH EXAN NETHOD SYSTEN DESCRIPTION ZONE CQttPGNENTS REQ, IST PER 2HD PER 3RD PER li 6'1 C5 CIRCUNFEREttTIAL MELDS SURFACE SI 12 4/0 4/0 4/0 VDLUiNETRIC
+axe+ ttOTE :tt OF CONPONENTS: NECESSARY TO NEET 7,5X OF Sl MELDS PER C-F-1.
C5. 11 CIRCUttFEREttT IAL MELDS SURFACE HPSI 22 3/0 3/0 4/0 VGLUt!ETRIC
~~~%~ HOTE :tt QF COtlPONEHTS: NECESSARY TO NEET 7.5X OF Sl MELDS PER C-F"i.
~
C5 F 11 CIRCUttFERENTIAL MELDS SURFACE HPSI 6 62 25 3/0 3/0 4/0 VOLUrETRIC aw%wt HQTE lB CF CGNPGHENTSl NECESSARY TO NEET 7.5X OF Sl MELDS PER C-F-I C5.12 LOHGITUDlttAL MELDS SURFACE 0/0 0/0 0/0 VOLUNETRIC t
C5.21 CIRCUNFEREHTIAL MELGS UT-PT HPSI 61 I/O 1/0 0/0 C5.21 MELDS UT-PT HPSI 3'IRCUMFERENTIAL 62 13 0/0 1/0 1/0 4'T-PT C5 ~ 21 CIRCUMFERENTIAL MELDS HPSI 62 34 I/O 0/0 3/0 3'T-Pl'PSI C5,22 LONGITUDINAL MELDS 0/0 0/0 0/0 C5.30 SOCKET MELDS HPSI 83 30 4/0 0/0 0/0 2'PSI C5.30 SOCKET MELDS PT 87 156 8/0 4/0 8/0 2'PSI C5.30 SOCKET MELDS PT 84 29 0/0 4/0 0/0 2'PSI C5,30 SOCKET MELDS PT 85 35 0/0 0/0 5/0 2'/O 2'PSI C5.30 SOCKET MELDS PT 86 39 0/0 5/0 0/0 2'PSI C5.41 BRANCH CONNECTORS >"- 2'PS - PT 2" 0/0 1/0 0/0 CIRCUMFERENTIAL MELDS C5.41 >>RANCH COHNECTGRS >= 2'PS - PT HPSI 0/0 0/0 CIRCUtiFEREHTIAL MELDS
>-" 2'PS - 0/0 0/0 0/0 12'3 C5.42 BRANCH CONNECTORS PT HPSI NONE PT LQNGITUDIt(AL MELDS MELDS T < .375' EXEMPT - N Sl 71 0/0 0/0 0/0
-408
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT I PAGE:
REVISION,' INSERVICE INSPECTION PLAN FGR THE FIRST INTERVAL CLASS 2 SECTION XI SUtlt!ARY TABLE 8
.ATEGORY C-F-l - CODE CASE N-408 TABLES ASNE tt OF COMPONENTS SEC. Xi NUMBER OF RELIEF SCHEDULED/CONPLETED ITEN 5 ITEN 5=SCRIPTION FXAtl METHOD SYSTFN DESCRIPTION 10'3 ZONE CONPGNENTS RED. IST PER 2ND PER 3RD F'ER C5,43 HELDS T .375'XEMPT Sl 0/0 0/0 0/0 12'4
< N 27
-408 C5.43 'AELDS I < .375' EXEMPT - N SI 22 0/0 0/0 0/0
-408 C5.43 'AELDS T < .375' EXEMPT - N SI 6" 44 27 0/0 0/0 0/0 10'9
-408 C5 ~ 44 CIRCUNFERENTIAL NELDS - EXENPT SD CLG 23 0/0 0/0 0/0 10'0 M-408 C5 44 CIRCUNFEREHTIAL TELOS - EXEMPT SD CLG, 35 0/0 0/0 0/0 10'1 H-408 C5,44 CIRCUNFERENTIAI. ltELDS - EXFNPT SD CLG. 30 OIO 0/0 0/0
- N-408
,5. 44 - IOr 24'2 CIRCUNiERENTIAL MELDS EXEMPT SD CLG 20 0/0 0/0 0/0
- N-408 C5.44 CIRCUMFERENTIAL MELDS - EXEMPT SD CLOD 70 61 0/0 0/0 0/0
- N-408 C5. 44 CIRCUNFEREMTIAL MELDS - EXENPT HPSI I ) SUCTION 24'. 73 18 0/0 0/0 0/0
) LPS H 408 C5 ~ 44 CIRCLNF REHTIAL NELDS
- M-408
- EXENPT HPSI,LPSI,SUCTION 14'3 30 0/0 0/0 0/0 C5 44 CIRCUtliEREHTIAL MELDS
- N-408
- EXEMPT HPSI)LPSI,SUCTIGM 6'3 16 0/0 '/0 0/0 C5.44 CIRCUMFERENTIAL NELDS
- N-408
- EXEtlPT HPSI,LPSI,SUCTION 24'4 30 0/0 0/0 0/0 C5.44 CIRCUNFEREHTIAL NELDS
- EXEMPT, HPSI,LPSI) SUCTION 14'4 29 0/0 0/0 0/0 N-408 C5. 44 CIRCUMFERENTIAL NELDS
- N-408
- EXEMPT HPS I, LPS I, SUCTION 8'4 l2 0/0 OI 0 0/0 C5.44 CIRCUtlFEREHTIAL NELDS
- N-408
- EXEtlPT HPSI,LPSI,SUCTION 6'4 22 0/0 0/0 0/0
DAT.:: 08/2'./87 ST ~ LUCIE NUCLEAR PLANT UNIT I ?AGE: 7 REV IS I OH: 1 INSERVICE INSPECTIOH PLAN FOR THE FIRST INTERVAL CLASS 2 SECTION XI
SUMMARY
TABLE 8 CATEGORY C-F-1 - CODE CASE H-408 TABLES ASNE 8 OF COMPONENTS SEC. XI NUNBER OF RELIEF SCHEDULED/COiIPLETED ITEN 4 ITEN DESCRIPTION EXAM METHOD SYSTEi1 DESCRIPTION ZONE COMPOHENTS RED. 1ST PER 2ND PER 3RD P:R C5.44 CIRCUHFEREH'IIAL MELDS
- EXEMPT SD CLG.) SI, C.S. 10'5 0/0 0/0 0/0 H-408 C5.44 CIRCUHFERENT!AL MELDS
- N-408
- EXEMPT SD.CLG., SI, C,S. 12'6 19 0/0 0/0 0/0 C5.44 CIRCUMFERENTIAL MELDS
- EXEMPT SD CLG., Sl, C ~ S. 12'7 0/0 0/0 0/0 H-408 C5 ~ 44 CIRCUMFERENTIAL MELDS EXEMPT SD CLG., SI, C.S. 10'7 0/0 0/0 0/0 N-408 C5.44 CIRCUMFERENTIAL MELDS
-, N-408
- EXEMPT SD CLG., SI, C.S. 6'7 0/0 0/0 0/0 12'8 t
C5.44 CIRCUMFERENTIAL MELDS - EXEMPT SD CLG ~ ) Sl) C~S ~ 19 0/0 0/0 0/0
- N-408
'5.44 CIRCUNFEREHTIAL MELDS
- H-408
- EXEMPT SD CLG. ) SI ) C, S. 8'8 0/0 0/0 0/0 C5.44 CIRCUMFERENTIAL MELDS - EXEHPT C~ S. 12" 79 38 0/0 0/0 0/0 C5,44
- H-408 CIRCUMFERENTIAL MELDS
- '1-408
- EXEHPT C.S. 12'0 34 0/0 0/0 0/0
<<<<4 EXEMPT CIRCUMFERENTIAL MELD SUP!NARY <<%<<
24' 109 14' 59 12' 211 f0' 148 8' l3 6' 67 TOTAL - 607
DATE: OS/25/87 ST, LUCIE NUC'EAR PLANT UNIT 1 RASE: 8 t
