ML20094Q193
| ML20094Q193 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/30/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20094P517 | List: |
| References | |
| PROC-951030, NUDOCS 9512010080 | |
| Download: ML20094Q193 (42) | |
Text
___-
l ATTACHMENT 3
\\
l i
B38 951031 800 TENNESSEE VALLEY AUTHORDY SEQUOYAH NUCLEAR PLANT PAGEI ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 A
TENNESSEE VALLEY AUTHORITY l
SEQUOYAH NUCLEAR PLANT ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT This document is to be used only for the second ten year inspection interval for ASNE Section XI l
REVISION NO.
I SUBMITTED BY bJk DATE /0 B-3 l
RAM R
l APPROVED BY sv um a,us DATE/=-e'+ r.
r ASME SECTION XI P CI PROGRAMS SUPV.
APPROVED BY DATE/0M0hf NECHANICAONdCLEAR LEAD ENGINEER DR A
0 327 Q
_PDR
./
-..._m.
~
D
i
't 1
- 3 s
1 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE2 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUhENT REV 1 REVISION LOG t
4 REVISION DESCRIPTION OF REVISION DATE 1
1 i
i 1
0 InitialIssue March 28,1994 3
i RIMS # B38951024801 i
i i
1 Minor editorial revisions.
k i
l I
i l
l f
4 i
l 1
a 4
f h
1 1
4 i
I s
TENNESSEE VALLEY AIRTIORITY SEQUOYAH NUCLEAR PLANT PAGE3 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 TABLE OF CONTENTS PAGE I.
CHARTER - MISSION - OBJECTIVES 4
II. PURPOSE - BASES - HISTORY 5
III. REFERENCES 6
IV. DEFINITIONS 7
V.
PROGRAM SCOPE AND PIAN 8
VI. REGULATORY REQUIREMENTS 9
VII. DESCRIPTION 10 VII
I. PROCEDURE
S 11 IX. RESPONSIBILITIES 16 X. TRAINING 17 APPENDICES APPENDIX A: ASME SYSTEM PRESSURE TESTING i
REQUESTS FOR RELIEF j
l ATTACHMENTS ATTACHMENT 1:
INDUSTRY CONTACTS ATTACHMENT 2:
PRESSURE TEST SCHEDULE
q e
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE4 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 I.
CHARTER Note:
This document has been prepared for the Second Ten Year ASME Section XI Inspection Interval.
Positions or commitments regarding the first ten year inspection interval should be based on existing FSAR, SER, and other system documents.
A.
MISSION STATEMENT The ASME Section XI Section shall incorporate TVA policies and standards to support safe and reliable operation of Sequoyah Nuclear Plant through the following:
- 1. Establishing and maintaining the ASME Section XI Pressure Test Program to ensure the requirements of 10CFR50.55a and Technical Specifications are met.
- 2. For all cases where ASME pressure test requirements are not met, or alternatives to Code requirements are proposed, provide a documented relief request with subsequent NRC approval.
- 3. Development of implementing procedures to satisfy programatic requirements by the Program Test Engineer.
The Program Engineer & the Program Test Engineer shall hold responsibility, accountability, and authority for accomplishing this mission and maintaining the program.
The Supervisor, ASME XI and Special Programs shall assign the Program Engineer and provide the resources necessary to accomplish this mission.
B.
OBJECTIVES The Objectives of the ASME Section XI Pressure Test Program areas follows:
)
- 1. Perform system pressure testing in accordance with ASME Section XI, 1989 Edition unless. relief is requested for alternative testing.
- 2. Perform system pressure tests taking into consideration the requirements of Code Case N-498.
- 3. Maintain system pressure boundary integrity by satisfing Tech Spec j
Surveillance Requirements 4.4.10.
- 4. Maintain clearly defined responsibilities of organizations involved with pressure testing.
- 5. Maintain applicable procedures, test equipment, and methods to current industry standards or better.
- 6. No NRC violations due to the ASME Pressure Testing Program l
I t
' TENNESSEE VALLEY AUmORITY
%QUOYAH NUCLEAR PLANT PAGES ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REVI II.
PURPOSE - BASES The rules for the inservice pressure testing for Nuclear Power Plant Components are contained in the ASME Boiler and Pressure Vessel Code,Section XI, Division 1.
10CFR50.55a of the federal law and Sequoyah's technical l
specifications require that ASME Section XI be met throughout the service life of the nuclear power plant and updated at each 10 year interval.
Under the provisions of 10 CFR 50.55a, inservice pressure testing of safety related piping systems will be performed in accordance with a specific edition of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
The interval dates, applicable editions and addenda for the first 10 year interval were as follows:
First Interval Start Unit 1: 7/1981 First Interval Start Unit 2: 6/1982 The present Code of Record is ASME Section XI, 1977 Edition with Addenda through Summer 1978.
