ML20087J061
| ML20087J061 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/15/1984 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML18038A638 | List:
|
| References | |
| PROC-840315, NUDOCS 8403220076 | |
| Download: ML20087J061 (129) | |
Text
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O PRESERVICE AND INSERVICE INSPECTION PLAN NINE MILE POINT NUCLEAR STATION - UNIT 2 Y V NOA@ ARA 1 V M@XAWE r
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PRESERVICE AND INSERVICE INSPECTION PLAN TABLE OF CONTENTS
_S_ection Title Page 1-1 1
GENERAL REQUIREMENTS 1.1 SCOPE AND RESPONSIBILITIES 1-1 1.1.1 Applicable Code for Preservice Inspection 1-1 1.1.2 Applicable Code for Inservice Inspection 1-2 1.1.3 Later Codes 1-2 1
1.1.4 Requests for Relief from Code Requirements 1-3 1.1.5 Definition of Terms 1-4 1.2 EXAMINATION AND TEST REQUIREMENTS 1-4 1.2.1 Methods of Examination 1.2.1.1 Volunetric Examination 1-4 1.2.1.2 Surface Examination 1-5 1.2.1.3 Visual Examination 1-5 1.2.2 Pressure Tests 1-5 1.2.3 Inservice Testing of Pumps 1-5 1.2.4 Inservice Testing of Valves 1-6 1.2.5 Inservice Testing of Snubbers 1-6
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1.3 PLANT DESIGN FEATURES TO PROVIDE INSPECTABILITY 1-6
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1.3.1 Weld Contour, Access, and Surface Finish for 1-6 Ultrasonic Examination 1.3.2 Weld Access for Surface Examination 1-7 1.3.3 Weld Access for Visual Examination 1-7 1.3.4 Removable Insulation 1-7 1.3.5 Access Platforms 1-7 1.4 EVALUATION OF EXAMINATION AND TEST RESULTS 1-7 1.5 REPAIRS AND REPLACEMENTS 1-8 1.6 RECORDS AND REPORTS 1-9 1.6.1 Responsibility 1-9 1.6.2 Reports for Preservice and Inservice Inspection 1-9 of Class 1, 2,
and 3 Components and Component Supports 1.6.3 Records of Class 1, 2 and 3 Pressure Tests 1-9 1.7 PRESERVICE INSPECTION PROGRAM SCHEDULE 1-9 i
j 1.8 INSERVICE INSPECTION PROGRAM SCHEDULE 1 1.8.1 Code Class 1, 2,
and 3 Inspection Program 1-10 1.9 FUTURE UPDATES 1-11 i
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Nine Mile Point Unit 2 TABLE OF CONTENTS (Cont) g Section Title Page 1.10 INSERVICE DIAGRAMS 1-11 2
CLASS 1 COMPONENTS 2-1 2.1 SCOPE AND RESPONSIBILITY 2-1 2.1.1 Class 1 Components 2-1 2.2 EXAMINATIONS AND INSPECTIONS 2-1 2.2.1 Preservice Inspection 2-1 2.2.2 Inservice Inspection 2-2 2.3 ACCEPTANCE STANDARDS 2-2 2.3.1 Preservice Inspections 2-2 2.3.2 Inservice Inspections 2-2 2.4 SYSTEM PRESSURE TEST 2-2 2.4.1 Pressure Test Guidelines 2-3 2.5 REPAIRS AND REPLACEMENTS 2-3 2.5.1 Repairs 2-3 2.5.2 Replacements 2-3 ll 2.5.3 Construction Code 2-3 3
CLASS 2 COMPONENTS 3-1 3.1 SCOPE AND RESPONSIBLITY 3-1 3.1.1 Class 2 Components Inservice Diagrams 3-1 3.2 EXAMINATIONS AND INSPECTION 3-1 3.2.1 Preservice Inspection 3-1 3.2.2 Inservice Inspection 3-1 3.3 ACCEPTANCE STANDARDS 3-2 3.3.1 Preservice Inspections 3-2 3.3.2 Inservice Inspections 3-2 3.4 SYSTEM PRESSURE TEST 3-2 3.4.1 Pressure Test Guidelines 3-2 3.5 REPAIRS AND REPLACEMENTS 3-3 3.5.1 Repairs 3-3 3.5.2 Replacements 3-3 3.5.3 Construction Code 3-3 11 l
Nine Mile' Point Unit 2
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TABLE OF CONTENTS (Cont)
Section Title Page 4
CLASS 3 COMPONENTS 4-1 4.1 SCOPE AND RESPONSIBILITY 4-1 4.1.1 Class 3 Components Inservice Diagrams 4-1 4.2 EXAMINATION REQUIREMENTS 4-1 4.2 1 Preservice Inspection 4-1 4.2.2 Inservice Inspection 4-1 4.3 ACCEPTANCE STANDARDS 4-2 4.3.1 Preservice Inspection 4-2 4.3.2 Inservice Inspection 4-2 4.4 SYSTEM PRESSURE TEST 4-2 4.4.1 Pressure Test Guidelines 4-2 4.5 REPAIRS AND REPLACEMENTS 4-3 4.5.1 Repairs 4-3 4.5.2 Replacements 4-3 4.5.3 Construction Code 4-3
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5 INSERVICE TESTING CF PUMPS 5-1 5.1 SCOPE 5-1 5.2 INSERVICE TEST PROCEDURES 5-1 5.2.1 Inservice Tests 5-1 5.2.2 Baseline Values 5-2 5.2.3 Pump Test Schedule' 5-2 5.3 METHODS OF MEASUREMENT 5-2 5.4 RECORDS OF INSERVICE TESTS S-2 6
INSERVICE TESTING OF' VALVES 6-1 6.1 SCOPE AND RESPONSIBILITY 6-1 6.2 TEST REQUIREMENTS 6-1 6.2.1 Preservice Tests-6-1 6.2.2 Inservice Test Requirements.
6-1 6.2.3 Valve Test Schedule-6-2 6.2.3.1 Category A and B Valve Exercising-Schedule 6 6.2.3.2 Category A Valve Leak-Rate Test Schedule 6-3 3
6.2.3.3 Category C Safety Valve and Relief Valve. Test 6-3 iii
Nine Mile Point Unit 2 TABLE OF CONTENTS (Cont)
)
Section Title Page Schedule 6.2.3.4 Category D Valve Test Schedules 6-3 6.2.4 Replacement, Repair, and Maintenance 6-3 6.3 RECORDS AND REPORTS 6-3 6.3.1 Records of Value Inservice Tests 6-4 6.3.2 Valve Inservice Test Plans 6-4 6.3.3 Valve Inservice Test Record 6-5 7
COMPONENT SUPPORTS 7-1
7.1 INTRODUCTION
7-1 7.1.1 Code Editions 7-1 7.1.2 Supports Requiring Examinations and Tests 7-1 7.2 SCOPE AND RESPONSIBILITY 7-2 7.2.1 Scope 7-2 7.2.2 Supports Exempt From Examination and Test 7-2 7.2.3 Integral Attachment Pad Type Boundaries 7-2 7.2.4 Piping Components 7-3 7.3 EXAMINATION AND INSPECTION 7-4 7.3.1 Application of Examination Methods 7-4 7.3.2 Preservice Examination 7-4 7.3.3 Inservice Examination 7-4 7.4 STANDARDS FOR EXAMINATION EVALUATIONS 7-5 7.5 REPAIR PROCEDURES 7-5 7.6 TEST REQUIREMENTS 7-5 7.6.1 Preservice Tests 7-5 7.6.2 Inservice Tests 7-5 7.6.3 Test Procedures 7-6 7.7 CORRECTIVE ACTION 7-6 7.8 EXAMINATION AND TESTING OF SNUBOERS 7-6 7.8.1 Introduction 7-6 7.8.2 Terminology 7-7 7.8.3 Procedures and Equipment 7-8 7.8.3.1 Examination and Test Procedures 7-8 7.8.3.2 Examination and Test Results 7-9 7.8.3.3 Instrumentation and Test Equipment 7-9 7.8.3.4 Maintenance Procedures 7-9 iv l
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Nine Mile Point Unit 2 TABLE OF CONTENTS (Cont) 1 Section Title Page 4
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j 7.8.3.5 Snubber Modification and Replacement 7-10 Procedures 7.8.4 Personnel Qualifications 7-10 7.8.5 Preservice Examination and Operability 7-10 Testing Requirements 7.8.5.1 Preservice Operability Test Requirements 7-10 i
7.8.5.2 Preservice Examination Requirements 7 7.8.5.3 Preservice Thermal Movement 7-11 Examination Requirements 7.8.5.4 Preservice Examination and 7-12 Testing Records 7.8.6 Inservice Examination and Testing 7-12 Require.aents 7.8.6.1 Incervice Examination and Testing 7-12 Programs j
7.8.6.2 Snubber Groups for Inservice Examination 7-12 and Operability Testing Programs 7.8.6.3 Inservice Examination Requirements 7-13 7.8.6.4 Inservice Examination Acceptance Criteria 7-14 7.8.6.5 Inservice Examination Failure Evaluation 7-15 7.8.6.6 Inservice Examination Frequency, Sample 7-16 Size, and Composition 7.8.6.7 Inservice Examination Corrective Action 7-17 4
7.8.6.8 Inservice Operability Testing Requirements 7-18 7.8.6.9 Inservice Operability Testing 7-19 Acceptance Criteria 7.8.6.10 Inservice Operability Testing 7-20 Failure Evaluation 7.8.6.11 Inservice Operability Testing Frequency,
'7-21 Sample Size, and Composition 7.8.6.12 Inservice Operability Testing Methods 7-23 7.8.6.13 Inservice Operability Testing 7-23 Corrective Action 7.8.6.14 Inservice Examination and 7-24 i
Testing Records 7.8.7 Records and Recordkeeping 7-24 7.8.7.1 Requirements 7-24 7.8.7.2 Preservice Records 7-24 7.8.7.3 Inservice Records.
7-24 7.9
SUMMARY
7-25 7.9.1 Preservice Examinations-(Including 7-25'
. Snubbers) 7.9.2 Preservice Testing of Snubbers 7-25 O
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Nine Mile Point Unit 2 TABLE OF CONTENTS (Cont)
Section Title Page 7.9.3 Inservice Examination (Excluding Snubbers) 7-25 7.9.4 Inservice Examination of Snubbers 7-25 7.9.5 Inservice Testing of Snubbers 7-25 8
CODE CASES 8-1 9
REQUESTS FOR RELIEF 9-1 lo PROCEDURES FOR INSERVICE INSPECTION 10-1 AND INSERVICE TESTING 11 PIPING SYSTEM ISOMETRICS 11-1 12 COMPONENT DETAIL DRAWINGS 12-1 13 PIPING AND COMPONENT SUPPORT DRAWINGS 13-1 O
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LIST OF TABLES Table Number Title 1-1 INSERVICE DIAGRAMS 2-1 CCDE CLASS 1 INSERVICE DIAGRAMS 2-2 CODE CLASS 1 PRESERVICE EXAMINATIONS 2-3 COJE CLASS 1 INSERVICE EXAMINATIONS -
FIRST INSPECTION INTERVAL 3-1 CODE CLASS 2 INSERVICE DIAGRAMS 3-2 CODE CLASS 2 PRESERVICE EXAMINATIONS 3-3 CODE CLASS 2 INSERVICE EXAMINATIONS -
FIRST INSPECTION INTERVAL 4-1 CODE CLASS 3 INSERVICE DIAGRAMS 4-2 CODE CLASS 3 PRESERVICE EXAMINATIONS 4-3 CODE CLASS 3 INSERVICE EXAMINATIONS -
FIRST INSPECTION INTERVAL 5-1 INSERVICE TESTING - PUMPS 6-1 INSERVICE TESTING PROGRAM FOR ASME CLASS 1,
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2, AND 3 VALVES N-6-la SYMBOLS USED TO DESIGNATE VALVE TYPES 6-lb SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPES 6-1c SYMBOLS USED TO DESIGNATE VALVE POSITIONS 6-2 CATEGORY C SAFETY AND RELIEF VALVES PS-1 PRESERVICE INSPECTION - PUMP SUPPORTS PS-2 PRESERVICE INSPECTION - VESSEL SUPPORTS PS-3 PRESERVICE INSPECTION - HEAT EXCHANGER SUPPORTS PS-4 PRESERVICE INSPECTION - PIPE SUPPORTS PS-5 PRESERVICE INSPECTION - VALVE SUPPORTS PS-6 PRESERVICE INSPECTION - INTERVENING' ELEMENT ATTACHMENTS TO ASME COMPONENTS S-1 SAFETY-RELATED SNUBBERS vii
Nine Mile Point Unit 2 LIST OF TABLES (Cont)
Table Number Title IS-1 INSERVICE INSPECTION - PUMP SUPPORTS IS-2 INSERVICE INSPECTION - VESSEL SUPPORTS IS-3 INSERVICE INSPECTION - HEAT EXCHANGER SUPPORTS IS-4 INSERVICE INSPECTION - PIPE SUPPORTS IS-5 INSERVICE INSPECTION - VALVE SUPPORTS IS-6 INSERVICE INSPECTION - INTERVENING ELEMENT ATTACHMENTS TO ASME COMPONENTS V-3 VISUAL EXAMINATION V-4 VISUAL EXAMINATION VT-4 O
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LIST OF FIGURES I
Figure Number Title I
7-1 INTEGRAL ATTACHMENT 7-2 PLOT FOR ACCEPT-REJECT OF SNUBBERS t
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Section 1
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GENERAL REQUIREMENTS 1.1 SCOPE AND RESPONSIBILITIES The purpose of the Inservice Inspection Program is twofold.
1.
To provide rules and requirements for monitoring the pressure-containing piping systems, components, and supports of the reactor coolant
- system, portions of the associated auxiliary
- systems, and the emergency core cooling systems in order to provide an assessment of the general overall condition of the reactor coolant boundary.
2.
To provide rules and requirements for performing operability tests on pumps, valves, and snubbers to ensure their continued operational readiness.
Title 10 of the Code of Federal Regulations, Part 50.55a(g) requires preservice inspection, inservice inspection, and inservice testing to be performed in accordance with Section XI of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Rules for Inservice
-~g Inspection of Nuclear Reactor Coolant
- Systems, including 1
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applicable addenda.
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The performance of the Preservice and Inservice Inspection Program shall be the responsibility of NMPC or its designated agents.
This responsibility shall include the requirements contained in IWA-1400(a) through (o) of the Code.
1.1.1 Applicable Code for Preservice Inspection The Preservice Inspection Program for Niagara Mohawk Power Corporation's (NMPC)
Nine Mile Point Nuclear Station - Unit 2 (Unit 2) shall be in compliance with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel
- Code, 1980 Edition, including addenda through Winter 1980 with a
modification for preservice examination of Class 1 and Class 2 components.
The modification shall be the performance of a
preservice volumetric examination on the weld volume defined by the entire wall thickness (t) in all welds where volumetric examination is required (refer to Figures IWB-2500-8,
-9,
-10, and -11 and Figures IWC-2500-4 and
-7).
The weld volume that will be examined exceeds the I
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Nine Mile Point Unit 2 (1/3 t) code requirement shown on the referenced figures for these welds.
In
- addition, appropriate Code Class 2 pipe welds in the residual heat removal system, emergency core cooling system, and containment heat removal system shall be examined.
The extent of the preservice examinations for these systems shall be determined using the requirements of paragraph IWC-1220, Table IWC-2520, Categories C-F and C-G, and paragraph IWC-2411 in the 1974 Edition and addenda through the Summer 1975 addenda of Section XI of the ASME Code.
1.1.2 Applicable Code for Inservice Inspection The Inservice Inspection (ISI) and Inservice Testing (IST)
Programs for Unit 2 shall be developed in compliance with the rules and regulations of 10CFR50.55a(g)(4).
In accordance with the requirements of 10CFR50.55a(g)(4),
this plan shall be revised for the initial 120-month inservice inspection interval and for each successive 120-month inservice inspection
- interval, where necessary, to incorporate the requirements contained in
+ka latest editions and addenda of the ASME Code incorporated by reference in 10CFR50.55a(b)(2) 12 months prior to the date of issuance of the operating license for the initial 120-month interval and 12 months prior to the start of each successive 120-month interval.
In addition, appropriate Code Class 2 pipe welds in the residual heat removal system, emergency core cooling system, and containment heat removal system shall be examined.
The extent of the inservice examinations for these systems shall be determined using the requirements of paragraph IWC-1220, Table IWC-2520, Categories C-F and C-G,
'and paragraph IWC-2411 in the 1974 Edition and addenda through the Summer 1975 addenda of Section XI of the ASME Code.
1.1.3 Later Codes As permitted by paragraphs 10CER50.55a(g)(2) and (g)(4),
NMPC may elect, for certain components, to meet requirements set forth in later editions and addenda of the Code than the editions and addenda specified in the approved Program Plan.
The later Codes selected shall have been incorporated by reference in 10CER50.55(b)(2).
Additionally, use of the later Codes shall be subject to approval by the Nuclear Regulatory Commission.
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1.1.4 Requests for Relief from Code Requirements
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Under the provisions of 10CFR50.55a(g)(5)(iii), relief from i
Code examination and/or test requirements for components,
- supports, or support elements shall be requested in writing to the Nuclear Regulatory Commission when-components or supports are exempted from examination by subsequent editions of the ASME Code incorporated by reference in 10CFR50.55(b)(2) provided other relevant Code requirements are met, or when safety hazards or technical difficulties make examination impractical.
The request for relief shall become part of this plan and part of the component or support examination and test records and shall contain the j
following information.
1.
Identification of the component or
- support, including its name and number as given in the FSAR, its function, and the ASME III Code Class.
2.
The Code requirement that is impractical or the later Code exemption.
3.
The basis for the request for relief.
4.
The inspection periods and intervals for which the requested relief is needed.
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Alternate tests or examinations being proposed when i
Code requirements are impractical.
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The schedule for implementing the alternate tests l
or examinations.
7.
The impact on the overall level of plant quality t
and safety if it is impossible to perform an 3
alternate examination.
8.
The preservice inspection results and the inservice inspection results, if any, for the components or supports for which the relief is being requested.
When the requests for relief are due _to. radiation considerations, the following additional information shall be included:
1.
Total estimated man-rem exposure involved in the examination.
i 2.
Radiation' levels at the test area.
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Flushing or shielding capabilities that might reduce radiation levels.