REVISION: INSERVICE INSPFCTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTIO!i Xl SUHHARY TABLE 8 CATEGORY C-F-2 - CODE CASE H-408 36'/0 AStlE 4 OF COilPONEHTS SEC. XI HUHBER OF RELIEF SCHEDULED/COHPLETED ITEtl 4 ITEil DESCRIPTIOH ".XAH HETHOD SYSTEH DESCRIPTION ZOtiE COHPONENTS RED ~ IST ER 2,'iD PER 3RD PER C5.51 PIPI!JS >= 3/STI -". NPS- HT tlSS 0/0 0/0 CIRCUHFERENTIAL MELDS PT C5.51 C5.51 PIPltiS >= 3/ST; 4 CIRCUHFERENTIAL MELDS PIPINS >= 3/BTi 4 NPS-NPS-HT PT tlT HSS HSS 35'3 34" 64 12 0/0 0/0 2/0 0/0 0/0 1/0 CIRCUHFERENT I AL MELDS PT 34'4 C5.51 PIPING >= 3/BTI 4 CIRCUMFERENTiAL MELOS NPS- HT PT HSS 35.5'/0 14 0/0 2/0 0/0 8'/0 C5.51 PIPINS >= 3/ST' NPS- HT HSS 1/0 0/0 C5 ~ 51 CIRCUHFERENTIAL MELDS
'IPING >= 3/ST; 4 NPS CIRCUHFERENTIAL MELDS PT HT PT tlSS 34'5 0/0 0/0 0/0
- s.si PIPING >= 3/BTI 4 NPS- HT HSS 0/0 0/0 CIRCUHFERENTIAL MELDS PT C5.51 PIPINB >= 3/ST; 4 NPS- tlT iHSS 1/0 0/0 0/0 CIRCUHFER."NTIAL MELQS PT 8'/0 34'5 6'lSS C5,51 PIPING >= 3/BTI 4 HPS- HT 0/0 0/0 2/0 CIRCUHFERENTIAL 'AELDS PT 35.5'SS C5.51 PIPINS >= 3/ST) 4 NPS- HT 56 0/0 0/0 I/O CIRCUHFERENTIAL MELDS PT C5.51 PIPittB >= 3/ST; 4 NPS " HT HSS 0/0 0/0 CIRCUHFERENTIAL MELDS PT PIPIHS >" -3/BTI 4 NPS- 0/0 0/0 1/0 20'7 C5. 51 HT HSS CIRCUHFERENTIAL MELOS PT 6'F C5.51 PIPltiS >= NPS- I/O 0/0 0/0 18'7 3/BTI 4 HT CIRCUHFEREHTIAL MELQS UT C5.51 PIPING >= 3/ST; 4 NPS- I/0 1/0 0/0 20'8 tlT BF CIRCUtlFERENTIAL MELDS UT t C5.51 PIPING >= 3/ST; 4 CIRCUHFERENTIAL MELDS NPS- HT UT BF 10 0/0 0/0 2/0
BATE: 08/2 /87 ST. LUCIE NUCLEAR PLANT UNIT I REV IS ION: I INSERVICE INSPFCTIQtt PLAN FOR THE FIRST INTERVAL CLASS 2 SECTION XI
SUMMARY
PAGE.'TEGORY TABLE 8 C-F CODE CASE N-408 ASi!E 4 OF COMPO!iENTS SEC. Xl NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM lt I'IEM DcSCRIPTION 18'8 EXAM t!ETHOD SYSTEM DESCRIPTION EONE COMPONENTS RED. IST PER 2!tD PER 3RD PER C5.51 PIPltiB >= 3/STI NPS- I/O 0/0 0/0 20'1 4 MT BF CIRCU!!FERENTIAL NELDS UT C5.51 PIPItiG NPS- 0/0 20'2
>= 3/STI 4 tlT BF 0/0 2/0 36'/0 CIRCUtlFERENTIAL NELOS UT C5.51 PIPING >= 3/BT; 4 NPS- MT BF 0/0 0/0 2/0 CIRCUMFERENTIAL NELDS UT C5,52 PIPING >= 3/BT; 4 NPS- tlSS 0/0 0/0 34'3 MT LONGITUDINAL NELDS UT 34'/0 C5.52 PIPING >= 3/ST; 4 tiPS- MSS 24 0/0 4/0 0/0 LONGITUDINAL NcLDS UT C5,52 PIPING > 3/STi 4 NPS MT MSS 0/0 2/0 LONGITUDINAL NELDS .UT 36'lSS 5.52 PIPING >= 3/BT; 4 tiPS- ilT 0/0 4/0 0/0 LONGITUDINAL 'AELDS UT C5 52, PIPING >" 3/STI 4 tlPS MT MSS 35 5" 1/0 I/0 0/0 C5. 52 LONGITUDINAL NELDS PIPING >='3/ST; 4 NPS LONGITUDINAL TELOS UT MT UT MSS 34'5 0/0 OIO 0/0 C5.52 PIPING >= 3/BT; 4 tiPS-LGNBITUDItiAL NELDS tlT UT t!SS 35,5'6 0/0 0/0 2/0 C5.52 PIPING >- 3/BTI 4 NPS 34" 0/0 0/0 4'T MT tlSS I/O LONGITUDINAL MELDS UT C5 70 SOCKET ttELDS > MSS, BF 0/0 0/0 0/0 4'/0 8'5 C5.81 BRANCH PIPE CONNECTIONS > 2'T MSS I/O 0/0 0/0 NPS CIRCUMFERENTIAL NELDS 6'lSS es 81
~ BRANCH PIPE CONNECTIONS > 2'lT 1/0 0/0 0/0 NPS CIRCUMFERENTIAL NELDS C5.8} BRAiiCH PIPE CONNECTIONS > 2'lT MSS 0/0 0/0 NPS - CIRCUilFERENTIAL WELDS
OATEN'8/25/87 ST, LUCIE NUCLEAR P'NT UNIT 1 PAGE: 10 REVISION: I INSERVICE INSPECTION PLAti FOR THE FIRST INTERVAL CLASS 2 SECTION Xl SUttttARY TABLE B
.ATEGORY C-F-2 - CODE CASE N-408 ASttE I OF COttPOiRENTS 8'/0 6'6 SEC, XI NUNBER OF RELIEF SCHEDULED/COttPLETED ITEtl 0 ITEtt DESCRIPTION EXAN ttETHOD SYSTEtt DESCRIPI'ION IOttE CONPONENTS REQ. IST PER 2ND PER 3RD PER C5.81 BRANCH PIPE COtiNECTIONS > 2'T iNSS 0/0 0/0 1/0 tiPS CIRCUiNFERENTIAL MELDS C5.81 BRANCH PIPE CCNtiECTIONS > 2 NT HSS 0/0 1/0 4'6 tiPS - CIRCUttFERENTIAL NELDS C5.81 BRANCH
?IPE CONNECTIONS > 2'T ttSS 0/0 0/0 0/0 NPS CIRCUttFERENTIAL MELDS 4'F C5.81 C5 ~ 81 C5 82 BRANCH NPS BRANCH tiPS -
BRANCH PIPE CONNECTIONS PIPE CONNECTIONS PIPE CONNECTIOllS CIRCUttFERENTIAL MELDS CIRCUNFERENTIAL MELDS 2'T 2'T 2'T BF 4'2 tlSSi BF) N/A 71 0/0 0/0 0/0 I/O 0/0 0/0 ,
0/0 0/0 0/0 NPS - LONGITUDINAL MELDS
DATE; 08/2./Bl ST. LUCIE NUCL:"AR PLANT UNI AAAI REVISION: INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTIGH Xl SUttttARY TABI.E B ASHE 4 OF CGitPGNENTS SFC. XI NU?1BER OF RELIEF SCHEDULED/COMPLETED ITEN tt ITEN OESCRIPTIOM EXANi HETHGD SYSTEM DESCRIPTIOM ZONE CONPOHEttTS REQ. IST PER 2ND PER 3RD PER C6,10 PUMPS PUMP CASING TELOS SURFACE ALL H/A 0/0 0/0 0/0 C6.20 VALVES-VALVE BODY HELDS SURFACE ALL iN/A 0/0 0/0 0/0