The following are in &ccordance with ASME Section SI, 1980 Edition with Addenda through Winter 1981 in lieu of the Code of Records 1)
Test Pressurization Boundaries (IWA-5211(d),
IWA-5224, IWA5221 and i
Footnote 1 for Examination Category B-P c C Table IWB-2500-1]
2)
Definition of " Normal Reactol Operations" (Footnote 4 of IWB-1000) 3)
Hydrostatic Pressure Including Static Head (IWA-5265 (b)]
4)
Code Class 1 or Equivalent Specified Test Pressure (IWB-5222 (a) & (b)]
5)
Code Class 2 and 3 or Equivalent - Use of Design Pressure (IWC-5222 (a) ]
6)
Definition of " Opened-Ended" Systems and Components (Footnote 1 of IWC-5222(d)
As required by 10 CFR 50.55a (b), the effective edition of Section XI with regard to the second ten year interval is as follows:
Second Interval Start Units 1 & 2: Estimated 12/15/95 Unit 1 & 2:
1989 Edition Additionally, IWA-5214 (a) from the 1990 Addenda will be used. This addenda resolves the conflicts between the references given in IWA-5214(a) in the 1989 Edition.
)
l i
I r
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE6 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 III. REFERENCES 1.
- 2. Code Case N-498, Alternative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and 2 Systems.
- 3. ASME Boiler and Pressure Vessel Code,Section XI, Division 1, 1989 Edition.
- 4. ASME Boiler and Pressure Vessel Code,Section III, 1989 Edition.
- 5. ANSI /ASME N45.2.6-1978,-Qualification of Inspection Examination and Testing Personnel for Nuclear Power Plants.
- 6. TVA Calculation SQN-SQTP-001, ASME Section XI Inservice Code Class Boundaries for the Second 10 Year Interval.
- 7. Reserved B. Reserved
- 9. Sequoyah Nuclear Plant Technical Specifications
- 10. Sequoyah Nuclear Plant Design Criteria and Design Guides:
- a. SQ-DC-V-3.0 Classification of Piping, Pumps, Valves and Vessels
- b. SQ-DC-V-2.16 Single Failure Criteria
- c. SQ-DC-V-3.2 Classification of HVAC Systems
- 11. TVA submittals to the NRC (later)
- 12. STD - 6.9, Repair / Replacement of ASME Section XI Components
- 13. STD - 8.5, ASME Section XI System Pressure Test Program
- 14. SSP - 9.56, Raw Water Fouling and Corrosion Control Program
- 15. SON UFSAR
- 17. ASME Code Case N-522, Pressure Testing of Containment Penetration Piping
- 18. Memo from NRC to 0.D.
Kingsley, Jr., Authorizing Use of ASME Code Case N-416-1, TAC No.'s M90602 and M90603.
- 19. Memo from NRC to O.D. Kingsley, Jr., Request to Use ASME Code Case N-498-1 as an Alternative to the Required Hydrostatic Pressure Test, TAC No.'s M91827 and M91828.
- 20. Memo from NRC to 0.D. Kingsley, Jr., Authorization to Use ASME Code Case N-522, TAC No.'s M90930 and M90931.
r 4
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE7 ASME SYSTEM PRESSURE TESTINGyROGRAM BASIS DOCUMENT REV1 IV. DEFINITIONS 1.
Interval - That amount of time approximately equal to 1/4 of expected plant life (10 years).
See IWA-2432, 2150(d), 2430(e), and IWB-2412.
2.
Period That amount of time in calendar years and/or months approximately equal to 1/3 of an interval.
3.
Design Temperature and Press'tre - The design temperature and pressure of a specified system or portion of piping shall be determined by the corresponding system flow diagram.
- 4. Nominal Temperature and Pressure - The system or component is lined up and exposed to pressure and temperature conditions associated with normal plant operation, or for standby systems those conditions required for the associated system to perform its design safety function.
- 5. Buried Component - A component that is buried or encased in concrete. This does not include pipmg which penetrates a concrete wall.
This piping is considered inaccessable per IWA-5240.
6.
Open Ended - A condition of piping or lines that permits free discharge to open atmosphere or containment atmosphere.
1 I
l l
i TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE8
)
ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 i
V.
PROGRAM SCOPE & PLAN SCOPE ASME Section XI, Table IWX-2500-1 identifies those components and test frequency applicable to the pressure test requirements of IWA-5000 for periodic and interval testing.