The components or supports for which relief from examination has been granted by the Nuclear Regulatory Commission will be exempted from the Code examination or test requirement for which relief was requested.
1.1.5 Definitions of Terms AUGMENTED - denotes those inspections or examinations which go beyond the requirements of ASME Section XI.
These inspections / examinations are required by NUREGs, IE bulletins, and other agencies with control over the construction,
- testing, and operation of nuclear power plants.
INSPECTION INTERVAL - denotes the number of calendar years following placement of the power unit into commercial service as defined by Article IWA-2400.
INSPcL11va PERIOD - denotes those divisions of the inspection interval that are covered by this inservice inspection and testing program.
1.2 EXAMINATION AND TEST REQUIREMENTS Periodic examinations and tests are required to be performed on certain Code Class 1, 2,
and 3
pressure-containing components and their supports to ensure continued integrity and operational readiness of the plant throughout its lifetime.
The required examinations and tests for specific components and component supports are identified in subsequent sections of this program.
1.2.1 Methods of Examination The methods of examination used on each component and system shall be in accordance with the requirements in Subarticle IWA-2000 of ASME XI.
These methods are defined belcw.
The specific components and supports to be examined by these methods are given in Sections 2, 3,
4, and 7 of this Plan.
1.2.1.1 Volumetric Examination Volumetric examination is defined as ultrasonics, radiography, and eddy current.
Ultrasonic examination (UT) shall be used most commonly for weld examination, although radiograph (RT) may be used under certain conditions, and 1-4 O
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eddy current (ET) may be specified for examining steam
\\s-generator tubes and heat exchanger tubes.
1.2.1.2 Surface Examination Surface examination is defined as magnetic particle (MT) or liquid penetrant (PT) and shall be used for weld examinations.
1.2.1.3 Visual Examination Visual examination is defined in IWA-2210 as VT-1 through VT-4 and shall be used as follows:
VT-1 Visual examination to determine general condition of components, parts or surfaces for corrosion, cracks, erosion, wear, or physical damage.
VT-2 Locate evidence of leakage from pressure-retaining systems and components during an inservice test, component functional test, or pressure test.
Insulation need not be removed for performance of VT-2 visual examinations.
VT-3 Determine general mechanical and structural
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condition of components and their supports.
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This may require measurement of clearances, checking bolt tightness, and other checks to determine structural integrity.
VT-4 Determine conditions relating to the oeprability of components or devices of mechanical components such as snubbers, pumps,
- valves, component supports and spring and weight-constant hangers.
Disassembly of the components may be required.
1.2.2 Pressure Tests Code Class 1, 2,
and 3 components require system pressure tests each inspection period and hydrostatic tests each inspection interval to meet the requirements of ASME XI.
Detailed requirements for pressure tests are given in Sections 2, 3,
and 4 of this Plan.
1.2.3 Inservice Testing of Pumps Periodic inservice testing shall be performed on all pumps that are (a) ASME Section III, Code Class 1, 2,
or 3, (b)
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Nine Mile Point Unit 2 provided with an emergency power source and required to maintain the plant in a shutdown condition or to mitigate consequences of an accident, and (c) pumps not categorized as Code Class 1, 2,
or 3 but are considered to be safety related.
The pump test program is given in Section 5 of this Plan.
1.2.4 Inservice Testing of Valves Periodic inservice testing shall be performed on ASME III, Code Class 1, 2,
and 3 valves that are required to perform a specific function in shutting down a reactor to maintain the plant in a safe shutdown condition or in mitigating the consequences of an accident.
In
- addition, valves not categorized as Code Class 1, 2,
or 3 which are considered safety related shall also be included in the program.
The valve test program is given in Section 6 of this Plan.
1.2.5 Inservice Testing of Snubbers Periodic inservice operability testing shall be performed on all ASME III, Code Class 1, 2,
and 3 snubbers.
The snubber test program is given in Section 7 of this Plan.
1.3 PLANT DESIGN FEATURES TO PROVIDE INSPECTABILITY ASME III design specifications of Code Class 1
and 2 equipment include the following requirements for inservice inspection:
1.3.1 Weld Contour, Access, and Surface Finish for Ultrasonic Examination All Code Class 1 and 2 welds that require ultrasonic examination are finished and contoured to permit unbroken contact of the ultrasonic transducer with the weld through the couplant medium.
The base metal is clean, free of weld spatter, slag, etc, and the weld has a surface smoothness of 250 rms or better and a
minimum piping longitudinal clearance of 4t + 2 in.
except for extraordinary cases on both sides of the weld centerline on pipe welds, where t is the thickness of the base metal (in inches).
Code Class 1
and 2 welds that require manual volumetric examination can be reached by hand and have a minimum 6-in.
(except in extraordinary cases) radial clearance around surfaces requiring examination.
Welds that will be 1-6
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ultrasonically examined by automatic devices are provided with clearance to accommodate the devices that will be used.
All areas that require ultrasonic examination are tested in an unpainted condition to enhance coupling between the transducer and surface.
1.3.2 Weld Access for Surface Examination Code Class 1 and 2 welds that require surface examination have been provided with a minimum radial clearance of 6 in.
to permit manual access with magnetic particle probes or dye penetrant brushes and sprays.
1.3.3 Weld Access for Visual Examination Welds that require direct visual VT-1, VT-3, or VT-4 examination can be seen either directly with the eye or indirectly by means of optical devices such as mirrors, periscopes, borescopes, or fiberoptics.
In
- additice, mechanical components such as snubbers, supports, spring loaded and constant weight hangers, pumps, and valves which may require disassembly to perform a visual examination are provided with access and clearance within practical limitations to permit required
- testing, removal, and disassembly of the component.
Snubbers are ' removable to facilitate operability tests.
1.3.4 Removable Insulation Insulated welds that require either volumetric or surface examination are provided with removable insulation over the full examination area and with storage space for the removed insulation.
1.3.5 Access Platforms Permanent platforms for inservice inspection access have been provided in many areas, particularly in high radiation areas where personnel exposure must be minimized.
In other areas, space has been provided for erection of temporary scaffolding.
1.4 EVALUATION OF EXAMINATION AND TEST RESULTS The Owner or his agent shall be responsible for the evaluation of the results of each inservice examination and inservice test.
Evaluations shall be performed in accordance -with Article IWA-3000 and other appropriate articles of ASME XI as follows:
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Nine Mile Point Unit 2 Class 1 Components, IWB-3000 Class 2 Components, IWC-3000 Class 3 Components, IWD-3000 Component Supports, IWF-3000 Snubber Tests, IWF-5000 Pump Tests, IWP-3000 Valve Tests, IWV-3000 Test parameter limits for pumps and valves that require inservice testing are listed in Section 5, Pump Testing, and Section 6, Valve Testing.
1.5 REPAIRS AND REPLACEMENTS Repairs to components shall be made in accordance with Article IWA-4000 and other appropriate articles of ASME XI as follows:
Class 1 Components, IWB-4000 Class 2 Components, IWC-4000 Class 3 Components, IWD-4000 Com'aonent Supports, IWF-4000 Pumps and valves shall be repaired in accordance with manufacturers' recommendations.
Replacuments shall meet the requirements of the original Construction Code in accordance with Article IWA-7000 and other appropriate articles of ASME XI as follows:
f T.
Class 1 Components, IWB-7000 Class ? Components, IWC-7000 Class 'J Components, IND-7000 As provided for in IWA-7210(c), replacements may meet all or portions of the requirements of later editions of the Construction Code prcrided that the specific requirements of IWA-7.?lO(c) are met.
Replacement of
- pumps, valves, and supports shall be in accordance with the Owners' specifications.
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1.6 RECORDS AND REPORTS
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1.6.1 Responsibility The Owner or its Agent shall develop and maintain, at Unit 2, a system of documentation to ensure the availability and storage of the following records:
1.
Examination and test plans and schedules.
2.
Reports of examination and test results.
3.
Description of examination, test
- methods, and procedurec.
4.
Reports of evaluations of results.
5.
Reports of 4
corrective actions, repairs, and replacements.
1 1.6.2 Reports for Preservice and Inservice Inspection of Class 1, 2,
and 3 Components and Component Supports The Owner shall prepare plans and schedules for preservice and inservice inspection that will meet the requirements of ASME XI.
Plans and schedules shall be filed with the enforcement and regulatory authorities having jurisdiction at the plant site.
The owner's inservice inspection reports shall be filed with the enforcement and regulatory authorities having jurisdiction at the plant site within 90 days after completion of the inservice inspection.
1.6.3 Records of Code Class 1, 2,
and 3 Pressure Tests The record of the visual examination conducted during a system leakage test or a
system hydrostatic test shall consist of itemization of the number and location, and.
quantification (i.e.,
drops per minute per item) of leaks.
1.7 PRESERVICE INSPECTION PROGRAM SCHEDULE Preservice examinations and operability tests required by ASME XI, Articles IWB, IWC, IWD, IWF, IWP, and-IWV'for Code Class 1, 2,
and 3 components and supports shall be performed prior to initial startup of the plant.
Required preservice examinations and tests for specific Code Class 1, 2,
and 3 components and supports.are described in the subsequent sections of this plan.
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Nine Mile Point Unit 2 1.8 INSERVICE INSPECTION PROGRAM SCHEDULE
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1.8.1 Code Class 1, 2,
and 3 Inspection Program The inservice inspection program for Code Class 1, 2,
and 3 components is based on four consecutive 10-yr inspection intervals covering the 40-yr plant life.
This schedule is in accordance with ASME XI, IWA-2420, Inspection Program B.
The inspection intervals are determined by the number of calendar years from the date of commercial operation as defined by the regulation of the Federal Power Commission, Chapter 1 Title 18, Code of Federal Regulations 101 paragraph 9.D.
The 10-yr inspection intervals may each be decreased or extended (but not cumulatively) by as much as 1 yr.
If the plant is out of service continuously for 6 mo or more, the inspection interval during which the outage occurs may be extended for a period equivalent to the outage.
Each inspection interval is divided into three inspection periods.
The first period ends 3 calendar years after the beginning of the interval, the second period after 7 yrs, and the third period after 10 yrs, coincident with the end of the interval.
Except as provided for in ASME XI, at least 16 percent of the inspections required must be completed by the end of the first period, with credit for not more than 34 percent if additional examinations are completed, and at least 50 percent must be completed by the end of the second period with credit for not more than 67 percent.
One hundred percent of the required inservice inspections must be completed by the end of each 10-yr inspection interval.
A major exception to the above rules occurs in examination of pressure-retaining welds in the reactor pressure vessel that raay be deferred to the end of the 10-yr inspection interval.
This exception and others are discussed in detail in Section 2 of this Inservice Inspection Program for the specific components.
It is intended that the inservice examinations be performed during plant outages such as refueling shutdowns or maintenance shutdowns occurring during the inspection interval.
Inservice tests are intended to be performed during normal plant operation as well as during shutdown periods.
Where the extent of inspections requires the examination of all the components during the first inspection interval, the 1-10
Nina Mile Point Unit 2 i
( ')
components inspected by the expiration of one-third of same the first interval shall be inspected by the expiration of one-third of successive inspection intervals (second 10 yrs, etc).
This rotational basis shall be used throughout the successive inspection intervals insofar as practical.
Where less than all the components are required to be inspected in the first inspection
- interval, a
similar percentage of components not previously inspected (other than the preoperational examinations) shall be required in each successive inspection interval.
Test schedules are given for specific pumps, valves, and snubbers in Sections 5, 6,
and 7 of this plan.
1.9 FUTUF.E UPDATES The test and inspection programs described in this report will be updated 6 months prior to the anticipated date of commercial operation.
1.10 INSERVICE DIAGRAMS Submitted with this program is a set of P& ids that show all systems and portions of systems in Unit 2 that require examination or test.
%)
The inservice diagrams are FSKs or P& ids which are color-coded to facilitate review of the program and contain the following information:
1.
Identification of Code Class 1, 2,
and 3
boundaries.
2.
Identification of Code Class 1,
2, and 3
components.
The inservice diagrams submitted with this program are listed in Table 1-1.
1-11 i
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.f e*
Nino Mile Point Unit 2
()
TABLE 1-1 INSERVICE DIAGRAMS P&ID Figure Number System Breathing Air 9.3-3 Reactor Building Closed-Loop 9.2-3 Cooling Water Containment Atmosphere Monitoring 6.2 Primary Containment Purge 9.4-8 High-Pressure Core Spray 6.3-1 Low-Pressure Core Spray 6.3-4 Reactor Building Equipment Drains 9.3-9 Reactor Building Floor Drains 9.3-9 Air Startup-Standby Diesel Generator 9.5-40 Standby Diesel-Generator Fuel 9.5-40 Fire Protection-Water 9.5-1 Feedwater 10.1-6 Na Inerting System In Preparation Standby Gas Treatment 9.4-8 DBA Hydrogen Recombiner 6.2 Control Building Air Conditioning 9.4-1 Os Control Building Chilled Water 9.4-1 Instrument Air 9.3-1 Reactor Core Isolation Cooling 5.4-9 Reactor Vessel Instrumentation 5.3-1 Containment Leakage Monitoring 6.2 Main Steam 10.1-3 Reactor Coolant (Recirculation) 5.4-2 Control Rod Drive Hydraulic System 4.6-1 Residual Heat Removal System 5.4-13 Service Air 9.3-1 Spent Fuel Pool Cooling and Cleanup 9.1-5 Standby Liquid Control 9.3-17 Main Steam Safety Valves, Vents, 10.1-3 and Drains Service Water 9.2-1 Reactor Water Cleanup 5.4-16 NOTE:
Unit 2 P& ids submitted with the FSAR are provided.
The Inservice diagrams will be submitted April 30, 1985.
{}
e Nine Mile Point Unit 2
[Y
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SECTION 2 1
CLASS 1 COMPONENTS 2.1 SCOPE AND RESPONSIBILITY This section of the plan provides the rules and requirements for preservice inspection and inservice inspection, acceptance standards for flaw indications, system pressure tests, and repairs and replacements for ASME Code Class 1 i
pressure-retaining components and their integral attachments.
2.1.1 Class 1 Components The ASME Code Class 1 inservice diagrams-are listed in Table 2-1.
2.2 EXAMINATIONS AND INSPECTIONS The examinations shall be witnessed or otherwise verified by an Inspector.
/)
2.2.1 Preservice Inspection kJ The preservice examinations required by Article IWB-2000 of ASME Section XI shall be completed prior to commercial operation.
These preservice examinations shall be applied to the component parts identified in Table IWB-2500-1 and shall be extended to include essentially 100 percent of the pressure-retaining welds in all Class 1 components, except i
in those components exempted from examination by IWB-1220(a), (b), and (c) or by an approved request for relief.
In addition to the exemptions mentioned
- above, in Category B-0, control rod drive
- housings, essentially 100 percent of the welds in the installed peripheral control rod drive housings only shall be examined.
Table 2-2 identifies the specific components and parts which require preservice examination, and those which are exempt by 1WB-1220(a),
(b),
(c),
or by an approved request for relief.
{
2-1 m
,-,n-n.
e
+,
Nine Mile Point Unit 2 2.2.2 Inservice Inspection ll The inservice examinations required by Article IWB-2000 of ASME Section XI shall be completed in accordance with the schedule established by Table IWB-2412-1.
These inservice examinations shall be applied to the applicable component parts identified in Table IWB-2500-1 for the first inspection interval.
Components exempted from examination by IWB-1220 or by an approved request for relief shall be excluded from inservice inspection.
Table 2-3 identifies the specific components and parts which require inservice inspection during the first inspection interval and those which are exempted by IWB-1220(a), (b),
(c) or by an approved request for relief.
2.3 ACCEPTANCE STANDARDS j
Acceptance standards shall be in accordance with Article IWB-3000 of the Code.
2.3.1 Preservice Inspections The preservice examinations shall be evaluated by comparing the examination results with the acceptance standards specified in Article IWB-3000.
2.3.2 Inservice Inspections Inservice nondestructive examination results shall be compared with recorded resulta of the preservice examination and prior inservice examinations.
Acceptance of the components for continued service shall be in accordance with the requirements of Article IWP-3000.
2.4 SYSTEM PRESSURE TEST Code Class 1 pressure-retaining components within each system boundary shall be subject to syrtem pressure tests in accordance with the rules and requirements contained in Articles IWA-5000 and IWB-5000 of the ASME Code Section XI.
Final detailed procedures which meet these requirements and the requirements of Pressure Test Guidelines under Section 2.4.1 of this ISI program shall be prepared by the Owner or its Agent.
Prior to use, all system pressure test and hydrostatic test procedures shall satisfy the authorized inspector that the procedures satisfy all requirements of ASME XI.
2-2
Nina Mile Point Unit 2 I) 2.4.1 Pressure Test Guidelines V
System pressure test precedures shall comply with the requirements of Article IWA-5000, and as applicable, Article IWB-5000 for Class 1 components.
The written procedures shall define whether the pressure test is a system leak test or hydrostatic
- test, and shall fully define the pressure test boundaries.
The procedures shall include sufficient detail to identify applicability of the procedure to the component being tested, and shall provide technical adequacy to ensure that the test meets the requirements and intent of ASME XI.
2.5 REPAIRS AND REPLACEMENTS 2.5.1 Repairs Repair procedures for pressure-retaining components and component supports shall meet the rules and requirements contained in Articles IWA-4000 and IWB-4000.
Repair operations shall be performed in accordance with a program delineating essential requirements of the complete repair cycle (IWA-4130).
m k,)
2.5.2 Replacements Articles IWA-7000 and IWB-7000 provide the rules and requirements for replacements.
Replacements are defined as spare and renewal components, appurtenances, and subassemblies or parts of a
component or system.
Replacement also includes the addition of components, such as valves, and system changes, such as rerouting of piping.
2.5.3 Construction Code Repairs and replacements should be in accordance with the Owners' design specification and construction code of the component or system.
Later editions of the construction code or Section III of the Boiler and Pressure Vessel Code either in its
- entirety, or portions thereof, may be used provided they meet or exceed the original construction-code requirements or an engineering ' evaluation is performed justifying use of the later codes.
If the repair welding-cannot be performed in accordance with these requiremants, alternate rules are provided in IWB-4000.
i 2-3 fN j
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Nine Mile Point Unit 2 TABLE 2-1 CODE CLASS 1 INSERVICE DIAGRAMS P&ID System Figure Number High-Pressure Core Spray 6.3-1 Low-Pressure Core Spray 6.3-4 Reactor Building Equipment Drains 9.3-9 Feedwater 10.1-6 Reactor Core Isolation Cooling 5.4-9 Main Steam 10.1-3 Reactor Coolant (Recirculation) 5.4-2 Residual Heat Removal 5.4-13 Standby Liquid Control 9.3-17 Reactor Water Cleanup 5.4-16 O
\\
u NOTE:
Unit 2 P& ids submitted with the FSAR are provided.