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UHIT 1 PAGEOS 12 REVISION: 1 INSERVICE INSPECTION PLAN FOR TME FIRST INTERVAL CLASS 2 SECTION XI
SUMMARY
TABLE B CATEGORY C-H - ALL PRESSURE RETAINING COMPONENTS IH PRESSURE VESSELS ASME 5 OF COMPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 4 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTIOH ZONE COMPONENTS RED. 1ST PER 2ND PER 3RD PER C7. 10 PRESSURE VESSELS-SYSTEtl VISUAL VT-2 ALL CLASS 2 PER COLOR 12 12/0 12/0 12/0 PRESSURE TEST CDDED P&ID'S
>>>>w NOTE )0 OF COMPONENTS: EXAMINE ALL CLASS 2 COMPONENTS AND SYSTEMS EACH PERIOD ~
- S/G, RHX, BAT) HDOHST) SCHX C7.20 PRESSURE VESSELS-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 2 PER CDLOR CODED P&ID'S 12 0/0 0/0 '2/0
>>>>a NOTE :I OF COMPOHENTS: EXAMINE ALL CLASS 2 COMPONENTS AHD SYSTEMS EACH INTERVAL, C7.30 PIPING-SYSTEM PRESSURE TEST VISUAL VT-2 ALL CLASS 2 PER CDLOR 12 12/0 12/0 12/0 CODED P&ID'S
>>>>+ HOTE :0 OF COMPONEHTS: EXAttINE ALL CLASS 2 COMPONENTS AND SYSTEMS EACH PERIOD.
- CCH) MS) FH, BO, CS, AFN, RC, CVCS, CS) RFH, Sl, SCS C7,40 PIPIHG-SYSTEtl HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 2 PER COLOR 12 0/0 0/0 12/0 CODED P&ID'S
>>>>+ NOTE :a OF COMPONENTS: EXAMINE ALL CLASS 2 COMPONENTS AHD SYSTEMS EACH INTERVAL.
C7.50 PUMPS-SYSTEM PRESSURE TEST VISUAL VT-2 ALL CLASS 2 PER COLOR 12 12/0 12/0 12/0 CODED P&ID'S
>>>>+ NOTE lO OF COMPONENTS) EXAMINE ALL CLASS 2 COMPONENTS AND SYSTEMS EACH PERIOD,
)BAP) CHP) CSP) LPSI) HPSI C7.60 PUMPS-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 2 PER COLOR 12 0/0 0/0 12/0 CODED P&ID'S
>>>>+ NOTE ll OF COMPONENTSl EXAMIHE ALL CLASS 2 COMPONEHTS AHD SYSTEMS EACH INTERVAL.
C7.70 VALVES-SYSTEM PRESSURE TEST VISUAL VT-2 ALL CLASS 2 PER COLOR 1/0 1/0 1/0 CODED P&ID'S
>>>>+ NOTE lN OF COMPONENTSl EXAMIHE ALL CLASS 2 COMPONENTS AND SYSTEMS EACH PERIOD.
C7 ~ 80 VALVES-SYSTEM HYDROSTATIC TEST VISUAL VT-2 ALL CLASS 2 PER COLOR 0/0 0/0 1/0 CODED P&ID'S
>>>>+ NOTE l% OF COMPONENTS) EXAMIHE ALL CLASS 2 CDMPOHEHTS AHD SYSTEMS EACH INTERVAL, APART OF PIPING SYSTEM
0 RPPENO I >< C CLRSS 3 ENRMINRTION SUMMRRY TRBLES
DATEl 08/25/87 ST. LJCIE NUCLEAR PI.ANT iJHIT 1 PAGE: 1 REVISION: 1 INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 3 SECTION XI SUttNARY TABLE C CATEGORY D-A
- SYSTENS IN SUPPORT OF REACTOR SHUTOOMN FUttCTION ASttE 4 OF CONPONENTS SEC, XI NUMBER OF RELIEF SCHEDULED/CO<1PLETED ITEt1 4 ITEtl DESCRIPTION EXAM METHOD SYSTE<1 DESCRIPTION ZONE COt1PONENTS RED. 1ST PER 2HD PER 3RD PER Dl. 101 SYSTEN PRESSURE TEST VI'-2 ALL CLASS 3 BOUNDARY I/O 1/0 1/0
<<<<> NOTE lALL COt1PONENTS TO BE EXAttINED EACH PERIOD Dl. 10B SYSTEM HYDROSTATIC TEST VT-2 ALL CLASS 3 BOUNDARY 0/0 0/0 1/0 aww4w NOTE lALL COttPONENTS TO BE EXAMINED EACH INTERVAL D1.20 INTEGRAL ATTACHttENT-COttPO<<tENT VT-3 'FM 113 2 I/O . 1/0 0/0 SUPPORTS AND RESTRAINTS Dl 20
~ INTEGRAL ATTACHMENT-COHPOttEttT VT-3 CONDENSATE 118 I/O 1/0 I/O SUPPORTS AND RESTRAINTS
. Dl.20 INTEGRAL ATTACHtlENT-COHPONEHT VT-3 CONDENSATE II9 2 0/0 '1/0 1/0 SUPPORTS AND RESTRAINTS Dl,30 INTEGRAL ATTACHNENT-NECHANICAL VT-3 N/A 0/0 0/0 0/0 AND HYDRAULIC SNUBBERS e Dl.40 INTEGRAL ATTACHttENT-SPRING TYPE SUPPORTS VT-3 N/A 0/0 0/0 0/0 Dl 50
~ I ttTEGRAL ATTACHNENT-CONSTAttT VT-3 CONDFttSATE 120 1 0/0 1/0 0/0 LOAD TYPE SUPPORTS DI.60 INTEGRAL ATTACHttENT-SHOCK VT-3 H/A 0/0 0/0 0/0 ABSORBERS
D ATE: 08/25/87 ST ~ LUCIE NUCLEAR PLANT UNIT 1 PAGE'. 2 REVISION: INSERVICE INSPECTIOM PLAN FOR THE FIRST INTERVAL CLASS 3 SECTIOti XI SL'tlNARY TABLE C CATEGORY D-B
- SYSTEtlS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAICENT HEAT RENOVAL, ATtlOSPHERE CLEANUP ASttE 4 OF CONPOtiENTS SEC. XI tiUNBER OF RELIEF SCHEDULED/COMPLETED I TEtl 4 ITEN OESCRIPTIOM EXAM "ETHOD SYSTEM DESCRIPT IOti ZONE COMPONENTS RED'ST PER 2ND PER 3RD PER 02 '0A SYSTEtl PRESSURE TEST VT-2 ALL CLASS 3 BOUNDARY 1/0 I/O 1/0 a+au+ NOTE lALL COtlPOtiEMTS TO BE EXAtlINED EACH PERIOD.