The applicable tables and examination categories in relation to code class are as follows:
Class 1...... Table IWB-2500-1........ Category B-P, B-E Class 2...... Table IWC-2500-1........ Category C-H, C-B Class 3...... Table IWD-2500-1........ Category D-A, D-B, and D-C Class MC..... Table IWE-2500-1........ Category E-P (for Metal Containments penetrations; note that this will be performed under the Appendix J program)
Additionally, repair / replacement activities performed in accordance with the requirements of ASME XI shall be pressure tested prior to resumption of service if required by IWA-4000 or IWA-7000. Alternatively, the requirements of Relief Request ISPT-2 may be used to satisfy the pressure test requirement in lieu of Code required hydrostatic testing. provides a pressure test schedule for the systems included within the ASME Section XI boundaries.
This schedule gives general information of the systems, boundaries, and the tests required by periods for the second interval.
This schedule may be amended as needed as long as compliance with all the Code requirements for system pressure testing is obtained.
i PLAN A. The ASME pressure tests shall be reviewed and approved by the Program Test Engineer.
]
B.
The ASME pressure test-records shall be maintained in accordance with Subsections IWA ~400, IWA-5300 and IWA-6000 of the 1989 Edition of ASME Section XI.
l l
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE9 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV I VI.
REGULATORY REQUIREMENTS 10CFR50.55a (g) requires the inservice inspection and pressure testing of ASME Code Class 1,
2, and 3 components per the 1989 Edition of ASME Section XI.
ASME Section XI. Subsections IWA,
- IWB, IWC, IWD and IWE identifies those components and/or systems which shall be tested pursuant to IWA-5000 or 10CFR50 Appendix J for IWE.
Later editions and addenda pursuant to paragraph
- 50. 55a (g) (4) (iv) and the use of ASME Code Cases pursuant to footnote 6 to 50.55a of 10CFR50 also apply.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 10 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 VII. DESCRIPTION Under the provisions of 10 CFR 50.55a, pressure testing will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
As required by 10 CFR 50.55a (b), the effective edition of Section XI with regard to the second ten year interval is the 1989 Edition, Division 1.
The pressure test program shall be conducted in accordance with Article IWX-5000 (where IWX refers to IWB, IWC, etc.) of Section XI of the ASME Boiler and Pressure Vessel Code (applicable Edition and Addenda) except for relief requested under the provisions of 10 CFR 50.55a and approved test alternatives contained in code cases listed in the test program.
A 1
= _ _.-
TENNES$dE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE11 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 VIII. PRESSURE TEST REQUIREMENTS A. Test Description The pressure retaining components within each system boundary shall be subject to system pressure tests.
When test conditions are stable and any required hold times are satisfied a visual examination C-2 shall be performed to detect any leakage. The required system pressure tesLs may be conducted in conjunction with one or more of the following system tests:
t,
- 1. A System Leakage Test conducted following opening and reclosing of a Class 1 system at nominal operating pressure, and prior to plant startup following each reactor refueling outage. When a system leakage test is performed to satisfy the periodic test requirements identified in Table IWB-2500-1, or after reassembly of mechanical joints, no holding time is required after attaining test pressure and temperature conditionc.
When a system leakage test is performed in lieu of a 10-year hydrostatic test the system shall be pressurized to nominal operating pressure for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for noninsulated systems as per Code Case N-498 When testing to satisfy N-498 the boundary subject to test pressurization and VT-2 examination shall extend to all Class 1 pressure retaining components within the system boundary.
- 2. A System Functional Test conducted to verify operability in systems or components not required to operate during normal plant operation while under system operating pressure. When a system functional test is performed to satisfy the periodic test requirements identified in Table IWC-2500-1 or IWD-2500-1 a 10 minute holding time is required af ter attaining system operating pressure.
l When a system functional test is performed to satisfy N-498 requirements in lieu of a 10-year hydrostatic test the system shall be pressurized to nominal operating pressure for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for noninsulated systems. The system shall be maintained at nominal operating pressure during the performance of the VT-2 visual examination. The boundary subject to test pressurization and examination shall extend to all Class 2 components included in those portions of systems required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
Componerts outside the boundary pressurized under a periodic system / component functional test may be tested separately in a system inservice pressure test.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 12 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 3.
A System Inservice Test conducted to perform a VT-2 visual examination while the system is in service under operating pressure. The system inservice test is normally applied to those safety systems which may be required to operate during the course of normal plant operation. When an inservice test is performed to satisfy the periodic test requirements identified in Table IWC-2500-1 or IWD-2500-1, no holding time is required provided the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
When a system inservice test is performed to satisfy N-498 requirements in lieu of a 10-year hydrostatic test the system shall be pressurized to nominal operating pressure for a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for noninsulated systems. The system shall be maintained at nominal operating pressure during the performance of the VT-2 visual examination. The boundary subject to test pressurization and examination shall extend to all components included in those portions of systems required to operate oi.
support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
NOTE:
The preceding system pressure tests may be used in lieu of a 10-year hydrostatic test for Class 1 and 2 safety systems providing the criteria specified in Code Case N-498 is satisfied during test performance.