The Inservice diagrams will be submitted April 30, 1985.
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COL! CLASS 1 PFESE*TICE E113INATICNS (SYSTEM NAtt IATT*)
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C os p 3-Jark N.).
Sa r*
nea*
PSID or ASME III Mfg.
Part 11entafi-tracinatiot Iten Estaptavnb CAL Llo06 MDI EY<a.CQ4%
EfrAE Etat _ s99E41Retta LIER.E2a le9_.
EM9 314110til Eil19t.Ils salt 92LI' E2mi lit &l _INI N ettE..
RK9Et2 hit i
ESlM I
- 1. This table vill t,e sataitte<1 Pogust 31, 1984
- 2. A takin vill te !.sovided for each syst ee.
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t seeld, pump casing, tat egral attachsszt, bolted connection, etc.
als isent111e4 la sectran II of 153r; see table IED-2500-1.
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CODE Ctaa5 1 13srPYic3'ELA11har133 - f T P ST 15 5'I.C TIJ N 137t978L (ST5TTE Nair tsTt9 I
6
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l Campo-Mark Pa.
Pa rt C Jie ment P&ID or 4532 III Mfg.
Part 11er t i fi-Freatsatin Ites 14vaptions CAL Hock E01
.ETElfW GE454 EEli!
Iltt
$921$lkalE3 ' Likt.h '
1s2.....
229 IAAtittal 211192. h EtiT22[If
- 2d ilWGL IFOL E 9 5 h f_..
ELCE*M LC f
E91fE3 l
,1
- Lis t.ehle will tv sut.mitted Favester 30, 8935.
- 2. a tacts will te ps ov11+a for e 4ch system.
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i O deld, paap Casihg, int egral attachter.t, boltel connection, etc.
aAs inontified. la secta:za II of AS AE; see Table 190-2504-1.
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Nine Mile Point Unit 2
()
SECTION 3 CLASS 2 COMPONENTS 3.1 SCOPE AND RESPONSIBILITY Ihis section of the Plan provides the rules and requirements for preservice inspection and inservice inspection, acceptance stendards for flaw indications, system pressure
- tests, and repairs and replacements for ASME III Code Class 2 pressure-retaining components and their integral attachments.
3.1.1 Class 2 Components Inservice Diagrams The ASME Code Class 2 Inservice Diagrams are listed in Table 3-1.
3.2 EXAMINATIONS AND INSPECTIONS The examinations shall be witnessed or otherwise verified by an Inspector.
3.2.1 Preservice Inspection Tne preservice examinations required by Article IWC-2000 of ASME Section XI shall be completed prior to commercial operation.
These preservice examinations shall be applied to the applicable component parts identified in Table IWC-2500-1.
Table 3-2 identifies the specific components and parts which require preservice examination.
Components exempted from examination by IWC-1220(a), (b),
and (c) or by an approved request for relief shall be excluded from preservice examination, but are listed in Table 3-2.
3.2.2 Inservice Inspection The inservice examinations required by Article IWC-2000 of ASME Section XI shall be completed-in accordance with the schedule established by Table IWC-2412-1 and Section 1.8 of this plan.
These examinations shall be applied to the applicable component parts identified in Table IWC-2500-1 for the first inspection interval.
Components exempted from examination by IWC-1220 or by an approsed request for relief.
shall be excluded from inservice inspection.
4
{O h
3-1 i
Nine Mile Point Unit 2 Table 3-3 identifies the specific components and parts which require inservice inspection during the first inspection interval.
3.3 ACCEPTANCE STANDARDS Acceptance standards shall be in accordance with Article IWC-3000 of the Code.
3.3.1 Preservice Inspections The preservice examinations shall be evaluated by comparing the examination results with the acceptance standards specified in Article IWB-3000.
3.3.2 Inservice Inspections Inservice nondestructive examination results shall be compared with recorded results of the preservice examination and prior inservice examinations.
Acceptance of the components for continued service shall be in accordance with the requirements of Article IWB-3000.
3.4 SYSTEM PRESSURE TEST Code Class 2 pressure-retaining components within each system boundary shall be subject to system pressure tests in accordance with the rules and requirements contained in Article IWA-5000 and IWC-5000 of the ASME Code,Section XI.
Final detailed procedures which meet these requirements and the requirements of Pressure Test Guidelines under Section 3.4.1 of this ISI program shall be prepared by the Owner, or its Agent.
Prior to use, all system pressure test and hydrostatic test procedures shall satisfy the authorized inspector that the procedures satisfy all requirements of ASME XI.
3.4.1 Pressure Test Guidelines System pressure test procedures shall comply with the requirements of Article IWA-5000, and as applicable, Article IWC-5000 for Class 2 components.
The written procedures shall define whether the pressure test is a system lea!c test or hydrostatic
- test, and shall fully define the pressure test boundaries.
The procedures shall include sufficient detail to identify applicability of the procedure to the component being tested, and shall 3-2
Nina Milo Point Unit 2 j
l
'\\
provide technical adequacy to ensure that the test meets the requirements and intent of ASME XI.
3.5 REPAIRS AND REPLACEMENTS 3.5.1 Repairs Repair procedures for Class 2 pressure-retaining components and component supports shall meet the rules and requirements contained in Articles IWA-4000 and IWC-4000.
Repair operations shall be performed in accordance with a program delineating essential requirements of the complete repair cycle (IWA-4130).
I 3.5.2 Replacements Articles IWA-7000 and IWC-7000 provide the rules and requirements for replacements.
Replacements are defined as spare and renewal components, appurtenances, and subassemblies or parts of a
component or system.
Replacement also includes the addition of components, such as valves, and system changes, such as rerouting of piping.
3.5.3 Construction Code
)
Repairs should be in accordance with the Owners' design specification and construction code of the component or j
system.
Later editions of the construction code or Section III of the Boiler and Pressure Vessel Code either in its entirety or portions thereof may be used provided they meet or exceed the original construction code requirements or an engineering evaluation is performed justifying use of the later codes.
If the repair welding can not be performed in accordance with these requirements, alternate rules are provided in IWC-4000.
3-3 1 (/
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N_
i
t Nine Milo Point Unit 2 f
TABLE 3-1 CODE CLASS 2 INSERVICE DIAGRAMS P&ID System Figure Number Breathing Air 9.3-3 Reactor Building Closed-Loop Cooling 9.2-3 Containment Atmosphere Monitering 6.2 Primary Containment Purge 9.4-8 Reactor Building Equipment Drains 9.3-9 Reactor Building Floor Drains 9.3-9 Fire Protection - Water 9.5-1 Standby. Gas Treatment 9.4-8 1
DBA Hydrogen Recombiner 6.2 Instrument Air 9.3-1 Reactor Core Isolation Cooling 5.4-9 Reactor Vessel Instrumentation 5.3-1 Containment Leakage Monitoring 6.2 Main Steam 10.1-3 Reactor Coolant (Recirculation) 5.4-2 Control Rod Drive Hydraulics 4.6-1 High-Pressure Core Spray 6.3-1 t
I Low-Pressure Core Spray 6.3-4 Residual Heat Removal 5.4-13 Service Air 9.3-1 Spent Fuel Pool Cooling and Cleanup 9.1-5 Standby Liquid Control 9.3-17 Reactor Water Cleanup 5.4-16 NOTE:
Unit 2 P& ids submitted with the FSAR are provided.
The inservice diagrams will be submitted April 30,-1985.
)
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Nire stie roint hit 2 l
TABLF 3*2 l
CODE CL ASS 3 INSEFYICE EI A3IE ATICWS - FIWST IN3PECTIDW I??E'T AL (STST EM R & M E LITF9 )
l Caspo-M a rk Ns.
- s rt Cole ment P6ID or 409E 17!
Mfg.
P4rt 7d ea ti f i-Faa sin et t on Ites tresstions CAL 11ock 8DE f
i j
EIsish Gkt11 EllD tatt..
EQ9EllB8L22 lht_ h 122-h2 h ulltli GSL12L_ h E11tS2E11_. I'2d Heal.. m 1 Ea<i.__
EL2CE BEL L
i h21ES:
i 1
l
- 1. This table etAl be subsitted Acoust 31, 1484.
- 2. A table will f.e provided for each syst+s.
j i
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i t
I l.
I 1
t I
t h
t r
abeld, posp casint, integral attachaent, bolted connection, etc.
i a&a identified in section II of Aset: see Table I50-2533-1.
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pine 911e Faitt 3rit 2 1
g TAELF 3-3 t
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CODE CLASS 2 IWStaVICE E(ASINAT!DN - FIRST tr$PECTION 2&TEPVAL (3YS?!d M AK E 1ATF2)
{
l C34p3-Sark No.
Part Cod e sent I&ID or ASMF III Mfg.
Part firt*ifi-tasaleation Ites Laempt&ona CAL Llack NDE 3I5124 G13E%
!(12 34tt._
k22 Edit 21Sk L1LE_!?a IES E!G IIttiktil 71119E_!2s EfttE2E11
?2si 11tg1. 1991 dankst___
Iiggisait 3k1EEt
- 1. This table will te satait ted sovember 20, 1935.
- 2. A taS1w will te provided for each syster.
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h a.els, pump casite, int egr al at t achment, eolted connectism, etc.
[
aAs teentified AB Section II et ASSE; see Tatie 19D-2500-1.
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e 1I
....=.- -
3
Nine Mile Point Unit 2
()
SECTION 4 CLASS 3 COMPONENTS 4.1 SCOPE AND RESPONSIBILITY This section of the plan provides the rules and requirements for preservice inspection and inservice inspection, acceptance standards for flaw indications, system pressure tests, and repairs and replacements for ASME Code Class 3 pressure-retaining components and their integral attachments.
4.1.1 Class 3 Components Inservice Diagrams The ASME Code Class 3 inservice diagrams are listed in Table 4-1.
4.2 EXAMINATION REQUIREMENTS The examinations shall be witnessed or otherwise verified by an Inspector.
)
4.2.1 Preservice Inspection
{G The preservice examinations required by Article IWD-2OOO of ASME Section XI.
shall be completed prior to commercial operation.
These preservice examinations shall be applied to the applicable component parts identified in Table IWC-2500-1.
Table 4-2 identifies the specific components and parts which require preservice examination.
Components exempted from examination by IWD-1220.1 and 1220.2 or by an approved request for relief shall be excluded from preservice examination, but are listed in Table 4-2.
4.2.2 Inservice Inspection The inservice examinations required by Article IWD-2000 of ASME Section XI shall be completed in accordance with the schedule established by Section 1.8 of this plan.
These examinations shall be applied to the applicable compotent parts identified in Table IWD-2500-1.
Table 4-3 identifies the specific components and parts which require inservice inspection during the first inspection interval.
Components exempted from examination by IWD-1220 or by an approved request for relief shall be excluded from inservice inspection, but are listed in Table 4-3.
('
4-1 V)
Nine Mile Point Unit 2 4.3 ACCEPTANCE STANDARDS Acceptance standards shall be in accordance with Article IWD-3000 of the Code.
4.3.1 Preservice Inspections The preservice examinations shall be evaluated by comparing the examination results with the acceptance standards specified in Article IWD-3000.
4.3.2 Inservice Inspections Inservice nondestructive examination results shall be compared with recorded results of the preservice examination and prior inservice examinations.
Acceptance of the components for continued service shall be in accordance with the requirements of Article IWD-3000.
4.4 SYSTEM PRESSURE TEST Code Class 3 pressure-retaining components within each system boundary shall be subject to system pressure tests in accordance with the rules and requirements contained in Articles IWA-5000 and IWD-5000 of the ASME Code,Section XI.
Final detailed procedures which meet these requirements and the requirements of Pressure Test Guidelines under Section 4.4.1 of this ISI program shall be prepared by the Owner, or its Agent.
Prior to use, all system pressure test and hydrostatic test procedures shall satisfy the authorized inspector that the procedures satisfy all requirements of ASME XI.
4.4.1 Pressure Test Guidelines System pressure test procedures shall comply with the requirements of Article IWA-5000, and as applicable, Article IWD-5000 for Class 3 components.
l The written procedures shall define whether the pressure test is a system leak test or hydrostatic
- test, and shall fully define the pressure test boundaries.
The procedures shall include sufficient detail to identify applicability of the procedure to the component being tested, and shall provide technical adequacy to ensure that the test meets the requirement.= and intent of ASME XI.
4-2
Nino Mile Point Unit 2 4.5 REPAIRS AND REPLACEMENTS 4.5.1 Repairs Repair procedures for Class 3 pressure-retaining components and component supports shall meet the rules and requirements contained in Article IWA-4000 and IWD-4000.
Repair operations shall be performed in accordance with a program delineating essential requirements of the complete repair cycle (IWA-4130).
4.5.2 Replacements Articles IWA-7000 and IWD-7000 provide the rules and requirements for replacements.
Replacements are defined as spare and renewal components, appurtenances, and subassemblies or parts of a
component or system.
Replacement also includes the addition of components, such as valves, and system changes, such as rerouting of piping.
4.5.3 Construction Code Repairs should be in accordance with the owners' design specification and construction code of the component or system.
Later editions of the construction code or p)sSection III of the Boiler and Pressure Vessel Code either in
(
its entirety or portions thereof may be used provided they meet or exceed the original construction code requirements or an engineering evaluation is performed justifying use of the later codes.
If the repair welding cannot be performed in accordance with these requirements, alternate rules are provided in IWD-4000.
4-3 lv
Nino Mile Point Unit 2
()
TABLE 4-1 CODE CLASS 3 INSERVICE DIAGRAMS P&ID System Figure Number Remote Building Closed-Loop Cooling 9.2-3 Air Startup-Standby Diesel Generator 9.5-40 Standby Diesel-Generator Fuel 9.5-40 N2 Inerting System In Preparation Control Building Air-Conditioning 9. 4 ~1 r'
Control Building Chilled Water 9.4-1 Instrument Air 9.3-1 Main Steam 10.1-3 Reactor Coolant (Recirculation) 5.4-2 Residual Heat Removal 5.4-13 Spent Fuel Pool Cooling and Cleanup 9.1-5 Main Steam Safety Valves, Vents, and Drains 10.1-13 Service Water
-9.2-1 Reactor Water Cleanup 5.4-16 O
i NOTE:
Unit 2 P& ids submitted with the FSAR are provided.
The inservice diagrams.will be submitted April 30, 1985.
l 1
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l 9
9 9
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f bane tale Point ifLi t 2 v
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r 7&BLP 4-2 j
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i CCDE 61&55 3 PPE3f5VICE E14513471CWS (5f572' 549E LATEP) t Com po-
.tark 92.
Dort meat
?SID or 4.4 5 P III 9fg.
Part IJaktift-Esatisatist Ttes faeaptiske C AL tiact NDE synisa hh Ell 2 tent _. S99Laita!ca L&nt_fEs 122 Ett I!stitT11 U L& 2E_!h Otts2EII_. 1hi imi _.1 HL heltE EIkidsst E2135:
- 1. thta tat Ae vill Le satsit ted a49est 31, n84
- 2. A table will te providet f or each sy4 ten.
I l
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t i
9 I
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I
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te**d, pump cading, int egral e*.tacaseat, boltel coanectama, etc.
e l
aAs 15entifie1 an Sectaan 27
.4 A317:.ee Table IED-25?0-1.
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Nine Mile Point Unit 2 i
r TABLE 4-3
)
F CODE CLASS 3 INSERVICE EXAMINATIOMS - FIRST INSPECTION INTERVAL (SYSTEM NAME LATER) l t
l I
Compo-Mark No.
Part System.
.nent P&ID or ASME III Mfg Part Identifi-Extmination Item Exemptions CAL Block NDE Code P&ID Name Coordinates Line No.
Iso M
Examined 8 cation No.
Category 3 No.a (Yes)
(No)
Number Procedure NOTES:
1.
This table will be submitted November 30, 1985.
2.
A table will be provided for each system.
8 Weld,. pump casing, integral attachment, bolted connection, etc.
aAs identified in Section XI of ASMEr see Table IWD-2500-1.
i l
i J
l l
i Nine Mile Point Unit 2
[d SECTICN 5 INSERVICE TESTING OF PUMPS 5.1 SCOPE This section provides the rules and requirements for inservice testing of ASM III Class 1, 2,
and 3 centrifugal and displacement type pumps that are provided with an emergency power source that are required to perform a
specific function in shutting down the reactor or in mitigating the consequences of an accident.
Pumps not categorized as ASME Code Class 1, 2,
or 3, but considered to be safety-related, are also covered.
These pumps are listed in Table 3-1.
Pumps and drivers that are excluded from testing requirements by IWP-1200 or are exempted from testing by an approved request for relief shall not be tested under this program, but are listed in Table 5-1.
5.2 INSERVICE TEST PROCEDURES
/~N 5.2.1 Inservice Tests Pumps (and drivers when required by the Code) shall be tested in accordance with the rules and requirements contained in IWP-3000, except bearing temperature measurements shall not be required.
Vibration and bearing temperature are two basic parameters that describe the mechanical characteristics of a
pump.
Baseline vibration and bearing temperature values determined under a
specific dynamic load (of
- speed, differential
- pressure, and flow rate) should be reproduced within specified limits during subsequent tests under similar load conditions.
Deviations from baseline values may indicate changes in the mechanical components that require corrective action.
Due to the difficulty in measuring bearing temperature accurately, a total vibration signature program measuring and recording vibration amplitudes over a
frequency range, will be used in lieu of bearing temperature testing.
(]
5-1 V
Nine Mile Point Unit 2 5.2.2 Baseline Values Baseline values are defined as one or more fixed sets of values of the parameters shown in Table IWP-3100-1 as measured or observed when the equipment is known to be operating acceptably.
All subsequent test results shall be compared to these reference values or to new reference values established in accordance with IWP-3111 and IWP-3112.
5.2.3 Pump Test Schedule In accordance with IWP-3400, the pumps identified in Table 5-1 shall be tested nominally once every 3 months when the plant is operating.
Testing should be continued during shutdown periods if this can be accomplished reasonably.
Pumps not tested during plant shutdown must be tested within 1 week after the plant is returned to normal service.