D2.10B SYSTEM HYDROSTATIC TEST Vl'-2 ALL CLASS 3 BOUtiDARY 0/0 0/0 1/0
><4+% NOTE lALL COMPONENTS TO,BE EXAtllNED EACH INTERVAL D3. 10A SYSTEM PRESSURE TEST VT-3 CC 101 OIO 0/0 I/O D3. 10B SYSTEM HYDROSTATIC TEST VT-3 110 18 6/0 6/0 6/0 D3.20 INTEGRAL ATTACHMENT-COMPONENT VT-3 NIA 0/0 0/0 0/0 SUPPORTS AND RESTRAINTS, D3.30 INTEGRAL ATTACHttENT-NECHANICAL VT-3 CC 100 1/0 1/0 1/0 AND HYDRAULIC SNUBBERS D3,30 INTEGRAL ATTACHttENT-tlECHAttICALVT-3 CC 105 1/0 1/0 1/0 AtiD HYDRAULIC SNUBBERS D3.40 INTEGRAL ATTACHttENT-SPRING VT-3 N/A 0/0 0/0 0/0 TYPE SUPPORTS 93.50 INTESRAL ATTACHMENT-CONS'TANT VT-3 N/A OIO 0/0 0/0 LOAD TYPE SUPPORTS
DATE: 08/2$ /S7 ST. LUCIE NUCLEAR PLANT UNIT I REVISION: INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 3 SECTION XI
SUMMARY
PASE.'SME TABLE C CATEGORY D-C
- SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL 4 OF COMPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEit 4 ITEtt DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS RED ~ IST PER 2ND PER 3RD PER D3.BOA SYSTEM PRc;SSURE TEST VT-2 ALL CLASS 3 BOUNDARY I/O I/O 1/0
+<aim NOTE lALL COiMPONENTS TQ BE EXAMINED EACH PERIOD.
D3. 10B SYSTEM HYDROSTATIC TEST VT-2 ALL CLASS 3 BOUNDARY 0/0 0/0 1/0
~<<<> NOTE lALL COMPONEttTS TO BE EXAMINED EACH INTERVAL 03 '0 INTESRAL ATTACHMENT-COMPONENT VT-3 N/A 0/0 0/0 0/0 SUPPORTS AND RESTRAINTS D3.30 INTEGRAL ATTACHMENT-MECHAttICALVT-3 N/A 0/0 0/0 0/0 AND HYDRAULIC SNUBBERS D3,40 SUPPORTS'/A IttTE6RAL ATTACHMENT-SPRIN6 TYPE VT-3 0/0 0/0 0/0 D3.50 INTESRAL ATTACHMENT-CONSTANT VT-3 0/0 0/0 0/0 LOAD TYPE SUPPORTS e D3.60 INTE6RAL ATTACHMENT-SHOCK ABSGRBERS VT-3 0/0 0/0 0/0
RPPEND IX D CLRSS 1 HRNGER SUI1NRRY TRBLES
DATE: 08/i5/82 ST. LUCIE HUCI.EAR PLANT UNIT I REVISION: } INSERVICE IttSPECTION PLAN FOR THE FIRST INTERVAL CLASS I SECTION XI SUHNARY TABL'E D PAGE.'XAtt CATEGORY F-A - PLATE AHD SHELL TYPE SUPPORTS AsttE 0 OF COtlPONENTS SEC. XI NUNBER OF RELIEF SCHEDULED/COHPLETED I TEil 0 ITEN DESCRIPTION ttETHOD SYSTEtl DESCRIPTION ZONE COttPONENTS REQ. lST PER 2ND PER 3RD PER Fl. l0 ttECKANICAL COtSECTIONS TO VT-3 RCS 0/0 0!0 0/0 PRESSURE RETAINING COttPONEttTS AND BUILDING STRUCTURE
DATE. '08/25/87 ST ~ LUCIE NUCLEAR PLANT Ut(IT I PAGE: 2 REVISION: INSERVICE INSPECTION PLAN FOR THE . IRST INTERVAL CLASS I SECTION XI SUttttARY TABLE D e CATFGORY F-B - LINEAR TYPE SUPPORTS ASttE 0 OF COttPONENTS SEC. Xl NUttBER OF RELIEF SCHEDULED/COttPLETED ITEN tt ITEN DESCRIPTION EXAtt METHOD SYSTEtt DESCRIPTIOM ZONE COttPONENTS REQ. 1ST PER 2ND PER 3RD PER F2. 10 ttECHANICAL CONNECT IOtiS TO VT-3 21 12 I/0 I/O I/O PRESSURE RETAINING COttPOtiENTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 SI 22 I/0 I /0 I/0 PRESSURE RETAI tt1 tt6 COttPOMEMTS AMD BUILDING STRUCTURE F2.10 ttECHANICAL CONNECTIONS TO VT-3 Sl 23 5 1/0 0/0 0/0 PRESSURE RETAININ6 COMPONENTS AND BUILDING STRUCTURE F2.10 ttECHAMIGAL CONNECTIONS TO VT-3 Sl 0/0 I/O 0/0 PRESSURE RETAININ6 COMPONENTS AND BUII.DIN6 STRUCTURE F2. 10 ttECHAMICAL COtttlECT IONG TO VT-3 RCS 0/0 0/0 0/0 PRESSURE RETAININ6 COttPOMENTS AND BUII.DING STRUCTURE F2.10 ttECHANICAL CONNECTIONS TO VT-3 RCS 26 12 1/0 I/O 1/0 PRESSURE REtAINING CONPONENTS AND BUILDING STRUCTURE F2 ~ 10 MECHANICAL CONNECTIONS TO VT-3 RCS 27 10 1/0 1/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2. 10 MECHANICAL COttttECTIONS TO VT"3 RCS 28 0/0 0/0 1/0 PRESSURE RETAINIM6 COttPONENTS AND BUILDING STRUCTURE F2,10 MECH ANICA) CONNECTIONS TO VT-3 RCS 1/0 0/0 0/0 PRESSURE RETAINING COMPONENTS AND BUILDIN6 STRUCTURE F2. 10 NECKAMICAL CONNECTIONS TO VT-3 0/0 1/0 0/0 PRESSURE RETAINING COttPONENTS AMD BUILDING STRUCTURE F2. 10 ttECKAMICAL CONNECTIONS TO VT-3 CH 0/0 0/0 1/0 PRESSURE RETAINING COttPOMENTS AND BUILDING STRUCTURE e
OATEN'8/25/87 ST ~ LUCIE NUCLEAR PLANT UN!T 1 PAGE:
REVISIOttl 1 INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUt!MARY TABLE D ASMiE 0 Of COMPONENTS SEC, XI ttUMBER OF RELIEF SCHEDULED/COMPLETED ITEil tt I TEtl DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COttPONENTS REQ. 1ST PER 2ND PER 3RD PER F2. 10 tlECHANICAL CONNECTIONS TO VT-3 RCS 1/0 1/0 0/0 PRESSURE RETAINING COMPONENTS AiND BUILDING STRUCTURE F2. 10 tlECHANICAL CONNECTIONS TO VT-3 SI 39 10 1/0 1/0, 1/0 PRESSURE RETAINING COMPONENTS ANi D BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 SI 40 13 2/0 1/0 1/0 PRESSURE RETAIitING COMPONENTS AND BUILDING STRUCTURE
08/25/87 ST. LUCIE tlUCLEAR PLAtlT UNIT 1 PAGE:
DATE:
REVISION: INSERVICE IHSPE".TION PLAN FOR THE FIRST INTERVAL CLASS 1 SECTION XI SUtlMARY TABLE. 0 CATEGORY F-C - COMPONENT STANDARD SUPPORTS ASME I OF COMPONENTS SEC. XI tlUMBER GF RELIEF SCHEDULED/COtlPLETED EXAM METHOD SYSTEM DESCRIPTIOH ZONE COMPONENTS REQ, 1ST PER 24D PER 3RD PER ITEM tt ITEM DESCRIPTION F3.10 MECHANICAL CGtlNECT IOHS TO VT-3 RCS 16 , 3 0/0 I/O 0/0 PRESSURE RETAININB COMPONENTS AND BUILDING STRUCTURE F3,10 MECHAtlIGAL CONtlECT TONS TO VT SI 21 17 1/0 2/0 1/0 PRESSURE RETAINING COMPONENTS AHD BUILDING STRUCTURE F3.10 MECHANICAL CONNECTIONS TO VT-3 Sl 22 1/0 I/O 1/0 PRESSURE RETAINING COMPONENTS AND BUILDIN6 STRUCTURE F3.10 ilECHANICAL COilHECIIGHS TO VT-3 SI 0/0 0/0 I/O PRESSURE RETAINING COMPONENTS AHD BUILDIN6 STRUCTURE F3.10 MECHANICAL CONNECTIONS TO . VT-3 Sl 24 13 1/0 1/0 1/0 PRESSURE RETAINltlG COMPONENTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONHECTIONS TO VT-3 RCS 0/0 0/0 1/0 PRESSURE RETAININ6 COMPONENTS AND BUILDING STRUCTURE F3.10 tlECHANICAL CONNECTIONS TO VT-3 RCS 26 0/0 1/0 I/O PRESSURE RETAININB COMPONENTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONNECT IGNS TO VT-3 RCS 27 1/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F3.10 tlECHAHICAL CONNECTIONS TO VT-3 RCS 28 0/0 1/0 0/0 PRESSURE RETAININB COMPONENTS AND BUILDING STRUCTURE F3.10 ttECHANICAL COtlNECTIONS IO VT-3 RCS 29 0/0 0/0 1/0 PRESSURE RETAININ6 COMPONENTS AND BUILDIN6 STRUCTURE F3.10 MECHAHIGAL CONNECTIONS TO VT-3 CH 30 11 1/0 I/O 1/0 PRESSURE BETA ININB COMPONEtlTS AND BUILDIHG STRUCTURE
08/25/87 ST, LUCIE NUCLEAR PLANT UNIT 1 PAGE: 5 DATE:
REV IS ION: 1 iNSERVICE INSPECTION Pt.AN FL'R THE FIRST INTERVAL C~ASS I SECTION XI
SUMMARY
TABLE Q 0 GF COMPONENTS ASME NUMBER OF RELIEF SCHEDULED/COMPLETED SEC. XI ITEtt 4 ITct1 DESCRIPTION EXAM METHOD SYSTEM DESCRIPI'ION ZONE COMPONENTS RED. IST PER 2ND PER 3RD PER F3 ~ 10 ttECHANICAL CONNECTIONS TO VT 0/0 I/O 1/0 PRESSURE RETAININS COMPONENTS AND BUILDING STRUCTURE F3 10 MECHANICAL CONNECTIONS TD VT-3 CH 32 26 2/0 2/0 2/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONNECTIONS TO VT-3 RCS 37 14 I/O I/O 1/0 PRESSURE RETAININS COMPONENTS AND BUILDINS S'TRUCTURE F3 '0 MECHANICAL CONNECTIONS TO VT-3 RCS 1/0 I/O 2/0 PRESSURE RETAININS COMPONENTS AND BUILDING STRUCTURE F3, 10 ttECHANICAL CONNECTIONS TO VT-3 . Sl 3V 17 I/O 2/0 1/0 PRESSURE RETAININS COMPONENTS AND BUILDING STRUCTURE F3. 10 McCHANICAL CONNECTIONS TO VT-3 Sl 40 21 2/0 2/0 2/0 PRESSURE RETAINING CQMPQttENTS AND BUILDING STRUCTURE
RPPEND IN E CLRSS 2 HRNGER SUl1NRRY TRBLES
08/25/87 ST LUCIE NUCLEAR PLAilT UNIT 1 PASE: 1 DATEl REV I 8 IOi'4: 1 INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTION XI SUtlNARY TABLE E CATEGORY F-A - PLATE AND SHELL TYPE SUPPORTS ASNE i 0 OF CONPONENTS SEC. XI NUNBER OF RELIEF SCHEDULED/COtlPLETED EXAN tlETHOD. SYSTEN DESCRIPTION IONE COtlPGNENTS REQ. 1S'I PER 2ND PER ~RD PER ITEtl tt I TEtl DESCRIPTION F l. 10 NECHANICAL CDNttECT I DMS TO VT-5 ALL NDNE 0 0/0 0/0 0/0 PRESSURE RETAINING CONPONENTS AND BUILDING STRUCTURE
DATE: 0B/2'/B7 ST ~ LUCIE NUCLEAR PLANT UNIT 1 PAGEOS 2 REVISION: INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 2 SECTIOH Xl
SUMMARY