Additionally, these same system pressure tests may be used in lieu of a 10-year hydrostatic test for Class 3 safety systems providing the criteria specified in Relief Request ISPT-1 is satisfied.
- 4. A System Hydrostatic Test conducted during plant shutdown at a pressure above nominal operating pressure or system pressure for which overpressure protection is provided. When performing a system hydrostatic test a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> holding time is required af ter attaining the test pressure and temperature conditions for insulated systems and 10 minutes for noninsulated systems or components. A hydrostatic test shall be required for those portions of safety systems which are not exposed to nominal operating pressure when testing pursuant to Code Case N-498 or Relief Request ISPT-1. System hydrostatic tests shall be conducted at the test conditions of pressure and temperature specified in IWB-5000, IWC-5000, and IWD-5000.
5.
A System Pneumatic Test conducted in lieu of a hydrostatic pressure test for components within the scope of IWC and IWD. When performing a system pneumatic test a 10 minute holding time is required after attaining test pressure.
1 l
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 13 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 B.
Test Pressurization Boundaries The following test pressurization and examination boundaries are applicable when performing those periodic tests identified in Table IWX-2500-1. The boundary limits, as discussed in the following, are generally defined by the location of the safety class interface valves within the system.
1.
System Leakage Test Boundary The boundary subject to test pressurization and VT-2 visual examination shall extend to the pressure retaining components within the system boundary containing pressurized reactor coolant under the plant mode of normal reactor startup ( Mode 2
).
2.
System Functional Test Boundary - The boundary subject to test pressurization and VT-2 visual examination shall include only those pressure retaining components within the system boundary pressurized under the test mode required during the performance of a periodic system / component functional test. Quarterly pump testing performed on a minimum flow test circuit does not satisfy the required test boundary if a test circuit is utilized during refueling outages which encompasses an injection flow path.
3.
System Inservice Test Boundary -
The boundary subject to test pressurization and VT-2 visual examination shall extend to those pressure retaining components under operating pressures during normal system service.
1 4.
System Hydrostatic Test Boundary - The boundary subject to test pressurization and VT-2 visual examination shall include only those portions of systems that were not exposed to nominal operating pressure when tested pursuant to Code Case N-498 or Relief Request ISPT-1.
The ASME Section XI Class 1, 2,
& 3 boundaries are defined by the Color Coded ISI drawings and calculation SON-SQTP-001.
Control of these drawings and this calculation is the responisbility of the Nuclear Engineering Department at SQN.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 14 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 C. Corrective Action The source of leakages detected during the performance of system pressure tests shall be evaluated by the Program Engineer for corrective measures as follows:
1.
Buried components with leakage losses in excess of limits acceptable for continued service shall be repaired or replaced.
2.
If leakage occurs at a bolted connection, corrective action shall be initiated in accordance with the requirements of Relief Request ISPT-03.
3.
Repairs or replacement of components shall be performed in accordance with IWA-4000 or IWA-7000, respectively.
4.
When boric acid residue is detected on components, the leakage source and the areas of general corrosion shall be located. Components with local areas of general corrosien which reduce the wall thickness by more than 10% shall be evaluated to determine whether the component may be acceptable for continued service, or whether repair or replacement is required.
1
a TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 15 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 D.
Instrument Requirements NOTE:
The following instrument requirements are applicable ONLY when performing system hydrostatic tests.
Any pressure measuring instrument or sensor, analog or ditigal, including the i
pressure measuring instrument of the normal operating system instrumentation may be used provided the following requirements are met.
1.
Accuracy The pressure measuring instrument or sensor used shall provide results accurate to within 0.5% of full scale for analog gages and 0.5% over the calibrated range for digital instruments.
2.
Calibration All pressure measuring instruments shall be calibrated against a standard deadweight tester or calibrated master gage. The gages shall be calibrated before each test or series of tests. A series ci tests is a group of tests that use the same pressure measuring instrums. :s and that are conducted within a period not exceeding 2 weeks.
3.
Ranges Analog gages shall have a graduated range of at least 1.5 times, but not 4
more than 4 times the intended maximum test pressures. Digital pressure i
instruments shall be selected such that the intended maximum test pressure shall not exceed 70% of the calibrated range of the instrument.
4.