Pumps that require testing, but operate more than once every 3 months, need not be run or stopped in order to run a
special pump test, provided that the same data required by a test are taken when the pump is running in regular service and duplicating the hydraulic circuit used for baseline or reference values.
5.3 METHODS OF MEASUREMENT The methods of measurement and instrumentation used shall meet the requirements contained in IWP-4000.
5.4 RECORDS OF INSERVICE TESTS The records and plans required by IWP-6000 shall be developed and maintained by Niagara Mohawk Power Corporation or its designated agent.
5-2 l
. ~.. _. -. _.. -. _ _ -.. - ~
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N Nine Mile Point Urit 2 1
T AblE 5-1 INSEPYICS TESTING - OUMPS Test Pump AS3E Interval flark Code PSID Applica b ilit v o[_Egga!!!gigEllegdigt (Days)
Test 39t_
Cldgg ELIQ C99Eds E2eed vi P
Q 1
Tb
_J1255L_ ggstes
- rogejgEg 25WP* PIA 3
9.2-1 LTR 92 Service water
.2SWP*fid 3
9.2-1 Lee 92 Service water 2SEP*PIC 3
9.2-1 LTR 92 Service water j
2SEP*P1D 3
9.2-1 LTP 92 Service water 2SEP*P1E 3
9.2-1 LT3 92 Service water 2ShP*P1F 3
9.2-1 ITE 92 Service water 4
2S LS
- P1 A 2
9.3-17 LTR 31 Standby liquid control
~ 2S LS*P1b 2
9.3-17 LTR 31 Standby liquid control 2RHS*P1A 2
5.4-13 LT E 31 Residaal heat removal 22HS*PIB 2
5.4-13 LII.
31 Fesidual heat re mo val 2EHS*P1C 2-5.4-13 L*R 31 Residaal heat reno va l 23HS*P2 2
5.4-13 LTR.
31 Lesidual heat renoval
~2CSL*P1 2
- 6. 3-4 LTE 92 Low pressure core p
spray 2CSL*P2 2
E.3-4 LTE 92 Low pressure core spray Completed tables will be provided July 31, 1984 2
1 of 2
3 O
3 Nine : file Point Uni t 2 1
TAbtE 5-1 (Cont)
Pump ASME Interval Mark Code P t, I D Melicability_of_Egra2eterJIes/Jol (Days)
Test No.
Clagg 2[,lD Coord_ Egeed gi t
g V
_Tb
_J12S}L_ gystem Proce3ure 2CSH*P1 2
6.3-1 LTE 92 High pressure core spray 2CSH*P2 2
6.3-1 Lis 92 Ifi git pressure core spray 2ICS*P1 2
5.4-5 lip 92 Reactor core isol cooling 2ICS*P2 2
S.4-9 LT R 92 Peactor core isol cooling 2SFC*P1A 3
9.1-5 LTE 92 Spent fuel pool cool and cleanup 2SFL*PIB 3
9.1-5 LTS 92 Spent fuel pool cool and cleanup I
l l
{
Cocpleted tables will be provided July 31, 1984 2 of 2
Nine Mile Point Unit 2 p)
SECTION 6 5%.)
INSERVICE TESTING OF VALVES 6.1 SCOPE AND RESPONSIBILITY This section provides the rules and requirements for inservice testing to assess cperational reediness of the ASME Code Class 1, 2,
and 3 valves (and ' '.teir actuating and position-indicating systems) required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident.
In
- addition, valves that are not categorized as Code Class 1, 2, or 3, but are considered safety
- related, are also included in the test program.
Table 6-1 identifies these valves.
Valves exempted from testing by IWV-1200 or by an approved request for relief shall not be tested under this program, but are listed on Table 6-1.
6.2 TEST REQUIREMENTS
s 6.2.1 Preservice Tests (Q
The preservice tests required by 1WV-3100 shall be performed on all of the applicable valves listed in Table 6-1 after installation and prior to service.
6.2.2 Inservice Test Requirements The tests required by IWV-3000 shall be performed on all of the applicable valves identified in Table 6-1 at the testing frequencies specified in IWV-3000.
Nominal valve test requirements are summarized as follows:
Category A
Active valves require exercising once every 3 months and leak testing during scheduled refueling
- outages, but not less than once every 2 yrs.
Valves that perform both a
pressure isolation and a
containment isolation function must be leak tested to satisfy the requirements of both 10CFR50, Appendix J (Type C test),
and ASME XI, IWV-3420.
Valves that perform only a pressure isolation function will be leak tested to satisfy the requirements of ASME XI, INV-3420.
Valves that perform only a containment isolation l/9 6-1 l \\~ 1 l
Nine Mile Point Unit 2 function will be leak tested to satisfy the requirements of
- 10CFR50, Appendix J (Type C test).
Passive valves require only leak testing as described above.
Active valves require exercising once every Category B
3 months.
Passive valves do not require testing.
Category C
- Active valve test requirements vary according to valve type.
Safety valves and check valves may be bench tested or tested in place.
The test schedule is a function of the number of months from startup to testing and of the total number of Category C safety and check valves and is shown in Table 6-2.
Active check valves require exercising once every 3 months.
Passive valves do not require testing.
Category D - Active valve test requirements differ by valve type.
For explosive-actuated
- valves, 20 percent of the charges must be
- removed, fired, and replaced with fresh charges every 2 yrs.
Rupture disk valves require no specific tests except that testable designs shall be tested in accordance with manufacturer's instructions.
Passive valves do not require testing.
ASME Section XI, Article IWV, provides for alternative means and schedules for testing valves that cannot be tested as described above.
6.2.3 Valve Test Schedule Valve test schedules vary depending on the parameter tested and the test category of eacn valve.
6.2.3.1 Category A and B Valve Exercising Schedule Category A and B
valves chall be full-stroke exercised at least once every 3 months.
If they cannot safely be fully stroked when the plant is operating, the valves shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdown.
A schedule of the valves shall be developed and maintained.
Valves in regular use that operate in the course of plant operation at frequencies that will satisfy the exercising requirements will not be additionally exercised, provided that the observations required by the valve test program are made and analyzed during plant operation and are recorded at intervals of not more than 3 months.
Valves in systems that are not operable need not be exerci sed in accordance with the test schedule.
In such 6-2 l
l
Nine Mile Point Unit 2
[
\\
- cases, they shall be tested within 30 days prior to the return of the system to operability.
6.2.3.2 Category A Valve Leak Rate Test Schedule Category A valves shall be leak rate tested at least once every 2 years.
6.2.3.3 Category C Safety Valve and Relief Valve Test Schedule Category C safety valves and relief valves shall be tested in accordance with the schedule in ASME XI in Table IWV-3510-1.
6.2.3.4 Category D Valve Test Schedules Every 2 yrs at least 20 percent of the charges in explosively actuated valves shall be
- removed, fired, and replaced with charges from a fresh batch.
If any charge fails to fire, all charges with the same batch number shall be
- removed, destroyed, and replaced with charges from a fresh batch from which a
sample charge shall have been tested satisfactorily.
r~s 6.2.4 Replacement, Repair, and Maintenance When a
valve or its control system has been replaced or repaired or undergone maintenance that could affect its performance, and prior to the time it is returned to
- service, it shall be tested to demonstrate that the performance parameters that could be affected by the replacement, repair, or maintenance are within acceptable limits.
NOTE Adjustment of stem packing; removal of the bonnet, stem assembly, or actuator; and disconnection of hydraulic or electrical lines are examples of maintenance that could affect valve performance parameters.
6.3 RECORDS AND REPORTS Records of test results required by IWV-6000 shall be developed and maintained by Niagara Mohawk Power Corporation or its designated agent.
ex 6-3 i
a
\\,_/
Nine Mile Point Unit 2 6.3.1 Records of Valve Inservice Tests A
list of valves shall be maintained to record the current status of the test program.
When a valve is successfully
- tested, only the date of the successful test is required to be listed.
In addition, the Owner, or its
- Agent, shall maintain a
- record, that shall include the following, for each valve covered by the inservice test program:
The manufacturer and the manufacturer's model and serial or other identification number.
A copy or summary of the manufacturer's test report, if available.
6.3.2 Valvo Inservice Test Plans The valve inservice test plan shall include the following:
Valve number Coordinates on P&ID drawings Valve manufacturer Valve nominal size Valve type Actuator type Stroke time (for power actuated valves)
Leakage rate (for Category A valves)
Setpoint (for relief valves)
ASME III Code Class valve Valve test category Normal position Safety function position Active or passive Position indication Test parameters 6-4
Nine Mile Point Unit 2
('
Feasibility of testing valve during normal plant operation i
Comparison of Technical Specification and inservice test requirements Exceptions taken to performing valve tests Valve test procedures 6.3.3 Valve Inservice Test Record The valve test record shall include the following:
Date of test Measured and observed quantities i
Identification of instruments used Comparisons with allowable ranges of test valves and analysis of deviations Requirements for corrective action Signature of the person or persons responsible for O
conducting and analyzing the test 4
i 1
I d
h 4
6-5
F Nine Mile Point Unit 2 TABLE 6-1 INSERVICE TESTING PROGRAM FOR ASME CLASS 1, 2, AND 3 VALVES t
System: Main Steam i
t
?
Valve Valve ASME Ca tego ry Active Actu-Norma l Testing Ma rk Code P&lD ASME XI or Size Va lve a to r Posi-Test Relief A l te r-Test Number Class PhlD Coo rd A B C D Pa s s ive ( 10. ) Type
- Type
- tions* Reauirement Reauest native Procedu re
[
2 MSS-4 X
16 CA A
O A0V92A 2 MSS-4 X
16 GA A
O A0V928 2 MSS *.
1 X
X 10/8 RL SA/A C PSV120
~
i 2 MSS
- 1 X
X 10/8 RL SA/A C PSV121 2 MSS *
.1 X
X 10/8 RL SA/A C PSV122 i
iz
.2 MSS
- 1 X
X 10/8 RL SA/A C
?
PSV123 PMS$*
1 X
-X 10/8 RL SA/A C PSV124
(
2 MSS
- 1 X
X 10/8 RL-SA/A C
(
t PSV125 2 MSS
- 1 X
X 10/8' RL SA/A C l
PSV126 4
j 2 MSS
- 1 X
X 10/8 RL SA/A C PSV127 l
2 MSS
- 1
~X X
10/8 RL SA/A C PSV128
{
2 MSS
- 1 X
X 10/8 RL SA/A C PSV129 t
1 of 27 i
i I
i i
i l
i i
I I
t Nine Mile Point Unit 2 d
i i
TABLE 6-1 (Cont) i I
j_
System: Main Steam j
i Valve Valve ASME Category Active Actu-Normal Testing 2
1 Mark Code PhlD ASME XI or Size Valve ator Posi-Test Roller Al te r-Test i
f i
Number Class Phl0 Coo rd A D G Q Passive (In.1 Type
- Type
- tions* Reauirement Reauest native Procedu re
]
2 MSS
- 1 X
X 10/8 RL SA/A C j
PSV130 2 MSS
- 1 X
X 10/8 RL SA/A C PSV131 I
i
.2 MSS
- 1 X
X 10/8 RL SA/A C i
PSV132
?
f f
2 MSS
- 1 X
X 10/8 RL
$A/A C j
PSV133 i
i
}
2 MSS
- 1 X
X 10/8 RL SA/A C i
PSV1386
[
I 2 MSS
- 1 X
X 10/8 RL SA/A C 3
PSV135 l
)
l 241SS* '
1 X
X 10/8 RL SA/A C L
i PSV136 i
2 MSS
- 1 X
X 10/8 RL SA/A C r
i PSV137 i
e 1
i i
t i
I I
t i
l 1-f
?
i l
l 2 or 27 i
t i
t
. - _ _ ~. - - - - - - -. - _ _. -.. _ _ _ - - - - - -... - _ _. - - -,.
I
--~..-.--._...
-...~.._ _.._.-_~. -.
-- ~._ -...
i O
l Mine Mile Pcint Unit 2 l
l l
l TABLE 6-1 (Cont) t I
System:. Auxiliary Steam i
i i
Valve e
l-
. Valve ASME Ca tegc ry Active Actu-Normal Testing i
Ma rk Code PklD ASME XI or Size Valve stor Posi-Test Relief Alter-Test l
Number Class Par 1D Coo rd A B C g Pa ssive f In. ) lype.* Type
- tions* Reauirement Reauest native Procedure
{
6 l
2 ASS-4 X
6 GA MO O
t KOV148
[
3 I
i r
t t
T I
t
+
f.
y I
1 p
1
?
I t
l-I i
i i
1 I
i l
4 e
8 g
i I
I i
l i
3 of 27 l
s-1 t
4 l
4 I
- >'(*F!I
.ff:
{f l(!
fIk
-k
!i h
iil!
Ii 6!:6ki ~
,i1 i 1 I!
e r
u d
. O e
tc so er TP g
ne irv tei stt el a tan t
fs ee iu l a ee RR t
n em er i
tu sa ee TR l
2 as t
min i
)
rso n
t ooi U
n NPt O
o t
C ure 7~
n
(
i top 2
o 1
cty P
Aal A f
G l
L lve 4
6 o
e e*
E p
l M
B ay A A
Vl C e
i T
)
r i
m e.
N a
zn e
ii t
Sf 4
S ev t
e i s
v u
i s a
trs h
coa x
A P E
d Q
n a
y1 rxC l
eo a
vgE e
l eM B X L.
S atS VaA d
- C A
na d
l Dr G
I o r
&o o
PC ta r
e D
n l
r e
a G
P n
s e
i Ees Mda b
Sol r
ACC u
T m
r 1
e e e 2
t vkb E1 s
l rm MV y
aau TO S
VMN
.2A 1
- !
- !iij.lii l.
hi}<ljl12 'ii3 9 i -
iiiflIl$3 ;
i4l li41'
- !:!t 1 ; Il l!4
i
(%d Nine Mile Point Unit 2 i
TABLE 6-1 (Cont)
System: Reactor Building Equipment Drains Valve Valve ASME Ca tego ry Active Actu-Norma l Testing Ma rk Code PalD ASME XI or Size Valve ator Posi-Test Relief A l te r-Test Number Class Pk1D Coo rd A B g Q Passive f in. ) lyp3* Type
- tions* Reauirement Reauest native Procedure 2 DER
- 2 X
4 CA MO O
MOV119 2 DER
- 2 X
4 CA MO O
MOV120 2 DER
- 1 X
2 CL MO C
MOV128 2 DER
- 1 X
2 CL MO C
MOV129 2 DER
- 2 X
2 CL MO O
MOV130
' 2 DER
- 2 X
2 CL MO O
MOV131 l
2 DER
- 2 X
3/4 CL M
O V28 20ER*
2 X
3/4 CL M
O t
V29 l
2 DER
- 2 X
3/4 CL M
C V30 l
2 DER
- 2 X
is PC M
O l
l V300 r
5 of 27 1
P
a Nine Mile Point Unit 2 TABLE 6-1 (Cont) 1 System: Nuclear Boiler instrumentation VaIvo Valve ASME Ca tego ry Active Actu-Normal Testing Mark Code P&lD
_ASME XI or Size Valve ator Posi-Test Retlef A l te r-Test
!!umbe r Class P&lD poord A l} C [} Pa ss ive LIM Typ_e* lype* hns* Requirement Request native Procedure 2iSC*
2 X
24 CK SA C
RV33A 2BSC*
2 X
24 CK SA C
RV33B 2lSC#
2 X
214 CK SA C
RV34A I
2tSC*
O X
24 CK SA C
RV314B 1
21SC*
2 X
24 CK SA C
RV35A J
21SC*
2 X
24 CK SA C
l RV350 2lSC#
2 X
24 CK SA C
RV36A 1
2BSC*
2 X
? 8' CK SA C
RV36B 4
6 of 27 i
i m
'. i
,1 ;
- . U 4
4j a
Nine Mile Point Ursit 2 y
,h f
A j
~'
TAq.e.E 6-1 (Contt f
4 j a-
{~ I!
+
System:' Ha'in, Steam Sa fety 'and Rel ier Va lve-Vents,and Dra ino I
'., i 2
I Valve i
4 Ma rk Code
.P&lD
_ASME XI
. Active}
Actu-Normal Testing Valve ASME Category or i Size Va l ve a to r Posi-Test.
Roller Alter-Test Number-,
Class P&lD Coord A B C D Passiva [hl Jype* Iyne" tions* Reauirement Reauesi native Procedu re j'
2 SW*
3 X
X 6
r z
RW101
(
2SW*
3 X
X 6
RL' SA C
5 RW102 i
2 SW*
3 X
X 6
RL SA C
RVV103 2 SW*
3 X
X 6
RL SA C
I l
RW1034 3
2SW*
3 X
X 6
RL SA C
RW105 -
2SW*
3 X
X 6
RL SA C
RW106 i
J 2SVV*
3 X
X
. 6 RL SA C
RW107 2SW*.
3 X
X 6
RL SA C
3 RW108 -
2SW*
3 X
X 6
RL SA C
l RW109 t
t 2SVV*
3-X X
6 RL SA C
RW110 2SVV*
3 X
X 6
RL SA C
RW111 2SW*
. 3 X
X 6
RL SA C
RW112 2SW*
3 X
X 6
RL SA C
RW113 7 or 27 i
i-3
. ~....
. ~~
\\
1 Nine Mile Point Unit 2 1
TABLE 6-1 (Cont) l System: Main Steam Safety and Relier Valve Vents and Drains Valve Valve ASME Ca tego ry Active Actu-Normal Testing i.
Ma rk Code P&lD ASME XI or Size Valve ator Posi-Test Relief A l te r-Test Number.
Class P&lD Coo rd A B C Q Passive f In. ) Type
- Type
- tions* Reauirement Request native Procedu re 2SW*
3 X
X 6
RL SA C
4 l
RW114 2SW*
3 X
X 6
RL SA C
RW115 2SVV*
3 X
X 6
RL SA C
RW116 I
2SW*
3 X
X 6
RL SA C
RVV117 f
2SW*
3 X
X 6
RL SA C
r i
RW118 c
i 2SW*
3 X
X-6 RL SA C
RW201 l
2SW*
3 X
X 6
RL SA C
a RW202 1
i 2 SW*
3 X
X 6
RL SA C
i RW203 l
^
, 2SW*
3 X
X 6
RL SA C
j RW204 2SW* '
3 X
X 6
RL SA C
RW205 I
2 SW*
3 X
X 6
RL-SA C
RW206 2SVV*
3 X
X 6
RL SA C
RW207 2SW*
'3 X
X 6
RL SA C
RW208 l
l 8 of 27 i
J t
4
- -. - _ ~
- ~.