TABLE E ASME 4 QF COMPONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEM 0 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONe COMPONENTS REQ. 1ST PER ittD PER 3RD PER F2. 10 tlECKAHICAL CONttECT IONS TO VT-3 SI 0/0 I/O 1/0 PRESSURE RETAINING COMPONENTS AND BUILDIttG STRUCTURE F2 ~ 10 MECHANICAL CONtlECTIOttS 'TO VT-3 HPSI 61 I/O 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 HPSI 62 23 2/0 1/0 2/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIOHS TO VT-3 ASS 1/0 1/0 I/O PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2 10 ttECHANICAL CONNECTIONS TO VT-3 MSS 0/0 1/0 0/0 PRESSURE RETAINIHG CQttPOHENTS AND BUILDIHG STRUCTURE F2. 10 MECHANICAL CONNECTIONS TO VT-3 MSS 65 2 0/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDIHG STRUCTURE F2. 10 MECHANICAL CONNECTIONS TO VT-3 MSS 66 0/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 67 1/0 0/0 0/0 PRESSURE RETAINING COMPQttENTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 0/0 1/0 0/0 PRESSURE RETAINING COMPONEHTS AND BUILDING STRUCTURE F2.10 MECHANICAL CONNECTIONS TO VT-3 iMFH 71 0/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AHD BUILDING STRUCTURE F2. 10 MECHANICAL CONNECTIONS TO VT MFH 72 1/0 '/0 0/0 PRESSURE RETAINING COMPONENTS AttD BUILDING STRUCTiJRE
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNI'T 1 PAGE:
REVISION: INSERVICE INSPECTION PLAN FOR tHE FIRST INTERVAL CLASS 2 SECTION XI SUttttARY TABLE E CATEGORY F-B - LINEAR TYPE SUPPORTS ASNE 0 OF CONPONENTS SEC. Xl NUttBER OF RELIEF SCHEDULED/COHPLETED ITEN tt ITEN DESCRIPTION EXAN ttETHOD SYSTEN DESCRIPTION ZONE COttPONENTS REQ, 1ST PER 2ttD PER 3RD PER F2. 10 ttECHANIC,"L COMt<ECT IOttS TO VT-3 NFM Bj 0/0 1/0 0/0 PRESSURE RETAINING CONPONENTS AND BUILDING STRUCTURE
ST. LUCIE NUCLEAR PLANT UNIT ! PACir t DATE: 08/25/87 REVISIONl I INSERVIC; ItiSPECTIQti PLAN FOR THE FIRST ItiTERVAL CLASS 2 SECTION Xl SUtINARY r TABLE E CATFBGRY F-C - COtlPQNENI'TANDARD SUPPORTS tt OF COtlPQtiENTS ASNE NUtlBER OF RELIEF SCHEDULED/COtlPLETED SEC. XI EXAN NETHOD SYSTEN DESCRIPTIOM IGNE CONPONENTS REQ 1ST PER 2MD PER 3RD PER ITEN tt ITEN DESCRIPTIOM F3. 10 MECHANICAL CONNECTIONS TO VT-3 Sl 44 2/0 3/0 3/0 PRESSURE RETAIN INB CQNPONENTS AND BUILDING STRUCTURE F3.10 NECHANICAL CONNEC'IIONS TO VT-3 HPSI 61 11 1/0 I/0 1/0 PRESSURE RETAINING CGNPONENTS AND BUILDING STRUCTURE F3.10 NECHANICAL CONNECTIONS TO VT-3 HPSI 62 10 1/0 I/O I/O PRESSURE RETAINING CONPONENTS AND BUILDING STRUCTURE F3.10 tlECHANICAL CONNECT IOtiS TO VT-3 iNSS 0/0 I/O 1/0 PRESSURE RETAIMINB CONPONENTS AND BUILDING STRUCTURE F3.10 ?IECHANICAL CONNECTIONS TO 'T-3 tlSS 64 0/0 I/O I/O PRESSURE RETAINING CONPONENTS AND BUILDltiG STRUCTURE F3. 10 NECHAMICAL CGtiNECTIONS I'0 VT-3 NSS 1/0 0/0 0/0 PRESSURE RETAINING CGNPONENTS AND BUILDING STRUCTURE ilECHANICAL CONNECT IOtiS TO VT-3 NSS 66 0/0 1/0 0/0 F3. 10 PRESSURE RETAININ6 COtlPONENTS AMD BUILDING STRUCTURE F3.10 NECHANICAL CGNtiECT IONS TO VT-3 NFli 67 0/0 0/0 I/O PRESSURE RETAINING CQiiPONENTS AND BUILDING STRUCTURE ilECHAMICAL COI'itiECTIONS TO VT-3 "
ilFM 68 }/0 1/0 0/0 F3.10 PRESSURE RETAININB CONPONENTS AND BUILDING STRUCTURE F3,10 NECHANICAL COtiNECTIOMS TO VT-3 HPSI 0/0 0/0 1/0 PRESSURE RETAININ6 COtlPONENTS AMD BUILDltiG STRUCTURE VT-3 HPSI 84 0/0 1/0 0/0 F3. 10 NECHANICAL CGNtiECTIONS TO PRESSURE RETAItilNB CGNPQNEtiTS AND BUILDING STRUCTURE
DATE. '08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PASE: , 5 REVISION: IttSERVICE INSPECTIOtt PLAN FOR THE FIRST INTERVAL CLASS 2 SECTION XI SUttttARY TABLE E CATEGORY F-C - CONPONENT STANDARD SUPPORTS ASi'tE 4 OF CONPONENTS NUNBER OF RELIFF SCHEDULED/CONPLETED SEC. Xl ITEN tt ITEN DESCRIPTION EXAN NETHGD SYSTEtt DESCRIPTION ZONE COttPONENTS RED. IST PER 2ND PER 3RD PER F3. 10 "ECHANICAL CGttNECT IOttS TO VT-3 HPSI 85 1/0 0/0 0/0 PRESSltRE RETAININS COttPONFNTS AND BUILDING STRUCTURE F3.10 ttECHANICAL CGttNiCTIGttS TO VT-3 HPSI 0/0 0/0 1/0 PRESSURE RETAINING CGNPGNENTS AND BUILDING STRUCTURE F3, 10 ttECHAMIGAL CGNttECT IONS TO VT-3 HPSI 87 27 2/0 3/0 2/0 PRESSURE RETAINItt6 CONPONENTS AND BUILDlttB STRUCTURE
RPPENDEN F CLRSS 3 HRNGER SUNNRRY TRBLES
08(25/87 ST ~ LUCIE NUCLEAR PLANT UNiT 1 PAGE' DATE:
REVISION: IMSERVICE IttSPECI'IOM PLAN FOR THE FIRST IMI'ERVAI.