Location The pressure measuring instrument shall be connected close to the component when testing an isolated component. When testing a group of components or system the instrument shall be connected to any point in the boundary such that the imposed pressure on any component, including static head, will not exceed 106% of the specified test pressure for the system.
l 1
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE16 i
ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUNENT REV1 IX. RESPONSIBILITIES
- 1. Program Engineer (Nuclear Engineering)
Overall Program Ownership i
Ensure compliance with existing regulations and standards and update as required Maintain Design Basis Calculations, Program Basis Documents, and IST Drawings j
- 2. Program Test Engineer (Technical Support) l Ownership of Site Standard Practice 8.5 " Pressure Test Program" Site Contact for all system pressure testing i
Procure services and equipment necessary to perform the pressure tests Coordinate test schedules with Operating and Outage schedules Coordinate pressure tests Prepare appropriate Reports (PERs, Periodic Test Reports)
Review and approve test results Maintain pressure test procedures Ensure periodic tests are performed on schedule Ensure instrumentation and test equipment necessary to perform system pressure tests is maintained and available for testing Maintain a tracking system to ensure periodic system pressure tests are scheduled and performed to meet periodic and interval system pressure tesing requirements
- 3. Corporate Preparation and Maintenance of corporate standards.
Interperation and coordination of ASME Code interperations and application of generic programs.
Coordinate, review and assist in preparation of requests for relief and submittals.
Periodic assessments of site code programs
- 4. Others Operations shall support the pressure tests with valve lineups and equipment operation as required operations shall perform their portion of the pressure test procedure Instrument Maintenance shall provide for calibration of necessary instrumentation The Mechanical Maintenance organizations shall provide corrective maintenance and test support as necessary
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 17 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 X.
TRAINING 1.
Program Engineer & Program Test Engineer Understanding of 10CFR50.55a Knowledge of test instrumentation used to perform pressure tests Knowledge of industry standards and ASME Section XI 2.
Test Performers Understanding of 10CFR50.55a Knowledge of test instrumentation used to perform pressure tests Knowledge of industry standards and ASME Section XI (as it applies to the performance of testing) i i
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 18 ASME SYSTEM PRESSURE TESTING PROGRAM B ASIS DOCUMENT REV1 APPENDIX A REQUEST FOR RELIEF In the event specific test requirements of 10CFR50.55a and ASME XI are impractical and cannot be met, specific relief may be granted by the NRC.
Additionally, requests for relief are included whereas TVA's opinion is such that the proposed alternative testing provides adequate assurance of pressure boundary integrity.
L i
i
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 19 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 REQUEST FOR RELIEF ISPT-01
Subject:
10-Year hydrostatic pressure test requiremnts for Class 3 systems.
Components:
All Class 3 piping systems which are applicalbe to the hydrostatic pressure test requirements of ASME Section XI.
Code Requirement:
A system hydrostatic pressure test (IWD-5223) and accompanying VT-2 examination is required at least once each inspection interval (Table IWD-2500-1, Categories D-A, D-B, and D-C).
Basis for Relief:
Since the acceptance of Code Case N-498 it has been common recognition that 10-year hydrostatic pressure testing can be somewhat burden some, and in some instances, may expose components to unnecessary stress levels without significant enhancement to quality or safety. TVA SQN employs a very comprehensive corrosion monitoring and control program which periodically performs visual examinations and wall thickness examination by volumetrics on selected Class 3 piping and components as a very accurate means of monitoring for pressure boundary degredation.
It is SQN's position that performing system pressure tests on Class 3 systems consistant with the requiretr.ents of N-498-1 in conjunction with the Corrosion Monitoring Program provides equivalent or superior assurance of system integrity as that provided by the code.
Alternate Testing:
The requirements of ASME Code Case N-498-1 will be used for the requirements of system pressure testing for Class 3 systems.
e TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 20 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 REOUEST FOR RELIEF ISPT - 02
Subject:
Pressure test requirements for welded repairs or installation of replacement items by welding.
Components:
All Class 1,
2, and 3 components which receive welded repairs or are installed by welding as replacements.
Code Requirements:
After repairs by welding on the pressure retaining boundary, a system hydrostatic test shall be performed in accordance with IWA-5000.
Basis for Relief:
Class 1,
2, and 3 pressure boundary replacements requiring installation by welding are normally constructed and supplied in accordance with th requirements of ASME Section III which provides for cydrostatic testing at the manufacturers.
Subsequent to installation hydrostatic pressure testing is a means of proving weld integrity.
Performing NDE and invoking acceptance criteria in accordance with current ASME III requirements in addition to a system leakage test provides reasonable assurance that weld integrity is maintained at an acceptable level of quality. Its is TVA SQN's position that the performance of hydrostatic testing subsequent to weld repairs and the installation of welded replacements is an impractical requirement which could not only expose components to unnecessary stress levels, but provides little or no enhancement to the level of quality or safety.