4 O
L 4
Nine Mlle Point Unit 2 l
TABLE 6-1 (Cont) l System: Main Steam Safety and Relier Valve Vents and Drains Valve Valve ASME Ca tego ry Active Actu-Normal Testing i
Mark Code P&lD ASME XI or Size Valve ator Posi-Test Relier A l te r-Test J.ype* J.ype" Rons* Reau i rement Reauest native Procedure i
i Number Class P RD poo rd A B g 0 Passive fin.)
e 2SW*
3 X
X 6
RL SA C
RW209 2SVV*
3 X
X 6
RL SA C
RW210 t
2 SW*
3 X
X 6
RL SA C
i RW211
- 2SW*
3 X
X 6
RL SA C
. RW212 i
2SVV*
3 X
X 6
RL SA C
RW213 2SVV*
3 X
X 6
RL SA C
{
RW214 I
i 2SVV*
3 X
X 6
RL SA C
j' RW215 1
2SvV*
3 X
X 6
RL SA C
RW216
~ 2SW*
3 X
X 6
RL SA C
RW217
+
2SW*
3 X'
X 6
RL SA C
RW218 2SW*
3 X
X 6
RL SA C
j RW301 2 SW*
3 X
X 6
RL SA C
l RW302 t;
2SW*
3 X
X 6
RL SA C
j f
' RW303 a
9 of 27 j
i 3
.._m_____.
.m i
l I
Nine Mile Point Unit 2
?
TABLE 6-1 (Cont)
System: Main Steam Safety and Relief Valve Vents and Drains i
Valve
~
~ Valve ASME Category Active Actu-Norma l Testing Mark Code PalD ASME XI or Size Valve ator Posi-Test Relief Alter-Test Numb _e_t Class PaclD Coord A B C Q Pa ss ive f in.1 Tyne* lyp_e" t ions
- Requirement Reauest native P rocedu re j
e 2SVV*
3 X
X 6
RL SA C
RW304 2 SW*
3 X
X 6
RL SA C
RW305 2SVV*
3 X
X 6
RL SA C
j RW306 l
2 SW*
3 X
X 6
RL SA C
I RW307 2 SW*
3 X
X 6
RL SA C
I RW308 2SW*
3 X
X 6
RL SA C
RW309 2SVV" 3
X X
6 RL SA C
RW310 2 SW*
3 X
X 6
RL SA C
RW311 2SVV*
3 X
X.
6 RL SA C
RW312 2SW*
3 X
X 6
RL SA C
RW313 2SW*
3 X
X 6
RL SA C
RW314 4
2SVV*
3 X
.X 6
RL SA C
l RW315 l
2SW*
3' X
X 6
RL SA C
RW316 i
t l
10 of 27 i
1 4
w:
e
I i
V O
i
)
1
[
l t
Nine Mile Point Unit 2 I
i o
)
TABLE 6-1 (Cont)
I i
r I.
. System: Main Steam Safety and Relief Valve Vents and Drains j
Valve Valve ASME Ca tego ry Active Actu-Normal Testing Ma rk Code P&lD ASME XI or
. Size Valve ator Posi-Test Relief A l te r-Test Typ_e* Type
- tions* Reauirement Reauest native Procedure Number-Class P&lD Coo rd A B G D Passive ( In. )
e 2SW*
~3
'X X
6 RL SA C
[
RW317 2SW*
3 X
X 6
RL SA C
]
RW318 -
,1 I
i l
1 i
I i
t I
I i
j
[
11 of 27 e
I i,
I
~
f I.
t.
. ~. -.
~. _ _. _ _ - _ _.,.. _ _. _... _..
4 4
Nine Mile Point Unit 2 TABLE 6-1 (Cont)
System: Residual Heat Removal i
Valve Valve ASME Ca tego ry
. Active Actu-Normal Testing Mark Code P&lb ASME XI or Size Va l ve a to r Posi-Test Relief A l te r-Test Number Class Pa;lD Coo rd 6 0 C Q Passive (In.) lyp_e* Type
- tions* Reauirement Reauest fla t ive P rocedu re e
2RHS*
2 X
24 BF MO O
Clov MOVIA 2RHS*
2 X
24 BF MO O
Clow MOV1B 2RHS*
2 X
24 BF MO O
Clow MOVIC 2RHS*
2 X
18 BF MO C
Clow MOV2A 2RHS*
2 X
18 BF MO C
i
'MOv2B 2RHS*
2 X
6 CA MO O
MOV4A
[
2RHS*
?
X 6
GA MO O
I MOV4B 2RHS*
2 X
6 CA MO O
i MOV4C 4
l 2RHS*
2 X
18 BF MO O
Clow l
MOV8A 2RHS*
2 X
18 BF MO O
Clow MOV8B l
2RHS*
2 X
18 BF MO O
Clow f
MOV9A 2RHS*
2 X
18 BF MO O
Clow 2
-MOV9B 2RHS*
2 X
18 BF MO O
Clow j
MOVl2A
- l-12 of 27 3
1 e
l
{
t t
l Nine Mile Point Unit 2 TABLE 6-1 (Cont)
System: Residual Heat Removal i
Valve Valve ASME Ca tego ry Active Actu-Normal Testing Mark Code P&lD ASME XI or Size Valve ator Posi-Test Relief A l te r-Test Number Class P&l0 Coo rd A B g D Passive (In.) Type
- Type
- Lipns* Reauirement Reauest native P rocedu re 2RHS*
2 X
18 BF MO O
MOV128 i
2RHS*
2 X
16 CA MO C
MOV15A
.2RHS*-
2 X
16 CA MO C
MOV158 2RHS*
2 X
8 CL MO C
MOV22A 2RHS*
2 X
8 GL MO C
l MOV2?'-
2RHS*
2 X
8 CL MO C
l MOV23A 2RHS*
2 X
8 GL MO C
MOV23B s
2RHS*-
2 X
12 GA MO C
MOV24A 2RHS*
2 X
12 GA MO C
=
MOV24B 2RHS*
2 X
12 GA MO C
MOV24C 2RHS*
2 X
16 CA MO C
1 MOV25A 2RHS*
2 X
16 GA MO C
j-MOV258 2RHS*
2 X
1 CL MO C
MOV26A
?
1 4
13 of 27 f
I l
4 Nine Male Point Unit 2 TABLE 6-1 (Cont) i l
System: Residual Heat Removal i
i Valve Valve ASME Category Active Actu-Normal Testing Mark Code P&lD ASME XI or Size Valve stor Posi-Test Relief A l te r-Test
. Number GJ a_11 Pael D Coo rd A B C Q Passive fin.) Type
- Type
- tions* Reau i rement Reauest native P rocedu re 2RHS*
2 X
1 GL MO C
MOV268 2RHS*
2 X
1 GL MO C
1 MOV27A 2RHS*
2 X
1 GL MO C
j MOV27B
?
2 2RHS*
2 X
18 BG MO O
Clow 2
MOV30A i
4 2RHS*.
2 X
18 BF MO O
Clow MOV30B 2RHS*
2 X
4 CA MO C
MOV32A 2RHSu 2
h 4
GA MO C
imV32B 2RHS*
2 X
4 GL MO C
i MOV33A i
2RHS*
2 X
4 GL MO C
i MOV33B 4
i 2RHS*
2 X
4 GL MO C
MOV37A 2RHS*
2 X
4 GL MO C
l MOV37B 2RHS*
1 X
12 CL MO C
r MOV40A 2RHS*
1 X
12 GL MO C
MOV40B 14 of 21 d
~
-... ~. ~. _
- ~.
4 Nine Mile Point Unit 2 TABLE 6-1 (Cont) i System: Residuai Heat RemovaI 1
I i
Valve Valve ASME Category Active Actu-Norma l Testing 1
Mark Code P&lD ASME XI or Size Va l ve a to r Posi-Test Relier Alter-Test i
Number-Class P&lD Coo rd A Q C D Pa s s i ve fin.) Type
- Type
- tions* Requirement Reauest native Procedure i
2RHS*
1 X
2 CL MO C
MOV67A 2RHS*
1 X
2 CL MO C
j MOV678 2RHS*
1 X
6 CL MO C
MOV104 2RHS*
1.
X 20 GA MO C
MOV112
^
2RHS*
1 X
20 CA MO C
-MOV113 2RHS*
2 X
16 CA MO C
MOV115 2RHS*
3 X
16 CA MO C
j
.MOV116 f
2RHS*
2 X
3
'CL MO C
MOC142 i
2RHS*
2 X
3 CA M0 C
Mov149 i'
2RHS*
1 X
X 12 CK A
C A0V16A:
2RHS*
1 X
X 12 CK A
C AOV16B 2RHS*
1 X
X 12 CK A
C AOV16C 1
l 2RHS*
1 X
X.
12
-CK A
C, A0V39A i
15 of 27 4
t r
l
O i
Nine Mile Point Unit 2 I
TABLE 6-1 (Cont)
System: Residual Heat Removal Va1ve Valve ASME Ca tego ry Active Actu-Normal Testing Mark Code P&lD ASHE XI or Size Valve ator Posi-Test Relief A l t e r-Test Number Class P&lD Coo rd A B Q Q Passive (In.) Type
- Type
- tions* Reau t rement Reaueg1 native f rocedu re r
2RHS*
1
-X X
12 CK A
C AOV396 2RHS*
2 X X 16 CK A
C 1
AOV150 2RHS*
2 X
X 4/6 RL SA C
Safety /
SV34A Relief 6
2RHS*
2 X
X 4/6 RL SA C
Sa fe ty/
SV34B Relier 2RHS*
2 X
X 6/8 RL SA C
Safety /
SV62A Relief 2RHS*
2 X
X 6/8 RL SA C
Safety /
SV62B Retief 2RHS*
2
.X X
3/4/ 1 RL SA C
RV20A
}
2RHS*
2 X
X 3/4/ 1 RL SA C
RV208 2RHS*
2 X
X
'3/4/ 1 RL SA C
RV20C t
i 2RHS*
2 X
X 3/4/ 1 RL SA C
j RV42A i
l 2RHS*
2 X
X 3/4/ 1 RL SA C
RV42B 2RHS*
2 X
X 3/4/ 1 RL SA C
RV56A j
2RHS*
2 X
-X 3/4/ 1 RL SA C
RV56B 4
16 of 27 l
i
____.m.
e
(
Nine Mile Point Unit 2 TABLE 6-1 (Cont) t System: Residual Heat Removal
' Valve Valve ASME Ca tego ry Active Actu-Normal Testing Ma rk Code P&lD ASME XI or Size Valve ator Posi-Test Relief Alter-Test Coond A B C D Pass ive ( In.1 Type
- Type
- t ions
- Reauirement Request native Procedu re Nutber Class P&l0 o
i 2RHS*
2 X
X 3/4/ 1 RL SA C
RV61A 2RHS*
2 X
X 3/4/ 1 RL SA C
RV61B 4
2RHS*
2 X
X 3/4/ 1 RL SA C
RV61C 2RHS*
2 X
X 3/4/ 1 RL SA C
T.108 i
2RHS*
2 X
X 3/4/ 1 RL SA C
RV110
?RHS*
2 X
X 3/4/ 1 RL SA C
MV139 I
2RHS*
2 X
X 3/4/ 1 RL SA C
RV152 i
i 2RHS*V1 2
X X 18 CK SA C
r 2RHS*V2 2
X X 18 CK SA C
4 2RHS*V3 2
X X 18 CK SA C
2RHS*V7 2
X X 6
CK SA C
2RHS*V8 2
X X
.6 CK SA C
2RHS*V9 2
X.X 6
CK SA C
2RHS*V13 2 X X 4
CK SA C
2RHS*V14 2 X X 4
CK SA C
2RHS*V17 0 X X 2
CK SA O
Stop ChecF i,
17 of 27 1-i
- -.. _ _. ~. _.., _ _. _ _. _ _ -
__..._-_.m
__m.
j i
i i
Nine Mile Point Unit 2 1
4 TABLE 6-1 (Cont)
{
l l
System: Resioaal Heat Removal 4
I Valve I' -
Valve
-ASME Ca tego ry Active Actu-Norma l Testing P&lD ASME XI or Size Valve ator Posi-Test Relier A l te r-Test Mark Code.
Coo rd A B
_Q Q Passive (In.), Type
- Type
- tions* Reau i remerit Reauost native Procedu re
}.
Number Class PklD
(
2RHS*V18 2 X X 2
CK SA O
f~
2RHS*V19 2 X X 3/4 CK SA C
2RHS*V20 2 XX 3/4 CK SA C
g 4
4 2RHS*V21 2 X
3 CA M
C j-2RHS*V22 2 X
3 GA M
C i
}'
i l
l 1
1 L
[
l 4
I
}
i i
l 1
l I
i 18 of 27 1;
l 1
i a
1I'
l 4
~,
W j.
i Nine Mile Point Unit 2 6
i TABLE 6-1 (Cont) j System: Reactor Water Cleanup i
t l
Vaive Valve ASME Ca tego ry Active Actu-Norma l Testing Mark
-Code P&lD ASME XI or Size Valve stor Post-Test Relief A l te r-Test j
Number Class P&lD Coord A B C D Passive f in. ) Type
- Type
- t. ions
- Reauirement Reauest native Procedu rg I
l 2WCS*-
1 X
8 CL MO O
.MOV102 2WCS*
1 ~
X 8
CL MO O
' ~
MOV112 i
4 1
2WCS*
1 X
8 CL MO O
c MOV200 I
3 i..
4 i
3 i
i 4
i e
l-i i.
l i
l V
i s
t f
t I
i i.
t l
I i
i r
1 i
i i
i i
y 1
19 of 27
?
j-
....m
.-.-_m_._
- -.. ~. ~...
Nine Mile Point Unit 2 1
TABLE 6-1 (Cont) i System: Spent. Fuel Pool Cooling and Cleanup Valve Valve ASME Ca tego ry Active Actu-Normal Testing Ma rk Code P&lD ASME XI or Size Valve ator Posi-Test-Relier Alter-Test Mumber Class P&lD Coo rd A B Q Q. Passive (In ) Type
- Type
- tions* Reauiremen,1 Reauest native P rocedu_re
+
2SFC*
3 X
8 BF A
0 AOV19A 2SFC*
.3 X
8 BF A
0 AOV19B 2SFC*
3 X
4' BF A
C AOV33A 2SFC*
3 X
4 BF A
C AOV338 2SFC*
3 X
8 BF A
0 AOV153 2SFC*
3 X
8 BF A
0 AOV1514 2SFC*
3 X
10 BF A
C HVSA 2SFC*
-3 X
10 BF A
C HV6B 2SFC*.
3 X
8-BF A
C HVI7A t
2SFC*
3 fX 8'
BF A
C HV178 2SFC*-
3 X
8' BF A
O h
HV18A 2SFC*
3 X
8 BF A
O HV188 2SFC*.
3 X
.8 BF A
O HV37A 20 of 27
[
_.m.
.. _.. _, _ ~. - - _. _ _ _.
---.__...~.-_.~- - -. =
1 I
l 1
i j-t J
i
}.
Nine Mile Point Unit 2 i
TABLE 6-1 (Cont)
I, i
System: Sp9nt Fuel Pool Cooling and Cleanup j.
Valve-Valve ASME Ca tego ry Active Actu-Normal Testing i
Mark Code P&l0 ASME XI or Size Valve ator Posi-Test-Relief A l te r-Test o,
. Number Class Pk1Q Coo rd A B Q Q Pass ive f In ) lype* Type
- t ions
- Reauirement Request native P rocedu re 2SFC#
3 X
6 BF A
0 j
HV37B
. 2SFC*
3 X
2 1/2 PC A
O j
HV149 i
2SFC*
3 X
10 BF A
0 j
HV54A i
2SFC*
3-X 10 BF A
0 j-HV54B 2SFC*V7 3
X X 1
CK SA f
'2SFC*V9.,3-X X 8
CK SA 2SFC#V11 3 X
X' 8
CK SA 2SFC*V20A 3 X X 8
CK SA 2SFC#V208 3 X X 8
CK SA 2SFC*V95A 3 X X 8
CK SA f
}
2SFC#V958 3 X X 8
CK SA 2SFC*
3 ~
X'X 8
CK SA j
V102A f
2SFC*
3 X X 8
CK SA V102B 2SFC*V106 3 X.X 4
CK
'SA I
2SFC* -
3 X X 1
CK SA.
V147A i
l l
L 2e of 27 t
n'
4 i
Nine Mile Point Unit 2 TABLE 6-1 (Cont)
System: Spent FueI Pool Cooling and Cleanup i
Valve Valve ASME Category Active Actu-Norma l Testing Mark Code P&lD ASME XI or Size Valve ator Posi-Test Relief A l te r-Test Number Class P&lD Coo rd A B C Q Pa ss ive ( In. ) Typ_e* Iyne* tions* Reouirement Reauest native P rocedu re 2SFC*
3 X X 1
CK SA V147B 2 SIC
- 3 X X 1
CK SA V148A 2SFC*
3 X X 1
CK SA V148B 2SFC*V151 3 X X 1
CK SA 2SFC*V229 3 X X 8
CK SA r
i i
4 22 of 27 4
1 4
b h
. -. - - ~ ~. --
. ~. -....
.)
t i
Nine Mile Point Unit 2 l
t, TABLE 6-1 (Cont) j System: High Pressure Core Spray i
i I
Valve Valve ASME Category Active Actu-Normal Testing 7
Mark Code P&lD ASME XI or Size Va l ve a to r Posi-Test Relief Al te r-Test i
Number Cla ss PALD Coo rd A B C Q Pass ive f in. ) Type
- Typ_e* tions* Requirement Request native Procedure 1
X X 12 CK SA/A C l
2CSH*-
?S"108 2CSH*
2 X
14 CA MO O
e MOV101 L
2CSH" 2
X 4
CA MO C
MOV105 2CSH*
'-1 X
12 CA-MO C
MOV107 i
)
2CSH*
2 '
X 10 CL MO C
r i
MOV110 2CSH*
- 2 X
12 CL
.MO.
C MOV111 2CSH*
2-X 10 CL MO C
MOV112 1
2CSH*
-2 X
18 CA' MO C
j MOV118-2CSH*.
2-X RL SA C
i.
RV113-i
.2CSH*
2.