CI.ASS 3 SECTiON XI SUttNARY TABLE F .
CATEGORY F-A - PLATE AND SHELL TYPE SUPPORTS ASNE 0 OF COMPONENTS SEC. XI NUttBER OF RELIEF SCHEDULED/CottPLETED ITEtt 0 ITEN DESCRIPTION EXAM METHOD SYSTEtt DESCRIPTION ZONE COMPONENTS REQ. 1ST PER 2ND PER 3RD PER F I. 10 MECHANICAL CONNECTIONS TO VT-3 CC 102 0/0 0/0 0/0 PRESSURE RETAINIMG COMPONENTS AND BUII.DING STRUCTURE Fl. 10 MECHANICAL CONNECTIONS TO VT-3 110 3 1/0 1/0 1/0 PRESSURE RETAINING COttPONENTS AND BUILDING STRUCTURE
DATE: 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PAGEOS 2 REVISION: 1 INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 3 SECTION XI SUttMARY TABLE F ASt! E I OF COt!PONENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEN tt ITEtt DESCRIPTICM EXAM ttETHOD SYSTEM DESCRIPTION ZONE COt!POMENTS REQ, 1ST PER 2MD PER 3RD PER F2.10 ttECHANICAL CONNECTIONS TD VT-3 CC 100 9 1/0 1/0 0/0 PRFSSURE SETA INltiG COt!PONEtiTS iiMD BUILDING STRUCTURE F2,10 CHAMICAL COMtiECT IOMS 'IO VT CC 101 12 I/O 1/0 1/0 PRESSURE RETAINING CDttPOHENTS AtiD BUILDItiG STRUCTURE F2. 10 I!ECHANICAL COtiNECTIONS TO VT-3 CC 102 24 2/0 2/0 2/0 PRESSURE RETAIMIN6 COttPONENTS AND BUILDING STRUCTURE F2 10 iNECHANICAL COiiNECTIONS TO VT CC 103 14 I/O 1/0 I/O PRESSURE RETAININS COMPONENTS AND BUILDING STRUCTURE I F2. 10 F2.10 t!ECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE ttECHANICRL CONNECT IONG TO PRESSURE RETAINING COt!POMENTS VT"3 VT-3 CC CC 104 105 22 24 1/0 2/0 2/0 2/0 2/0 2/0 AND BUILDING STRUCTURE F2 ~ 1Q t!ECHANICAL COtiMECTIONS TO VT-3 IQii 12 1/0 1/0 I/O PRESSURE RETAIMIMG COHPOMENTS AMD BUILDIN6 STRUCTURE F2. 10'!ECHAMICAL CONtiECTIONS TO VT-3 107 Ih 2/0 I/O I/O PRESSURE RETAINING COMPONENTS AtiD BUlLDINS STRUCTURE F2.10 NECHAiMICAL COMtiECTIOtiS TO VT-3 CiM 108 19 1/0 2/0 2/0 PRESSURE RE'IAIMING COMPONENTS AND BUII.DING STRUCTURE F2.10 ttECHAMICAL CONNECTIONS TO VT-3 CM 109 18 1/0 2/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2.1Q ttECHAMICAL CONNECTIONS TO VT-3 CW 110 16 5/0 5/0 5/0 PRESSURE RETAINING COttPONENTS AND BUILDIN6 STRUCTURE
DATE: 08/25/B7 ST. LUCIE NUCLEAR PLANT UNIT 1 ?AGE:
t REV IS I QM: I INSERVICE INSPECTION PLAN FOR THE FIRST INTERVAL CLASS 3 SECTION XI SUNttARY
'fABLE F CATEGORY F-B - LINEAR TYPE SUPPORTS ASNE 0 OF CQNPOitENTS SEC. XI NUMBER OF RELIEF SCHEDULED/COMPLETED ITEil 0 ITEN DESCRIPT ION EXAtt NETHOD SYSTEM DESCRIPTIQM ZONE CQt!PONENTS RED, IST PER 2ND PER 3RD PER
- 2. 10 MECHANICAL CONNECTIONS TO VT-3 SFC 0/0 1/0 0/0 PRESSURE RETAINING CQttPQNEt<TS AND BUILDING STRUCTURE F2 '0 MECHANICAL CONNECTIONS TO VT-3 112 6 0/0 0/0 I/O PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F2. 10 ttECHANICAL CONhECTIOtlS TO VT-3 113 7 1/0 1/0 0/0 PRESSURE RETAINING CQiNPONEitTS AND BUILDIttG STRUCTURE F2. 10 ttECHANICAL CONNECTIONS TO VT-3 118 7 0/0 1/0 1/0 PRESSURE RETAINING COttPONENTS AND BUILDING STRUCTURE F2 ~ 10 ttECHANICAL CONNECTIONS TO VT-3 120 6 0/0 I/O 0/0
~
PRESSURE RETAItaiNG COMPONENTS AND BUILDING STRUCTURE
DATEl OG/25/87 ST. LUCIE NUCLEAR PLANT UNIT I PAGE: 4 REVISION' INSERVICE INSPECTION PLAH FOR THE FIRST ItlTERVAL CLASS 3 SECTION XI SUtlMARY TABLE F CATE6QRY F-C - COMPONENT STANDARD SUPPORTS ASilE 4 OF COMPONENTS SFC, Xl NUtlBER OF RELIEF SCHEDULED/CQiMPLETED ITEtl tt ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPT IGN ZONE CGtlPONEHTS RED IST PER 2HD PER 3RD PER F3. 10 tlECHAHICAL CONNECTIONS TO VT-3 CC 100 13 1/0 1/0 1/0 PRESSURE RETAINING COMPONEtlTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONNECTIONS TO VT-3 CC 101 17 I/O 2/0 1/0 PRESSURE RETAINING COMPQtlENTS AND BUILDIH6 STRUCTURE F3.10 tlECHANICAL CONttECT IGNS TO VT-3 CC '102 20 2/0 1/0 2/0 PRESSURE RETAININ6 COMPONENTS AND BUILDING STRUCTURE F3.10 MECHANICAL CONNECTIONS TO VT-3 CC 103 15 1/0 2/0 1/0 PRESSURE RETAINING CGilPOHENTS AND BUILDING STRUCTURE F3 10 ilECHANECAL CONNECTIONS TO 'T-3 CC 104 8 0/0 1/0 1/0 PRESSURE REI'AENING COMPONENTS AND BUILDIHG STRUCTURE F3 ~ 10 MECHANICAL CONNECTIONS TQ VT-3 CC 105 21 2/0 1/0 2/0 PRESSURE RETAININ6 COMPONENTS AND BUILDIN6 STRUCTURE F3,10 MECHANICAL CONNECTIONS TO VT"3 CC 106 5 0/0 1/0 0/0 PRESSURE RETAINING COMPONENTS AHD BUILDIN6 S'ERUCTURE F3. 10 MiECHANICAL CONNECTIONS TO VT 3 107 6 0/0 '/0 1/0 PRESSURE RETAIMIHG COMPONENTS AttD BUILDING STRUCTURE F3.10 MECHAitICAL CONNECT IOHS TO VT-3 108 23 2/0 2/0 2/0 PRESSURE RETAINING COMPOHENTS AND BUILDING STRUCTURE F3. 10 tlECHANECAL CONNECTIONS TO V'1-3 109 13 1/0 2/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDIN6 STRUCTURE F3.10 MECHANICAL CONNECTIONS TO VT-3 110 2 0/0 0/0 0/0 PRESSURE RETAINING COtlPONEHTS AND BUILDIH6 STRUCTURE
DATE! 08/25/87 ST. LUCIE NUCLEAR PLANT UNIT 1 PASE:
REVISION: INSERVICE INSPECTION PLAN FQR THE FIRST INTERVAL CLASS 3 SECTIGN XI SUttMARY TABLE F CATECGRY F-C - COMPONENT STANDARD SUPPORTS ASME 0 GF COMPONENTS XI NUMBER OF RELIEF SCHEQULED/COMPLETED SEC.
ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION ZONE COMPONENTS REQ. 1ST PER 2ND PER 3RD PER ITEM 0 F3.10 MECHANICAL CONNECTIONS TO VT-3 SFC 111 6 0/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE F3. 10 tlECHANICAL CONNECTIONS TO VT-3 AFN 112 22 2/0 2/0 2/0 PRESSURE RE'TAINli?S COMPONENTS AND BUILDINS STRUCTURE F3.10 ttECHANICAL CO?1NECTIONS TO VT-3 AFN 113 15 1/0 1/0 2/0 PRESSURE RETAINlttB COMPONENTS AND BUILDING STRUCTURE F3 10
~ MECHANICAL CONNECTIONS TO VT-3 AFtt 114 14 1/0 1/0 2/0 PRESSURE RETAINING CQMPONFNTS AND BUILDINS STRUCTURE F3.10 MECHANICAL CONNECTiONS TO VT-3 115 10 I/O 1/0 0/0 PRESSURE RETAININB COMPONENTS AND BUILDING STRL'CTURE F3. 10 iMECHANICAL CONNECTIONS TQ VT-3 '116 5 0/0 0/0 1/0 PRESSURE RETAINING COMPONENTS AND BUILDI~?IS STRUCTURE F3.10 i ECHANICAL CQ?INECTIONS TO VT-3 AFN 111 6 1/0 0/0 1/0 PRESSURE RETAINI?(G COiiPONENTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONNECTIONS TO VT-3 118 16 1/0 1/0 2/0 PRESSURE RETAININB COMPONENTS AND BUILDING STRUCTURE F3. 10 MECHANICAL CONNECTIONS TO VT"3 II9 16 1/0 2/0 , 1/0 PRESSURE RE'PAINING COMPONENTS AND BUILDINS STRUCTURE
RPPENOI X G RSNE COOE CRSES
APPENDIX G ASME CODE CASES The following is a list of ASNE Code Cases which have been evaluated by FP&L as applicable to the St.Lucie Second Ten Year Inservice Inspection Program and are therefore incorporated into the program.
CODE CASE TITLE N-307-1 Revised Ultrasonic Examination Volume for Class 1 Bolting, Examination Category B-G-l N-335-1 Rules for Ultrasonic Examination of Similar and Dissimilar Metal Welds N-408 Alternate Rules for Examination of Class 2 Piping N-416 Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping N-419 Extent of VT-1 Examinations Category B-G-1 of Table I%3-2500-1 N-424 Qualif ication of Visual Examination Personnel N-426 Extent of VT-1 Examinations, Category B-6-2 of Table IWB-2500-1 36
CODE BOUNDRRY DRR WINGS 8.0 Code Boundary Drawings In this section are all the Code boundary drawings for the Class 1,, 2, and 3 systems. Code Class is designated on each drawing using a letters and and colors. Class 1 systems are color coded RED. and denoted with the letter A boxed. Class 2 systems are color coded BLUE and denoted with the letter B boxed. Class 3 systems are color coded GREEN and the letter C boxed is used.
CODE BOUNDARY DRAWING LIST Dxawing Number Rev. Sheet No. Title 8770-E-80303 1 of 5 Ultimate Heat Sink PSL1-CB-007-1 8770-E-80303 2 of 5 Component Cooling Water PSL1-CB-007-2 3 of 5 System 8770-E-80303 5 of 5 Intake Cooling Water PSL1-CB-007-3 System 8770-E-80306 1 of 2 Miscellaneous Systems PSL1-CB-009-1 8770-E-80307 1 of 3 Main Steam, Feedwater, PSL1-CB-001-1 Thrll Blowdown, Aux. Feedwater PSL1-CB-001-2 3 of 3 and Condensate Storage PSL1-CB-001-3 8770-E-80308 1 of 3 Reactor Coolant System PSL1-CB-002-1 Thru PSL1-CB-002-2 3 of 3 8770-E-80309 1 of 5 Chemical &, Volume Control PSL1-CB-003-1 Thru and Sampling System PSL1-CB"003-2 5 of 5 PSL1-CB-003-3 8870-E-80310 1 of 4 Safety Injection and PSL1-CB-004-1 Thru Shutdown Cooling System PSL1-CB-004-2 3 of 4 8770-E-80311 1 of 2 Containment Spray, Iodine PSL1-CB-005-1 Thru Removal and Refueling PSL1-CB-005-2 2 of 2 Water Systems 8770-E-80312 1 of 3 Fuel Pool Cooling and PSL1-CB-006-1 Thru Waste Gas Systems PSL1-CB-006-2 2 of 3 37
FLORIDR POMER fe LIGHT COMPANY ST. LUCI E NUCLERR PLRNT UNIT NO. 1 RR Na. i SUNNRRY OF INCOMPLETE EXRNINRT IONS PROGRRtl I DENT IF I CRT ION DESCR I PT ION RSNE CODE DESCR I PT I ON OF REL FIG.
ITEN NO. NUMBER I TEf1 NO. CRTEGQRY LIl1ITRTIQN PEg NO. REt1RRKS ZONE 1 SHELI WEl DS CIRC. WELDS 81.18 8-R N/R tlIDDLE SHELL TO LOMER s-2es SHELL Bi.ii SURVEILLANCE SPECI/IEN 81-L il1 COMBINED 8-15.SX 95- 8BX Bi-SKT COVERAGE
'IS-22eeSX BBT-1'fosx BX 68-29.1?X ?BRL-2 Iix 78RLT- ~ 21X 8-288R LOMER SHELL VERTICRL Bio 12 B-R RHTI-ROTATION LUGS 81-PSLR COMBINED 8-283B MELDS 8 -38.56X COVERRGE
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ITEM NO. NUMBER ITEM NQ. CRTEGQRY LIMITRTION REQ NO. REMARKS ZONE 2 28S-82 CLOSURE HER 81.98 B-R ONE SIDE EORM DUE TO TO FLRNGE CONFIGURRTION 288-83R MERIDIONRI 81.22 B-R INSULRTION 288-838 WELD RING
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