Alternative Testing:
The requirements of ASME Code Case N-416-1 shall be used.
l TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PIANT PAGE 21 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 l
REOUEST FOR RELIEF ISPT - 03
Subject:
Bolting examination (VT-3) subsequent to flange leakage occuring during a system pressure test.
Components:
All bolting associated with Class 1,
2, and 3 flange connections which receive a visual examination (VT-2) during i
the performance of system pressure testing.
Code Requirements:
If leakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100.
(IWA-5250 (a) (2) Corrective Measures)
Basis for Relief:
Current Code requirements specify that all bolting must be removed in the event of a bolted connection leak for the purpose of VT-3 examination and evaluation. This would require placing the associated component or portion of piping out of service possibly resulting in plant shutdown, delaying plant startup, or placing the plant in an unsafe condition for continued operation. Additionally, removal of all bolting is impractical if there is reasonable assurance that bolting material is of a specification which is not susceptible to corrosion when in contact with leaking fluid.
It is TVA SQN's position that proposed alternative testing provides an acceptable level of quality and safety as that
'provided by the Code.
Alternative Testing:
The requirements of IWA-5250 (a) (2) of the 1990 Addenda to the 1989 Edition will be used.
1
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 22 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 REOUEST FOR RELIEF ISPT - 04
Subject:
Pressure testing of non-safety system process piping in a containment penetration.
Components:
All Class 2 penetration piping whereas the inboard ' and outboard piping outside the containment isolation valves is classified as non-safety related.
l Code Requirements:
1)
- Piping, pumps, and valves that are part of the containment system, or which penetrate or are attached to the containment vessel. These components shall be examined in accordance with IWB or IWC, as appropriate to the classification defined by the design specification.
(IWE-1220(d)).
- 2) Pressure retaining components, piping and valves require a system pressure test, inservice or functional (IWC-5221) and/or a system hydrostatic test (IWC-5222) in conjunction with a VT-2 visual examination (Table IWC-2500-1, Category C-H).
Basis for Relief:
The portion of piping that penetrates containment and the associated inboard and outboard containment isolation valves are required to be constructed in accordance with Class 1 or 2 design requirements. In the instance where the penetration is associated with a non-safety system, the sole function of the penetration and the associated valves are to provide containtnent isolation capability for the protection of containment integrity during the unlikely event of a loss of the attached non-safety piping. In all cases the isolation valves associated with these penetrations are maintained, during normal operation, in the locked closed position or close upon receipt of a containment isolation signal. The safety function of these penetrations is verified by 10CFR50 Appendix J leakage testing. The performance of additional pressure tSating, as required by Table IWC 2500-1, Category C-H, is considered impractical in the sense that there is minimal enhancement to quality or safety resulting from the additional testing. It is TVA SQN's position that testing pursuant to 10CFRSO Appendix J requirements provides an acceptable level of quality and safety as the additional pressure testing requirements of the Code.
i Alternative Testing:
The requirements of ASME Code Case N-522 shall be used.
)
i I
I TENNESSEE VALLEY AUTHORFIY SEQUOYAH NUCLEAR PLANT PAGE 23 i
ASME SYSTEM PRESSURT FESTING PROGRAM BASIS DOCUMENT REV 1 F JUEST FOR RELIEF ISPT
,Q},
Subject:
Pressure testing of Class 1 components.
Components:
ASME Code Class 1 vents, drains, test and fill piping which range in diameter from 3/4 inch to 2 inches.
1 Code Requirement:
ASME Section XI, Subsection IWB-2500, Table IWB-2500-1, Category B-P, Footnote 1 states that *The entire pressure retaining boundary of the reactor coolant system is subject to system pressure test conducted in accordance with IWA-5000 with the exceptions specified in IWA-5214 when system I
pressure tests are conducted for repaired, replaced, or altered components."
Basis for Relief:
Various piping segments are located in open-end tailpipes that serve as vent, drain, test, or fill lines. Manual valves and flanges bound these piping segments to provide the design-required double isolation at the reactor coolant pressure boundary. These piping segments are not normally l
pressurized.
Pressure testing of these piping segments at nominal operating pressure in Mode 3 would require that the inboard isolation valve be opened when the reactor coolant j
system (RCS) is at full temperature and pressure (547 F and 2245 psig). The action would violate the design requirement for double isolation valve protection.
The potential for j
spills when opening the system presents a significant risk of personnel contamination.