X
'RL SA C
t 4
RV1114 l
6 f-2CSH*V7 2
X 4
CK SA C
I 1
2CSH*V9-. 2 X
16 CK SA C
2CSH*V16 2 X'
20 CK SA C
t 2CSH'V17 2 X
3 CK SA C
i i
23 of 27 t
i i
a m
=
v-n e
~ - -. - - - -
?
Nine Mile Point Unit 2 TABLE 6-1 (Cont)
System: High Pressure Core Spray Valve Valve ASME Ca tego ry Active Actu-Normal Testing Mark Code P&lD ASME XI or Size Valvo ator Posi-Test Relier A l te r-Test Number Class P&l0 Coo rd A B C Q Passive f in. ) Tyne* lype* tiong Reoulrement Eg_ quest native Procedure 2CSH*V55 2 X
3 CK SA C
2CSH*V59 2 X
e l' CK SA C
24 of 27
_.._._....______..-.___......._...,..__-___.m__
. - _ _ _ _. _ _ _ _ _ _ _. _ _ _ _ _ _ _ _. - _ _ _ _ -.. _.. _ _. ~. _ _ _.
...._._.m..
t 1
i.
i l
j Nine Mile Point Unit 2 i
j TABLE 6-1 (Cont) i i
r i
1 System: Standby L.iquid Control f
]'
Valve Valve ASME Ca tego ry Active Actu-Normal Testing i
Mark Code P&lD
'ASME XI or Size Valve ator Posi-Test Relief A l te r-Test j
Number Class P&lD Coo rd A B C D Pass ive N Type
- Type
- t ions
- Reau i rement Reauest native Rocedure j
i i
2SLS*
2 X
3 CL MO C-t j
MOVIA l
1 l
2SLS*
2 X'
3 GL MO C
1 MOV sin l
f
.2SLS*
2 X
-X 1.5 CK MO O
. MOVSA 1
X X 1.5 CK MO O
2SLS*
2 I.
MOV5B i
2
2SLS#RV2A 2 X
O.75x1 RL SA C
2SLS*RV2B 2 X
O.75x1 RL SA C
i 2SLS*V10 1 X X 1.5 CK SA C
j
. 2SLS*V12 2 X
1.5 CK SA C
l 2SLS*V14 2 X
1.5 CK SA C
1 2SLS*
-1 X
1.5 PG
'XP O
{
VEX 3A i
2SLS* '
1 X
1.5 PC XP O
}
+
-VEX 3B' l
1 i
i f
I I
h I
t i
jv, ii i-25 of 27 i
4 k
1 i
I
-_._.._s j'
t i
4 i
4 Nine Mile Point Unit 2 i
a TABLE 6-1 (Cont).
.{
i I
System: Low Pressure Core Spray
{
i 1;
f t
4 Valve'
]
. Vaive ASME Ca tego ry Active Actu-Normai Testing Mark Code P&lD ASME XI or Size Valve ator Posi-Test Relief A f te r-Test
[
l Number Class P&lD.
Coo rd A B C D Passivo ( In. ) Type
- Typ_e* tions* Reauirement Reauest native Procedure 2
e
.t I
l 2CSL*
1
.X X
12 CK A
C AOV101 l'
'2CSL*
1.
X 12 CA MO C
1.
- MOV104 I
2CSL*
2 X
4 CA MO
'C 1
MOV107
~
2CSL*
2 X
20 Bf MO O
MOV112 L
2CSL*
2 X
1.5x2 RL SA C
3
-l
-RV105' 1
[
2CSL*
2 X
0.75x1 RL SA C
)
RV123 i
I' i
2CSL*V4 2
X 16 CK SA C
4 t
1.
I 2CSL*V9 2
X 12 CK SA
.C i
?
i 2CSL*V14L 2
.X 2
CK SA C
)
2CSL*V21 2 X
2 CK SA C
I i
t b
i L
r i.
s F
l 26 of 27 3
f I
!~
f i
i r
k
_.-._._.._.__.__.m.
4 f
i l.
Nine Mile Point Unit 2
- 1..
I' TABLE 6-1 (Cont) i System: Feedwater
?
I Valve Valve ASME Category Active Actu-Normal Testing Mark Code
'P&lD ASME XI or Size Valve stor Posi-Test Reller A l te r-Test
. Humber Class P&lD Coo rd A B C D Passive ( In. ) Jyp_e* Type
- tions* Peauirement Reauest native Procedure 1
2FWS*
1-X 24 CK A
O AOV23A c
2fWS*
1 X
24 CK A
O i
AOV23n 2FWS*
1 X
24 CA MO O
MOV21A 1'
2FWS*
1 X
24 CA MO O
MOV218 i-2FWS*V12A 1 X
24 CK SA O
2FWS*V12B 1 X
24
'CK SA' O
i i
[
t l
[
t i
{
i i
i 3'
t j--
j' t
i
- See Tables 6-la, 6-Ib, and 6-Ic.
This' table will be completed by August 31,-1984.
27 of 27 1
4 t
I I
i 1
+
I I
r Nine Mile Point Unit 2 i
TABLE 6-la 1
SYMBOLS USED TO DESIGNATE VALVE TYPES Valve Types 4
i Symbol Meaning i
AN Angle Valve BF Butt.erfly BL Ball CK Check j
'I GL Globe PG Plug 4
RD Rupture Disk j
RG Regulating RL Relief SK Spring Check i
i s
4 i
8 1 of 1
, _ _.. _, _. _ _ _ _,,.. -.. _.,.. -.......... _... _ _ _ _ _. _ -....,.,. ~ -.,... _. _.. _, _ _.,.,,.., _... _... _.... _ _ _..., _. _...... - _....
Nine Mile Point Unit 2
- ()
TABLE 6-lb SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPES Valve Actuator Types Symbol Meaning A
Air Operator M
Manual Operator MO Motor Operator SA Self-Actuated S
Solenoid Operator H
Hydraulic Operator 1
i E
Electrical
{
XP Explosive Operator O
4 4
i 1 of 1
,_-,,,.m.,....
..,.,7
i Nine Mile Point Unit 2 l
i TABLE 6-1c i
i SYMBOLS USED TO DESIGNATE VALVE POSITIONS 1
1 1
Valve Positions Symbol Meaning I
O Open i
C Closed i
LO Locked Open i
i LC Locked Close i
TH Throttled j
1 Valve position determined by other system parameters as in the case of check i
valves.
l 3
i l
i 1
,I l
1 1 of 1 i
1 i
ii
Nine Mile Point Unit 2 T
TABLE 6-2
[V CATEGORY C SAFETY AND RELIEF VALVES TESTING SCHEDULE Time Period Number of Valves to be Tested Minimum of N /60 x total valves in this Startup through t
first refueling category First refueling Additional valves to make cumulative through second amount tested at least N /60 x total 2
refueling valves in this category Second refueling Additional valves to make cumulative through third amount tested at leady Na/60 x total refueling, etc.
valves in this category O
NOTE:
N, Na, etc, are the numbers of months from startup Ns, 2
to first refueling, second refueling, third refueling, etc.
When N is a number larger than 60, all valves that have not been tested during the preceding 5-yr period shall be tested.
The following period shall then be con-sidered to be the same as "startup through first refuel-ing" for purposes of determining test frequency, with the added requirement that at each refueling all valves that have not been tested during the preceding 5-yr period shall be tested.
The subsequent period will be considered the same as the first refueling.through the second refuel-4 ing, etc, with N determined by counting months from the new starting point.
1 of 1
Nine Mile Point Unit 2
)
SECTION 7 v
COMPONENT SUPPORTS
7.1 INTRODUCTION
7.1.1 Code Editions This section of the plan provides preservice and inservice examination and test requirements and the acceptance standards for ASME III Code Class 1, 2,
and 3 component supports based on the 1980 Edition through Winter 1980 Addenda of the ASME Boiler and Pressure Vessel
- Code,Section XI, and lists the specific supports requiring preservice and inservice examination and tests.
The preservice examinations and tests for component supports shall be in accordance with the rules and requirements contained within the 1980 Edition through Winter 1980 Addenda of the ASME Boiler and Pressure Vessel
- Code,Section XI, Subsections IWF and IWA.
The inservice examinations and tests for component supports
(-~g shall be in accordance with the same or later Code Edition
)
and Addenda applied to the components and approved by the
' ~ '
Nuclear Regulatory Commission, to the extent practical.
This section will be updated to reflect the applicable code edition and addenda for inservice examinations and tests at a
later
- date, if necessary, to comply with 10CFR50.55a(g)(4).
7.1.2 Supports Requiring Examinations and Tests Tables PS-1 through PS-6 list all ASME III Class 1, 2,
3 supports that require visual examination for preservice inspection.
Supports that are exempt from examination are also listed in Tables PS-1 through PS-6.
Tables IS-1 through IS-6 list supports for ASME III Class 1, 2 and 3 components or piping that are required to be examined under IWB, IWC, and IWD during the first inspection interval.
These supports must be inspected on each successive inservice inspection interval.
The snubbers that require functional testing are listed in Table S-1.
These are all of the nonexempt snubbers that
.n 7-1 N.]g
Nine Mile Point Unit 2 have ASME III, Code Class 1, 2,
or 3 components or piping.
(Currently there are no hydraulic snubbers in Unit 2.)
7.2 SCOPE AND RESPONSIBILITY (IWF-1000) 7.2.1 Scope The examination and testing requirements of Subsection IWF and this plan shall be limited to the Class 1, 2,
and 3
component supports required to be constructed in accordance with Subsection NF of the Code and fer which all of the requirements of the Construction Code have been met.
Supports that have been constructed in accordance with Subsection NF and do not support ASME Class 1, 2,
or 3 components are not within the scope of Section XI and this plan.
The examination requirements in Subsection IWF shall be applied to plate and shell type (F-A),
linear type (F-B),
and component standard type (F-C) supports that are within the support examination boundaries defined by IWF-1300.
As shown on the component support drawings, supports may be composed of a combination of linear, plate and
- shell, and component standard types of support elements.
Functional testing of component supports shall be limited to Class 1, 2,
and 3 snubbers.
7.2.2 Supports Exempt From Examination and Test The Code rules for Subarticle IWF-1230, Supports Exempt from Examination and Test, are being prepared.
Exemptions for supports shall be requested as outlined in Section 1 of this Plan.
7.2.3 Integral Attachment Pad Type Boundaries Paragraph IWF-1300(a) of the referenced Code defines the boundary of an integral attachment and, therefore, defines the support examination boundary as the distance from the pressure-retaining component as indicated in Subsections IWB, IWC, and IWD.
- However, Subsections
- IWB, IWC, and IWD and Figures IWB-2500-13, IWB-2500-15, IWC-2500-5, and IWD-2500-1 do not explicitly define examination boundaries for integral pad-type attachments as shown in Figure 7-1.
The integral attachment pad (B) and the welded connection (C) meet the design requirements in the applicable Code 7-2
Nino Mile Point Unit 2 O-subsection for the class of component to which they are attached; therefore, the distance from the pressure boundary (A) to the surface of the integral attachment pad (B), as l
illustrated by t in Figure 7-1, will define the minimum IWB, j
- IWC, and IWD examination boundary for this plan.
The Code subsection which is applicable to the welded connection which connects the integral support to the integral attachment is specified in the design specification (NF-ll32.2).
The welded connection will be included in the-applicable Code subsection examination boundary.
7.2.4 Piping Components The referenced code (IWF-2510) does not define the extent of a piping component for the purpose of selecting pipe supports which require inservice inspection.
The extent of a piping component could be defined as a single spool piece or as all of the piping of the same Code Class within a system.
The definition will-greatly affect the number of supports requiring inservice inspection.
A single spool piece may not have any supports, while a large system could have hundreds.
The extent of a piping component will be defined for the purposes of this plan as all of the run pipe contained within the pipe stress calculation boundaries.
Two or more calculations are usually required for piping of the same Code Class within a
system.
The calculations O
generally contain c.n average of 15 pipe supports.
The pipe stress calculation boundaries are defined in the calculation and are located at the first pipe support anchor in either direction along the pipe run and/or at equipment nozzle connections.
Pipe supports which are located on the same pipe run between-anchors and/or equipment affect each other;
- however, supports and piping which are separated by anchors and equipment do not affect each other significantly.
By selection of the calculation boundaries as outlined above, the proper -interaction of the supports-- and piping 'is accounted for in the analysis.
The piping contained within a
pipe stress calculation, therefore, seems like a
reasonable definition for the extent of a piping component.
The supports which are located within the boundaries of a particular pipe stress calculation, including the anchors at the calculation boundaries, will be identified as requiring inservice inspection provided the piping contained within the calculation requires inservice examination by Section XI.
i
.-e
Nine Mile Point Unit 2 7.3 EXAMINATION AND INSPECTION (IWF-2000) 7.3.1 Application of Examination Methods The VT-3 and VT-4 visual examination requirements of IWF-2000 and this plan shall apply to all nonexempt component supports and support elements, including snubbers.
The examinations of the welded and mechanical connections and the examinations of component standard supports defined in Table IWF-2500-1 shall be in accordance with the VT-3 and VT-4 visual examination methods specified in Table IWF-2500-2.
Additionally, the plate and shell type and linear type support structural members (i.e.,
baseplates, beams) shall be examined by the VT-3 methods defined in IWA-2213.
Category F-C supports shall be examined by both VT-3 and VT-4 visual examination.
7.3.2 Preservice Examination The visual examinations specified in Table IWF-2500-2 shall be performed completely, once, as a preservice examination for all nonexempt supports identified in Tables PS-1 through PS-6.
The preservice visual examinations shall be performed following the initiation of system tests and shall be completed prior to commercial operation.
7.3.3 Inservice Examination The inservice examinations shall be completed in accordance with the requirements of IWF-2400, IWF-2500, and this plan for all supports identified in Tables IS-1 through IS-6.
For multiple components that are similar in
- design, function, and service and that are within the same
- system, the supports of only one component of each type require inservice examination by IWF-2510(b).
This is applied to similar pumps, pressure vessels, and heat exchangers within a system, provided that the support designs are the same and operating temperatures and pressures are similar, that they are located in the same building and floor (g values will be the same),
and that the piping attached to them is similar in size, all of which results in similar support loadings.
Some piping arrangements within a system are similar or are mirror images of each other; however, support arrangements 7-4
Nine Mile Point Unit 2 (m
i and loading may vary.
The inservice exemptions of IWF-s/
2510(b) generally will not apply to piping component supports.
7.4 STANDARDS FOR EXAMINATION EVALUATIONS (IWF-3000)
Evaluation of preservice and inservice examination results shall be performed in accordance with the requirements of Article IWF-3000 and this plan.
The acceptance standards for support items, bolting and alignment in Subarticle IWF-3400 are being prepared.
The Unit 2 ISI Plan will be revised to include the standards after they are incorporated into the Code and are approved by the Nuclear Regulatory Commission.
Acceptance standards for support items, including bolting and alignment, shall be in accordance with the requirements of the design specifications and construction code in the absence of the Section XI requirements.
7.5 REPAIR PROCEDURES (IWF-4000)
The requirements for repair procedures in Article IWF-4000 are being prepared.
The Unit 2 ISI Plan will be revised to include the procedures after they are incorporated into the 7-w)
Code and are approved by the Nuclear Regulatory Commission.
(
Repairs to supports and replacement of supports shall be in accordance with the requirements of the design specifications and the construction code in the absence of the Section XI requirements.
7.6 INSERVICE TEST REQUIREMENTS (IWF-5000) 7.6.1 Preservice Tests The preservice operability tests required by IWF-5200 and Section 7.8 of this plan shall be performed for all Code Class 1, 2,
or 3 snubbers identified in Table S-1 regardless of size and prior to installation.
7.6.2 Inservice Tests The Inservice Tests For Snubbers 50 kips Or
- Greater, Subarticle IWF-5300, are under development.
The Unit 2 ISI Plan will be revised to include the test requirements after they are incorporated into the Code and are approved by the Nuclear Regulatory Commission.
l [
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Nina Milo Point Unit 2 The inservice tests required by IWF-5400 shall be performed for all nonexempt snubbers regardless of size, in accordance with approved test procedures.
Qualitative testing, as outlined in Section 7.8, may be used in lieu of quantitative test measurements to demc nstrate operability for those snubbers for which testing is impractical.
7.6.3 Test Procedures All snubber functional test procedures shall meet the test requirements contained in Article IWF-5000 and Section 7.8 of this plan and the corresponding test requirements contained in the design specification.
All test procedures shall be reviewed and approved by the Owner or its agent.
7.7 CORRECTIVE ACTION Immediate corrective action shall be taken for all supports that do not meet the Code requirements or functional test requirements.
Systems or components will not be put into service until corrective action has been completed.
Systems or components will be evaluated and removed from service, if necessary, if a
support is found inoperable, has lost structural integrity, or cannot be repaired or replaced within 72 hrs.
If a safety-related system or component is
- damaged, overstressed, or is likely to be damaged, the system or components will be taken out of service immediately.
Systems or components will not be put into service until corrective action has been completed.
7.8 EXAMINATION AND TESTING OF SNUBBERS 7.8.1 Introduction This section contains the general requirements for examination and testing of ASME III, Code Class 1, 2, and 3
snubbers; the frequency for performing the examinations and tests; the criteria for segregating snubbers into examination and test groups, and acceptance standards.
The purpose of this p.1.an is to demonstrate operational readiness of the snubbers by requiring the performance of the examinations,
- tests, and, when necessary, corrective action on selected snubber groups at required frequencies or periods.
Certain snubbers, as defined above, may be waived in part or totally on a case-by-case basis from the requirements of 7-6 O
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Nine Mile Point Unit 2
]O-this section provided that an exemption from the examination or test has been granted in accordance with Section 1.
7.8.2 Terminology The following list of definitions is provided to assure a uniform understanding of selected terms used in this j
section.
1.
Activation - the change in parameter that verifies restraining action.
2.
Breakaway Force - the minimum applied force required to initiate extension or retraction of the snubber.
3.
Drag Force - the force required to maintain the extension or retraction of the snubber at a
constant velocity prior to activation.
4.
Snubber - a device which provides restraint to a component or system during a sudden application of forces but allows essentially free motion during thermal movement.
5.
Inaccessible Snubbers - those snubbers that are in O-a high radiation area or other conditions that would render it impractical for the snubbers to be examined under normal plant operating conditions without exposing plant personnel to undue hazards.
6.
Maintenance - action taken to prevent or correct deficiencies in the function of a snubber.
7.
Mechanical Snubbers - devices in which load is transmitted entirely through mechanical components.
8.
Normal Operating Conditions - operating conditions during reactor startup, operating at
- power, hot standby, reactor cooldown to cold shutdown.
9.
Operability Testing - an element of inspection consisting of measurement of parameters that verify snubber performance.
10.
Operating Temperature - the temperature of the environment surrounding a snubber at its installed plant location during the phase of plant operation for which the snubber function is required.
7-7
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Nina Mile Point Unit 2 11.
Release Rate - the velocity or acceleration of extension or retraction of the snubber under a
specified load after activation of the snubber took place.
12.
Activation Velocity - the maximum velocity of extension or retraction of the snubber prior to the onset of restraining action.
13.
Threshold Acceleration - the maximum acceleration of extension or retraction of the snubber prior to the onset of restraining action.
14.
Swing Clearance - the movement envelope within which the snubber must operate without restriction, from the cold installed position to the hot operating position.
15.
Test Temperature - the temperature of the snubber at the time of the test.
7.8.3 Procedures and Equipment 7.8.3.1 Examination and Test Procedures Examinations and tests shall be performed in accordance with h
written procedures.
As a minimum, these procedures shall include:
1.
General Description (Method and Objectives) 2.
Scope of Application 3.
References 4.
Prerequisites, Precautions, and Limitations 5.
Test Equipment Required 6.
Sequential Actions to be Followed 7.
Acceptance Criteria 8.
Data Sheets.
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Nino Mile Point Unit 2 i
7.8.3.2 Examination and Test Results As a minimum, the results of examination and test data shall be documented and shall include:
1.
Manufacturer's model number, serial number, type, and unique location identification of the snubber 2.
Pertinent examination and test data 3.
Identification and disposition of nonconformances 4.
Information to identify the test / examination performed, procedure used, and the test / examination date 5.
Test equipment used and calibration dates 6.
Acceptability of test / examination results 7.
Inspector's identification.
7.8.3.3 Instrumentation and Test Equipment Instrumentation and test equipment used to verify the performance of the snubber shall be capable of measuring the test parameters over their amplitude and frequency ranges with accuracy sufficient enough to obtain meaningful test results.
All instruments and test equipment used in performing the tests shall be calibrated and controlled in accordance with written procedures to assure accuracy of measured data.
7.8.3.4 Maintenance Procedures Maintenance activities that may affect the ability of the snubber to perform its intended function shall be completed in accordance with written procedures.
Snubbers, which undergo maintenance activities which may alter the snubber's intended
- function, shall be examined and tested in accordance with the applicable requirements of Section 7.8.5.1 after maintenance is completed.
The written maintenance procedures shall specify the appropriate examinations and tests.
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Nina Milo Point Unit 2 7.8.3.5 Snubber Modification and Replace nt Procedures Modified and/or replacement snubbers shall be examined and tested in accordance with written procedures and in accordance with the requirements of Section 7.8.5.
The written procedures shall specify the appropriate examinations and tests.
7.8.4 Personnel Qualifications Personnel who are required to
- witness, perform, and/or evaluate the examinations and tests shall be qualified in accordance with the owner's administrative procedures.
7.8.5 Preservice Examination and Operability Testing Requirements 7.8.5.1 Preservice Operability Testing Requirements Preservice operability tests shall be performed on all snubbers, once, prior to installation.
Testing may be performed at the manufacturer's facility, at the plant site, or at an independent qualified testing laboratory.
The testing shall verify that:
1.
The force that will initiate motion (breakaway force) or the force that will maintain low velocity displacement (drag force), whichever is applicable is within specified limits, both in tension and compression.
2.
Activation is within the specified range of velocity or acceleration in both tension and compression.
3.
Release
- rate, where applicable, is within the specified range in tension and compression.
For units specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be demonstrated.
l Snubbers that fail any of the preservice operability tests shall be evaluated for the cause(s) of failure (s).
If a
i design or manufacturing deficiency in the snubber is found, it shall be corrected.
Modified, repaired, and replacement l
naubbers shall be tested in accordance with the above requirements.
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Nino Mile Point Unit 2 7.8.5.2 Preservice Examination Requirements A
preservice examination shall be made on all snubbers.
This examination shall be conducted after installation and shall be completed prior to commercial operation.
The initial examination shall as a minimum verify:
1.
There are no visible signs of damage or impaired operability as a result of
- storage, handling, or installation.
2.
The snubber load
- rating, location, orientation, position setting, and configuration (attachments, extensions, etc) are in accordance with design drawings and specifications.
Installation records (based on physical inspections) verifying that the snubbers were installed according to design drawings and specifications shall be acceptable in meeting this requirement.
3.
Adequate swing clearance is provided to allow snubber movement.
4.
Structural connections such as
- pins, bearings, studs, fasteners, and other connecting hardware such as lock nuts, tabs, wire, and cotter pins are
[V) installed correctly.
If the period between the preservice examination and initial system preoperational test exceeds 6 months, the examinations shall be repeated.
Snubbers which are installed incorrectly or otherwise fail to meet any of the preservice examination requirements shall be installed correctly,
- repaired, or replaced.
The corrected,
- repaired, and replacement snubbers shall be examined in accordance with the requirements of this paragraph.
Additionally, replacement snubbers shall be operability tested in accordance with the requirements of 7.8.5.1.
7.8.5.3 Preservice Thermal Movement Examination Requirements Duri ng initial system heatup and
- cooldown, the thermal movement of snubbers in systems whose design operating temperature exceeds 250 F shall be verified as follows:
1.
During initial system heatup and cooldown at temperature plateaus record the thermal movement.
- Verify, at each plateau, that the snubber movement 7-11 7 S,
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Nine Mile Point Unit 2 is within acceptable design limits.
All discrepancies or inconsistencies shall be evaluated and corrected, if necessary, prior to proceeding to the next specified plateau.
The total thermal movement from cold to hot at full operating temperature shall be recorded.
This value may be either measured directly if maximum operating temperature was attained, or extrapolated from lower temperature readings.
The cold or hot position setting shall be evaluated and adjusted if necessary to ensure adequate snubber clearance from fully extended or retracted positions.
2.
Verify that there is swing clearance at specified heatup and cooldown plateaus.
7.8.5.4 Preservice Examination and Testing Records Preservice examination and testing results shall be recorded in accordance with the requirements of Section 7.8.7.
7.8.6 Inservice Examination and Testing Requirements 7.8.6.1 Inservice Examination and Testing Programs Two separate and distinct inservice programs are required, the inservice visual examination program and the inservice operability testing program.
Each program has separate schedules.
The requirements and schedules for both programs are specified in the following sections.
7.8.6.2 Snubber Groups for Inservice Examination and Operability Testing Programs Snubbers shall be categorized into groups for the purpose of visual examination and operability testing.
The groups for visual examination need not be identical to the groups for operability testing.
A snubber may be included in more than one group.
Groups shall only be established based on the following:
1.
Snubbers shall be grouped according to accessibility.
Accessible and inaccessible snubber groups may be formed and considered separately from each other for the purpose of visual examination, operability testing,.and failure analysis.
l 2.
Snubbers may be grouped according to physical characteristics and environmental conditions.
The 1
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.N snubber groups may be considered separately from O
each other for the purpose of visual examination x
and operability testing.
Physical characteristics which may form the basis for grouping include manufacturer,
- design, type,
- size, capacity, supported components, and materials.
Environmental characteristics which may form the basis for grouping i..clude temperature,
- humidity, loadings, and susceptibility to damage.
3.
Snubbers shall be categorized according to cause of failure.
Cause of failure may not be identifiable until the examination and test program commences.
Snubber failure mode groups, described below, shall be formed as failure information becomes available.
Snubber failure mode groups may be considered separately from each other for the purpose of examination and testing.
The following failure mode groups shall be used:
a.
Generic Failures - failures resulting from a defect in manufacturing or design that gives cause to suspect other similar units.
This includes failures of any unit that fails to withstand the environment or application for which they were designed.
g 1
b.
Application Induced Failures - failures resul-ting from incorrect application of the unit or environmental conditions for which it has i
not been designed or qualified.
I c.
Isolated Failures - failures resulting from i
damage caused during installation or shutdown (i.e.,
standing on the units, dropping equip-ment or tools on the unit, etc).
The nature of the failure does not lend other units to be suspect.
d.
Unexplained Failures - failures that cannot be categorized as generic, application
- induced, or isolated.
This includes all failures for which the cause of failure cannot be determined.
7.8.6.3 Inservice Examination Requirements 1.
Inservice examination shall be a visual examination for impaired functional ability such 'as
- leakage, corrosion, or degradation from environmental ex-7-13 pQ
Nine Mile Point Unit 2 posure or operating conditions.
An examination procedure and checklist shall be prepared for this purpose.
2.
Snubbers shall not be subjected to prior main-tenance specifically for the purpose of meeting examination requirements.
7.8.6.4 Inservice Examination Acceptance Criteria To be acceptable, a snubber shall be capable of performing its design function as installed.
There may be conditions present which are undesirable but do not render the in-stalled snubber inoperable.
These and any unacceptable snubber are subject to corrective action.
To be acceptable, the snubber installation must meet all of the following requirements.
If it fails to meet any one of these requirements, it shall be identified as unacceptable unless an engineering evaluation or test establishes that the snubber installation was capable of performing its required function as found.
1.
Snubbers shall be installed so that they will carry the specified load.
Loose fasteners, deformed
- members, or detection of disconnected components are some of the conditions which can adversely af-fect the load carrying capability of the installation.
Detection of these conditions requires the identification of the installation as unacceptable, unless an engineering evaluation determines the snubber installation as found is capable of carrying the design load.
2.
Snubbers shall be installed in such condition that l
they do not restrict the thermal movement of the l
pipe or other equipment that the installation is designed to protect or restrain.
Misalignment, deformation,
- binding, and jamming are some of the conditions which can result in restricted thermal movement.
If no indication of binding or misalign-ment is observed and the snubber is free to pivot at the pinned connections, the provisions of this requirement are considered to have been satisfied.
3.
The visible design features required for the ac-tuation of the snubber shall be functional.
Features which can be visually verified are to be observed.
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(~~)l 7.8.6.5 Inservice Examination Failure Evaluation G
Snubbers which do not meet the examination acceptance criteria shall be evaluated to determine the cause of the failure and shall be considered unacceptable.
The unaccept-able snubbers shall be categorized according to the failure modes in 7.8.6.2(3).
The categorization of snubbers into failure mode groups shall be used as a basis for determining subsequent corrective action and examination frequencies in accordance with 7.8.6.6 and 7.8.6.7.
The following failure evaluation criteria shall be used to categorize snubbers into each failure mode group.
1.
Generic Failures a.
All snubbers that are determined to be in the same generic failure mode group as the unac-ceptable unit shall be considered unacceptable for the purpose of determining corrective action.
Replacement and modified snubbers shall be recategorized as acceptable for the purpose of determining the time to subsequent examination provided the provisions of 7.8.6.4 are met.
Additionally, an inservice examination shall be completed for the feS) replacement and modified snubbers after at g'/
least 2 months of reactor power operation and prior to 12 calendar months.
2.
Application Induced Failures All snubbers that are determined to be in the same application failure mode group as the unacceptable snubbers shall be considered unacceptable for the purpose of determining the time to subsequent examination.
Snubbers in this group, other than the original unacceptable
- snubbers, shall be recategorized as acceptable provided they are visually examined and meet the provisions of 7.8.6.4.
Additionally, an inservice examination shall be completed for all recategorized snubbers after at least 2 months of reactor power operation and prior to 12 calendar months.
3.
Isolated Failures All unacceptable units in this group which have been repaired or replaced shall be recategorized as acceptable for the purpose of establishing the time f"
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Nina Milo Point Unit 2 to subsequent examination provided the provisions of 7.8.6.4 are met.
4.
Unexplained Failures All snubb-that are determined to be in the same failure mod cup as the unacceptable snubbers shall be con __ered unacceptable for the purpose of determining the time to subsequent examination.
7.8.6.6 Inservice Examination Frequency, Sample Size, and Composition 1.
The initial inservice examination of snubbers shall include all (100 percent) of the installed snubbers in the facility.
The examination shall be initiated after at least 2 months of reactor power operation and shall be completed prior to 12 calendar months after initial power operation.
The results of the initial inservice examination shall be evaluated in accordance with the provisions of 7.8.6.5.
2.
When evaluations in accordance with 7.8.6.5 reveal the number of inoperable snubbers within a
- group, subsequent examinations shall be required for all snubbers within each group in accordance with the following schedule.
No. Unacceptable Snubbers Months to Subsequent In Group Being Examined Examination For That Group O
18 1
12 2
6 3,4 4
5,6,7 2
8 or more 1
NOTE:
The time interval to subsequent examinations may vary by plus or minus 25 percent to coin-cide with planned outages.
3.
Subsequent examination shall continue by groups in accordance with the previously described schedules.
The time to subsequent examination for any given l
group shall not be lengthened more than one step at a
time when the number of inoperable snubbers within a group decreases.
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Nine Mile Point Unit 2 4.
If, after two. successive examination intervals,.at O.
the maximum time interval allowed for a group, the maximum time interval is again allowed for a group, the maximum time interval for the next required examination of. that group may be increased if justified by.the owner and accepted by the regulatory authority having jurisdiction over the facility.
The inservice sample composition shall be as follows:
1.
Snubbers selected for examination in reduced sample lots shall be on a
representative basis of the snubber installation within the group.
2.
All snubbers shall be examined in turn.
3.
Snubber installations subject to increased wear, deterioration, or damage may be examined more frequently and those installations in hazardous locations may be examined less frequently than the average.
7.8.6.7 Inservice Examination Corrective Action The following corrective action shall be taken for snubbers:
O 1.
Generic Failures Snubbers which are categorized as generic failures and have generic defects shall be
- modified, repaired, or replaced.
The modified, repaired, or replacement snubbers shall have a history of proven performance for the intended application and en-vironment or shall be tested to the requirements of the design specification and meet'the requirements of Section 7.8.5.
2.
Application Induced Failures Snubbers which are categorized as application in-duced. failures shall be modified'or. replaced if ths-application or environment is not modified to meet-the application requirements of the snubbers.
The modified er replacement snubbers shall have a
history of proven performance for the intended ap-plication and environment or shall be tested tx> the requirements of the design specification and meet the requirements of Section 7.8.5.
Snubbers which are categorized-as application induced failures may
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l Nino Milo Point Unit 2 be
- repaired, if damaged, provided the application or environment is modified to meet the application requirements of the snubbers.
3.
Isolated Failures Snubbers which are categorized as isolated failures shall be modified, repaired, or replaced.
4.
Unexplained Failures Snubbers which are categorized as unexplained failures shall be modified, repaired, or replaced with equivalent or different snubbers.
An en-gineering evaluation shall be performed to deter-mine the cause of repetitive failures and eliminate the repetitive failures over a period of time, and to specify the type and size of the different replacement snubbers.
Components / systems whose snubbers fail the examinations or tests should be examined to ensure that the suppported component / system has not been impaired.
In lieu of repair or replacement of any unacceptable or suspect
- units, the units may be deleted based on the analysis of the affected piping system.
However, a failure analyeis shall be com-pleted to establish subsequent examination and testing frequencies for the remaining snubbers within that group.
Snubbers with deficiencies which do not require iden-tification of the snubbers as unacceptable should be restored to such condition as to ensure that the snubbers remain acceptable at least during the next service period.
7.8.6.8 Inservice Operability Testing Requirements 1.
Operability testing of anubbers shall be performed to verify the following:
a.
The force that will initiate motion (breakaway force) or the force that will maintain low velocity displacement (drag force), whichever is applicable, is within specified
- limits, both in tension and compression.
b.
Activation is within the specified range of velocity or acceleration in both tension and compression.
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Nina Mile Point Unit 2 l
c.
Release rate, where applicable, is within the O
specified range in tension and compression.
For units specifically required not to l
displace under continuous load, the ability of the snubber to withstand load without displacement shall be demonstrated.
2.
Snubbers need not be tested at full rated load for verifying operability provided that the measured parameters during the reduced load test can be cor-related to operability parameters at rated load.
3.
Qualitative testing may be used in lieu of quan-titative measurements in meeting the requirements of Section 7.8.6.9 provided adequate justification can be presented and accepted for this position to the regulatory authority having jurisdiction over the facility.
In those cases, the owner shall ob-tain sufficient data to justify, based upon service history or life cycle testing, the ability of the parameter in question to be within specification over the life of the snubber.
For example, demon-stration that activation takes place at the proper levels without measurement of the activation velocity or threshold acceleration.
A test report shall be available for each snubber exempted from O
an inservice quantitative test requirement.
The test report must verify the parameter was within specifications to allow exemption of the anubber from quantitative testing of the parameter.
7.8.6.9 Inservice Operability Testing Acceptance Criteria 1.
To be acceptable, a snubber shall meet all of the following performance test criteria:
a.
Activation is within the specified values.
b.
Release rate, where applicable, is within the specified values.
If the device is required to resist all displacement after activation, the resistance to displacement must be exhibited.
c.
Breakaway and/or drag force.does not exceed specified quantities in both directions.
2.
For snubbers justified in accordance with Section 7.8.6.8.3,
-the qualitative. test result I
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Nino Milo Point Unit 2 shall demonstrate the acceptability of the snubber.
7.8.6.10 Inservice operability Testing Failure Evaluation Snubbers which do not meet the operability testing accept-ance criteria shall be evaluated to determine the cause of the failure and shall be considered unacceptable.
The unacceptable snubbers shall be categorized according to the failure modes in Section 7.8.6.2 (3).
The categorization c f snubbers into failure mode groups shall be used as a basis for determining subsequent corrective action and testing requirements in accordance with the provisions of Sections 7.8.6.11 and 7.8.6.13.
The following failure evaluation criteria shall be used to determine the number of unacceptable snubbers in each failure mode group.
1.
Generic Failures All snubbers determined to be in the same generic failure mode group as the unacceptable snubbers shall be considered unacceptable.
Replacement, modified, and repaired snubbers shall be reclas-sified as acceptable for the purpose of establish-ing testing requirements in accordance with. the provisions of Section 7.8.6.11, provided they meet the provisions of Section 7.8.6.9.
2.
Application Induced Failures All unacceptable snubbers in this group and suspect snubbers determined to be in the same application induced failure mode group as the unacceptable snubbers shall be considered unacceptable for the purpose of establishing testing requirements in ac-cordance with the provisions of Section 7.8.6.11.
3.