Pressure testing in Mode 6 would require that a hydrostatic pump be connt.cted at each segment location. However, for some segments there is no connection available and would require a modification for installation of a pump connection. These piping segments are location in high-radiation areas and testing would result in high personnel radiation exposure. A breakdown of the dose estimates for each radiation area in the plant is provided below:
- 1. RCS Loop Drains 6 items at 10 person-hours per item at 300 mR/ hour l
- 2. Reactor Vessel Head Vents 2 items at 10 person-hours per item at 150 mR/ hour and 2 items at 8 person-hours per item at 20 mR/ hour.
- 3. Pressurizer Spray Vents 2 items at 10 person-hours per item at 200 mR/ hour.
a
- 4. Excess Letdown Drain 1 item at 8 person-hour per item at 50 mR/ hour.
- 5. RCS Seal Drains and Vents 4 items at 8 person-hours per item at 20 mR/ hour and 4 items at 8 person-hour per item at 50 mR/ hour where mR stands for millirem. This results in a total of 27.960 Rem of dose accumulated for performing these tests.
This data is based on estimated durations and actual survey data from SQN's cycle 5 outages. These radiation exporure
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 24 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 estimates are based on a pressure test in f4 ode 6 when each of the blind flanges would have to be removed, a test flange installed, and a hydrostatic pump connected.
Personnel would remain in the area to perform the test, disconnect the test equipment, and reinstall the blind flange.
These piping segments are visually inspected each refueling outage as the unit returns to-operation. These segments are not specifically pressurized past the first isolation valve for this inspection.
It is possible that the piping is pressurized because of leakage at the first isolation valve.
With these inspection being performed approximately six times in each inspection interval, the increase in safety achieved from the required nominal operating pressure test is not commensurate with the hardship of performing such testing.
Alternate Testing:
These piping segments will continue to be visually inspected following each refuel ~ng outage for leakage and evidence of i
past leakage during the RCS leakage test.
This test is conducted with the RCS at full operating temperature and pressure.
2 I
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE25 ASME SYSTEM PRESSLTRE TESTING PROGRAM BASIS DOCUMENT REV1 REQUEST FOR RELIEF - ISPT-06 VT-2 EXAMINATION
Subject:
Alternative requirements for Qualification of VT-2 Examination Personnel Components:
All ASME Class 1, 2,
and 3 pressure retaining components subject to the requirements of pressure testing.
Code Requirements:
ASME Section XI, Subsection IWA-2300 requires that personnel performing examinations be qualified and certified using a written practice prepared in accordance with SNT-TC-1A and the additional requirements of Division 1 of ASME Section XI.
Basis for Relief:
ASME Section XI Code Case N-546 has been approved by ASME but has not been published nor has it been accepted for use by the NRC through Regulatory Guide 1.147.
This Case provides alternative requirements for the qualification of personnel to perform VT-2 examinations. The opinion of the Committee is that VT-2 visual examination personnel need not be qualified nor certified to comparable levels of l
competence in accordance with the referenced standard (i.e.,
ANSI N45.2.6, ASNT SNT-TC-1A, or ASNT CP-199) provided the examination personnel are qualified in accordance with the l
following requirements, j
1.
At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> plant walkdown experience, such as that gained by licensed and nonlicensed operators, local leak rate personnel, system engineers. and inspection and nondestructive examination personnel.
2.
At least four hours of training on Section XI requirements and plant specific procedures for VT-2 visual examination.
3.
Vision test requirements of IWA-2321, 1995 Editica.
The use of this Case will allow SQN to use experienced plant personnel to perform the VT-2 examination during the performance of system pressure tests.
These personnel are knowledgeable of the plant systems and routinely perform walkdowns of the plant systems looking for abnormalities such as leaks in piping systems. By performing routine walkdowns, they are more familiar with the location of piping systems and can therefore perform a VT-2 examination in a more timely manner.
Plant operators have a keen sense of duty while performing their daily rounds to ensure that plant systems are operating correctly and reporting problems such as leakage from piping systems.
System Engineering perform routine walkdowns as part of their job to ensure that plant systems are operating correctly. Their experience, responsibility, and knowledge should be used and can help the plant perform system pressure testing in a more timely and responsible manner which helps to ensure that plant piping systems operate correctly which is the intent of performing ASME Section XI system pressure tests.
Using these personnel will also allow SQN to eliminate the need
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 26 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REVI for hiring additional personnel certified te the requirements of IWA-2300 especially during refueling outages when system pressure tests are typically performed.
Since the VT-2 examination is an examination for the evidence of leakage, the use of plant personnel, certified to the alternative requirements, who typically perform this type of examination during their daily job duties will not compromise the quality or safety of the VT-2 examinations.
Alternative F.equirement:
SQN will use ASME Code Case N-546 as alternative requirements for the qualification of VT-2 examination personnel.
i 4
.i l
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 27 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 r
r ATTACHMENT 1:
INDUSTRY CONTACTS NOTE: This Attachment is a separate document and may be revised and included herein without a revision to the Program Basis Document.