Isolated Failures All unacceptable snubbers in this group shall be recategorized as acceptable for the purpose of es-tablishing testing requirements in accordance with the provisions of Section 7.8.6.11.
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Nina Mile Point Unit 2 4.
Unexplained Failures The number of unacceptable snubbers shall establish the testing requirements in accordance with the provisions of Section 7.8.6.11.
Subsequent lots for testing shall be composed of snubber (s) similar in design, application, and configuration to the unacceptable snubber (s).
7.8.6.11 Inservice Operability Testing Frequency, Sample Size and Composition Testing shall take place at least once every inspection period using an initial representative sample consisting of at least 10 percent of the snubbers in the facility.
As far as practical, the initial representative sample selected for testing shall include the various dnsigns, configurations, operating environments, range of
- sizes, and capacity of snubbers.
Snubbers of parallel and multiple installation locations shall be identified and counted individually.
For the first lot tested, a sample which is representative of the snubber designs and installations in the plant shall be selected.
Snubbers shall be divided into groups and sub-T*
groups in accordance with Section 7.8.6.2.
The first sample (m-tested shall be, as far as practicable, a composite based on the ratio of the total number of snubbers in each particular group or subgroup to the total number of snubbers installed in the plant.
For each unacceptable
- snubber, an additional 20 snubbers from the same group as the unacceptable snubbers shall be tested.
As far as is practical, the subsequent samples shall include:
1.
Snubbers of the same manufacturer's design.
2.
Snubbers immediately adjacent to those found unacceptable.
3.
Snubbers from the same piping system.
4.
From. other piping
- systems, snubbers that have as temperature, similar operating conditions such humidity, vibration, and radiation.
Testing shall continue until the number of snubbers tested in each group (in the facility) is equal to or greater than
Nina Mile Point Unit 2 10 percent of all snubbers in each group (in the facility) plus 20 times the number of unacceptable snubbers found in each group (in the facility), or until all snubbers in each group (in the facility) have been tested.
At the end of group testing, the values of N and A shall be plotted on Figure 7-2.
A is the cumulative total number of snubbers found not to meet all appropriate test acceptance criteria.
The cumulative number of snubbers tested is denoted by N.
If at any time the point so plotted falls in the Reject Region, additional snubbers selected
- rom the various groups shall be tested.
The number of additional snubbers selected must be at least equal to the difference (N ) below the between the number tested (Ng) and the number 2
point on the accept-reject line at elevation A (see Figure 7-2).
The additional snubbers shall be a composite based on the ratio of the number of snubbers in each par-subgroup to the total number of snubbers ticular group or installed in the plant.
If at any time the point so plotted falls on the line or in the Accept Region, testing may be discontinued until the next scheduled test interval.
When the point plotted falls in the Reject Region, additional enubbers shall be tested until the point falls on the line or in the Accept Region, or until all of the snubbers have been tested.
If all f the snubbers in a
generic failure mode group have been replaced or corrected and retested, previous unacceptable test results or previous unacceptable snubbers for that group need not be included in the total A.
All other initially unacceptable enubbers for all other failure mode groups must be included in A.
For subsequent Inservice Operability Testing intervals, each representative sample shall be selected from previously un-tested snubbers.
Additionally, snubbers that failed during the previous test interval shall be retested.
After all snubbers have been tested, the tests shall be repeated, taking the same snubbers (or their replacements) in the same sequence as the original test to extent practicable.
For lots tested during subsequent testing intervals, the sample shall be based on the experience of past inservice operability testing.
A larger proportion of snubbers shall be selected from groups in which unacceptable snubbers have been found.
As far as practical, different snubbers shall be selected during each test interval so that eventually all snubbers will be tested.
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Nina Mile Point Unit 2 Snubbers shall not receive prior maintenance specifically O
for the purpose of meeting an operability test requirement.
7.8.6.12 Inservice Operability Testing Methods 1.
Testing is to be performed on the snubbers in their "as found" condition to the fullest extent practical.
2.
Test methods employed must not alter the condition of the snubber to the extent the test results misrepresent the original snubber condition.
3.
Inservice operability testing may be accomplished with the snubber installed in its permanent location by utilizing owner-approved test methods and equipment.
4.
Snubbers may be removed and bench-tested in accord-ance with owner-approved test procedures.
After reinstallation, the snubber shall meet the requirements of Section 7.8.6.4.
5.
If it is extremely difficult to utilize the test methods in paragraphs (3) and (4) above due to' the physical size of the snubber or inaccessibility of
('N
- location, the snubber subcomponents shall be
(_,)
examined and tested in accordance with approved procedures.
Reassembly of individual components must be in accordance with approved procedures.
6.
Testing methods may be used which measure specified parameters indirectly or which measure parameters other than those specified if test results can be correlated to the specified parameters through es-tablished methods.
7.8.6.13 Inservice Operability Testing Corrective Action When a snubber is determined to be unacceptab?.e as a result of inservice operability testing, corrective action shall be taken as follows:
1.
Components / systems whose snubbers fail the test shall be examined to ensure that the supported component (s) has not been impaired.
2.
A failure analysis shall be performed in accordance with Section 7.8.6.10 to determine the number of i
unacceptable snubbers.
7-23
. ha l
I
Nins Milo Point Unit 2 3.
The test sample is to be increased and additional testing performed in accordance with the provisions of Section 7.8.6.11.
4.
Unacceptable snubbers shall be adjusted, modified,
- repaired, or replaced in accordance with the requirements of Section 7.8.6.7 and the approved maintenance procedures.
7.8.6.14 Inservice Examination and Testing Records Inservice examination and testing records shall be main-tained in accordance with Section 7.8.7.
7.8.7 Records and Recordkeeping 7.8.7.1 Requirements Record copies of acceptance tests, design specifications, operacing and maintenance instructions, written inspection procedures, test equipment, calibration records, examination
- results, test
- results, maintenance
- records, replacement records, and schedules of inspection shall be maintained and l
controlled in accordance with the owner's administrative procedures.
7.8.7.2 Preservice Records Records necessary to verify the results of the preservice program shall be maintained and shall include, as a minimum:
1.
Preservice test results 2.
Examination records 3.
Thermal movement inspection records 4.
Nonconformance and corrective action required to be completed during the preservice inspection.
I 7.8.7.3 Inservice Records Records necessary to verify the results of the inservice program shall be maintained and shall include, as a minimum:
1.
Checklists verifying inservice examination, fluid levels, and as-found position setting.
2.
Inservice operability test results.
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Nina Mile Point Unit 2 3.
Nonconformance results, nonconformance evaluations,
(-')s and corrective action.
4.
Frequency of examination.
5.
Record of determination of months to subsequent examination.
7.9
SUMMARY
7.9.1 Preservice Examination (Including Snubbers)
All of the nonexempt supports, including snubbers, listed in Tables PS-1 through PS-6 shall be visually examined (VT-3 and/or VT-4 as applicable) once as a preservice examination.
7.9.2 Preservice Testing of Snubbers All of the
- snubbers, regardless of size, shall be func-tionally tested in accordance with the requirements of Sections 7.6.2 and 7.8 as a preservice test.
7.9.3 Inservice Examination (Excluding Snubbers)
All of the nonexempt supports and support elements, ex-cluding snubbers, listed in Tables IS-1 through IS-6 shall O
be visually examined (VT-3 and/or VT-4 as applicable) during each inspection interval according to the component examination schedule.
7.9.4 Inservice Examination of Snubbers All of the nonexempt snubbers listed in Table S-1 shall be visually examined (VT-3 and VT-4) in accordance with the requirements contained in Sections 7.6.3 and 7.8 of this plan.
7.9.5 Inservice Testing of Snubbers All of the nonexempt snubbers, regardless of size, listed in Table S-1 shall be functionally tested in accordance with the requirements contained in Sections 7.6.3 and 7.8 of this plan.
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i TABLE PS-1 PBt'OLkVICE INSPECTION - PUMP SUPPORTS l
Pump Design and Support Design Support i
Pu.p Instai14 tion Support Support and Erection Lacativa accessible or High Eadiation i
Pump Sark Specifications Ccde Mark Drawing Specifications ouildiaq/ inaccessAble
- one Ex amin a tion
+
Sitt EithtE E4EE Sbd EM2kiE Clegg Egalgt EgghgE-1252 ED U 2EltE EltIA1190
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PhESLEVICE INSPLCTION - TESSEL SGPPCETS l
Pump Decign and Support Design Support j
fump Insta164 tion Support Support and Erectian Loc. tion Accessibl+ or Hign Baliation Puay aark Specifications Code Mark Drawing Specifications EuildAng/ Inaccessitie Lane Examination E152 H Galt_t Eatt_as4_EMEttI G14E! E9512[_
EMahtL.
E!!!_Sud_H93ltt E1s!d11W2
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PEESERVIC E INSPECTION - HEAT EECHAN3f E SUPPORTS
[
Pump Design and Support Design Suppart P4ap Instat iat ion Support Support and Erection Location Accessible or High Eadiation l
Pump
!!a r c Specifications Code Mark Drawing S pecificat iciens Bui t. ding / Inaccessible Eone Examination j
8400
!!1BlitE Entt_thd_IMeltE Chgg Hut.htE_
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h 48t_iL51_]!435tE ElrY41194
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TAbtE PS-4 1
3 PhESEhTICE INSPECIION - PIPE SUPPOPTS Pump Desian and Support Design Sapport Pump Installation Support Support and Erection LacatiOL Accessitie or High Fadiatian i
Pump aart Spectitcations Code Mark Drawing Specifications maildi m4 / 1aaccessible 2sne Exaatnation
!4Et I495FiE
!!Bt_Ak9_ggatgg glggg Egghgg_
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TABLE PS-5 j
PkFSLEVICE INSPECTICM - VALY3 SUPPCRTS s
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' ?dap besign and Support Design Suppoct f
l.
-l Puan
, Specifications Code Mark Drawing Specifications Building / Inaccessit.Ae -
2xe Etaaikation Inste.iation Support Support and Erection Location Accessitie Jr High sadiation Pump
- Mars Jew';
$9 BD !E
!!s' i_8kd_'!9f hf E Eltf3 EEllRE_
!sghgE_
Eggt_ag G 3ktt EleYstieg
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1h1S T& ELE EILL BE 5F J's TED AUGOST 31, 1984.
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1 TAdLE PS-6 l
PL t.5 ES T IC.8 15:./ ECT IO h - IKTERVENING FLESEuf STTACHMENTS TO ASME COM&0b EFTS l
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j Pump Design and Support Design Support
{
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Pump MarA Specific at ions Code Mark Drawing Specifications Building / Inaccessibig tone ExamiLation i
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Nin' Mile Tsint Unit 2 6
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TABIb S-1 f
- AFETN RELifED SNUBBERS l
2 j
Pape Accessible or High Radiation Especially Difficult Exemptions From Snubber Code BZ Locat ion Inaccessible Zone During Shutdown to Remove Inspection Examination i
l System ID No.
Class Draw g o
( Are,a l (A or I)
(Yes or No)
(Yes or No)
(Yes or No)
Procedure I
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? ABLE IS* 1 t
Is$dPTICE INSP ECTION
- 9039 SUP'OR TS I
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Pump nark Specifications coJe mark Drawing Specifications 6etiding/
Inaccessitie tone Examination i
Etes EnsktL Itat.ani_ Esther Claff Esitti.
Esattt.
East _and_Esthet 112!t1129
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Psap Design and support Desisi
$sphort Pump Installation support support and Erect ion L ocation Accessstle or siqh Faliat ion Pu s p -
Bark Specifications Code Aark Drawing Speci f ica tions Ba1141ag/
Im access iba Zone Essaination Beat BathtE ESBR_11L4_I11ttE CAREQ 51thtE_
51EttE.
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- ABLE IS-4 L
INSEPTICE INSPECTION - PIPE SUPPC9TS
(
Pump Design and Support Design Support
[
Pump Installation Sapport Support and frection Location accessLLle os aigh Radiation
[
Pasp Hara Specifications Code mark Drawing S peci fica tions Building /
Ima cessib4e tone Esasisatloa
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EE9EtiME9-1 li THIS TABLE BILL dE SDBMITTED NOTR58E4 30, 1985.
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TABLE 15-5 11 SERVICE IBSPECTION - T ALT E SUPPOf f t i
4 Domp Design and Support Design Support Pusp Installation Support Supp3rt and Erection Location Accessitie or Biga Radiataca s
Fuap sath Ditt EURhti.
Specifications Code Mark Drating Specifica tions Se11 ding /
16accessibte Zona Enesiaation l
Ralf.RRA.212LtG Cleta EsattL E2tttE.
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$5pp3rt fump Installation sopport Support and Erection Location Accessille 3r High Radiation Pump aark Specifications Code
!t a r k Dravlag Specifications Building /
InaccessabAe Rose Emanisation E499 ES ELSE Eltt_SRd.EERLCE Geta EMMI Itsett.
Lest_nd_EinhE E12181192
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i Nine Mile Point Unit 2 TABLE V-3 VISUAL EXAMINATION Bolted and Closed Entire Threaded Welded Pinned Plate Beam To le ra nce Support Connect-Connect-Connect-Struc-Struc-Catalog Sliding Machined Condition Assembly tons ions ions tu re s tures items Surfaces Surfaces 1.
Missing Parts X
X X
X 2.
Loose Parts X
X X
X 3.
Wrong Parts (Size, Type, etc)
X X
X X
4.
Incorrect Assembly X
X X
X X
X 5.
Improper Alignment X
X X
6.
Improper Angular Alignment (Hot X
X and Cold Positions) 7.
Interferences-(Hot and Cold Positions)
X X
X 8.
Excessive Deformation X
X X
X X
X X
i 9.
Improper caps X
10.
Improper Clearances X
X X
X
'i
.1 1.
Insufficiert Thread Engagement X
X 12.
Incorrect Location X
13.
Corrosion X
X X
X X
X X
X X
14.
Erosion X
X X
X X
X X
X X
15.
Cracks X
X X
X X
X X
X X
16.
Linear Indications X
X 17.
Loss of Structural Integrity X
X X
X X
X X
18.
Wear X
X X
X X
X X
19.
Improper Torque or Tightness X
X 20.
Loose or Missing P. tint X
X X
X X
X X
21.
Scoring 22.
Debris X
X X
X X
23.
Excessive Roughness X
X X
X X
X 2 44. Weld Splatter X
X 25.
Arc Strikes X
X X
26.
Paint Deposits 3
1 of 1 i
4 T
Nine Mile Point Unit 2 TABLE V-4
()
VISUAL EXAMINATION VT-4 Spring Mechanical Hydraulic Condition Hangers Snubbers Snubbers Hot Position Setting X
X X
Cold Position Setting Within Required Acceptable Setting X
X X
Range Total Travel X
X X
Visible Indications of X
X X
Impaired Operability Operability Tests
- Friction Force or Binding Test X
X
[IWF-5400(1)]
X X
Lost Motion Test Acceleration Test X
[IWSF-5400(2) & (3)]
Actuation Velocity Test X
[IWF-5400(3)]
Bleed Rate Velocity Test O
X
[IWF-5400(3)]
X Pressure Leak Test t
- Operability tests will verify that the snubbers meet the oper-ability test requirements in the design specification and in.
IWF-5400.
1 of 1
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PRESSURE BOUNDARY (A)
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INTEGRAL j
NF OR NB, NC, ND AS DEFINED ATTACHMENT PAD (B)
IN THE SUPPORT DESIGN SPECIFICATIONS INTEGRAL SUPPORT m,
FIGURE 7-1 INTEGRAL ATTACHMENT lO
~, e e moa x go.ee coneon 1,0~
NINE MILE POINT-UNIT 2 w
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0.07n C = 0.05 (N-0.1n) WHERE n IS THE TOTAL NUMBER OF SNUBBERS IN THE FACILITY.
0.06n m
- g 0.05n O
0.045n
$ 0.04n E
m 0.03n REJECT REGION
________g, A
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N-NUMBER TESTED i
FIGURE 7-2 PLOT FOR ACCEPT-REJECT OF SNUBBERS NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2
Nine Mile Point Unit 2
)
SECTION 8 CODE CASES NMPC reserves the right to use any Code Cases applicable to the Edition and Addenda in use and which have been referenced by Regulatory Guide 1.147, and whose use may be necessary or desirable due to conditions found during the course of examinations.
It should be noted that all examinations of stainless steel piping systems shall be performed using procedures, techniques, and personnel which have been qualified to the requirements of the EPRI NDE Center for Detection of IGSCC.
A list of all Code Cases referenced in Regulatory Guide 1.147 actually used during the inspection of Unit 2 will be provided in November of 1985.
O 8-1 l
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Nine Mile Point Unit 2 SECTION 9 REQUESTS FOR RELIEF 9.1 Requests for Relief At the time of this submittal NMPC has not identified any Requests for Relief.
During the course of the Preservice Examination it may become necessary to seek approval from the NRC for Requests for Relief for Unit 2.
At such time that Requests for Relief are identified, they will be processed and evaluated and submitted to the NRC for approval.
A list of any Approved Requests for Relief for Unit 2 will be listed in a table in this section.
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l Nine Mile Point Unit 2 SECTION 10 i
- l' PROCEDURES FOR INSERVICE INSPECTION AND INSERVICE TESTING I
I 10.1 Inservice Inspection and Testing Procedures l
All approved ISI and IST procedures, including hydrostatic and preservice tests which are used for Unit 2, will be tabulated in this section when they become available.
a These procedures will be made available for review upon request.
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Nine Mile Point Unit 2 SECTION 11 PIPING SYSTEM ISOMETRICS 11.1 Piping Isometric Drawings A
tabulation of piping isometric drawings for systems covered by the preservice and inservice inspection plan will be listed in this section.
This list will be provided August 31, 1984.
The isometric drawings will be made available upon request.
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Nine Mile Point Unit 2
()
SECTION 12 COMPONENT DETAIL DRAWINGS 12.1 Component Detail Drawings A
tabulation of component detail drawings covered by the preservice and inservice inspection plan will be listed in this section.
This list will be provided August 31, 1984.
The drawings will be made available upon request.
O 12-1 O
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Nine Mile Point Unit 2 SECTION 13 1
i PIPING AND COMPONENT SUPPORT DRAWINGS 4
l
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13.1 Piping and Component Support Drawings A tabulation of the piping and component support drawings covered by the preservice and inservice inspection plan will i
be listed in this section.
This list will be provided by August 31, 1984.
i j
The drawings will be made available upon request.
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