I j
c 1
4 4
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 28 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 INDUSTRY CONTACTS NAME PLANT PHONE Becky Badham Farley 205-899-5156 x3598 David Hartline Farley 205-899-5756 x3522 Brian Andrie Perry 216-259-3737 x7654 Dennis Devay y
Perry 216-259-3737 x7656 Joe Kusnicki LaSalle 815-357-6761 x2575 Kleth Moser Braidwood 815-458-3803 Mike Sears Braidwood 815-458-2801 x2251 Roger Sagmoe Braidwood 815-458-2801 x2363 Jay Smith Bryon 815-234-5441 x2604 Frank Schaaf (Chairman, XI PT WG)
Glnna 716-724-8681 Mike Parerak ANO 501-964-8852
^
D.H. Pellham ANO 501-964-8935 Chris Bergren Indian Point 2 914-526-5756 Rick Jackson Shearon Harris 919-362-2069 Steve Scott Grand Gulf 601-437-6779 Mike Blew Turkey Point 305-246-6488 Bob Clew Turkey Point 305-246-6488 Mark Hickox Vogtle 404-826-4129 Dave Dobson Duane Amold 319-851-7320 All Egap Nine Mile 315-428-7314 Joe Barile Millstone 203-444-5584 Dave Foken Commanche Pk.
817-897-6550 Ben Mays Comanche Pk.
817-897-6816 T. R. Huber Surry 804-385-2034 Tom Porter North Anna 703-894-2817 Steve Jnhnson Wolf Creek 316-364-8831 x4491 Larry Hollaway Wolf Creek 316-364-8831 x4408 Jeff Isch Wolf Creek 316-364-8831 x4462 Dave Gollott LaSalle 815-357-6761 x2325 l
Jeff Parker McGuire 704-875-4772 Joel Reeves Catawba 803-831-3835 Chris Freer D.C.Ccok 616-465-5901 x1110 Larry Collier V. C. Summer 803-345-4049 i
Craig Younger S. Texas 512-972-8186 i
Chris Pendleton Diablo Canyon 805-595-4242 Kevin Christian Grand Gulf 601-437-6784 Brian Pae Wolf Creek 316-364-8831 x4425
3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAG 2 29 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 INDUSTRY CONTACTS NAME COMPANY PHONE David Gallino Gilbert / Commonwealth 215-775-2600 John Sullivan Gilbert / Commonwealth 615-756-0113 Tim Cottengim Gilbert / Commonwealth 215-775-2600 Donald Barlow Stone & Webster 617-598 7158 Dave Kanuch UESC 708-945-0555 DeWain Forbes UESC 708-945-0555 Mark Goodman UESC 708-945-0555
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 30 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV I ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 1
47W801-1 2
Main Steam system piping and Code Case Inservice Inservice 47W803-2 components described below (excluding N-498 S/Gs):
hydro test From Steam Generator i to FCV-1-15, attemative FCV-1-4 and FCV-1-147.
From Steam Generator 2 to FCV-1-11 and FCV-1-148.
From Steam Generator 3 to FCV-1-22 and FCV-1-149.
From Steam Generator 4 to FCV-1-16, FCV-1-29 and FCV-1-150.
1 47W803 2 2 and 3 Main Steam supply to Turbine Driven Inservice inservice Code Case 47W803-3 Auxiliary Feed Water Pump terry turbine N-498 as described below:
(Class 2) or N-498-1 From FCV-1-15 and FCV-1-16 through TDAFW Pump A-S terry turbine to roof (Class 3) exhaust and steam traps at drain tank.
hydro test attemative 1
47W801-2 2
Steam Generator Blowdown system piping Code Case Inservice inservice 47W862-1 and components described below-N-498 From Steam Generator 1 to FCV-1-7 hydro test attemative (including sample line),
From Steam Generator 2 to FCV-1-14.
i From Steam Generator 3 to FCV 1-25.
From Steam Generator 4 to FCV-1-32.
3 47W803-1 2
Main Feed Water system piping and Code Case Inservice inservice 47W803-2 components described below (boundary N-498 extends to non-isolated portions of hydro test Auxiliary Feedwater system):
attemative From Steam Generator 1 (including S/G shell) to 3-832,3-373 and FCV 33.
From Steam Generator 2 (including S/G shell)to 3-922 and FCV-1-14.
From Steam Generator 3 (including S/G shell) to 3-921 and FCV-1-25.
From Steam Generator 4 (including S/G shell) to FCV-1-32.
I
1 j
TENNESSEEVALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 31 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS ist 2nd 3rd PERIOD PERIOD PERIOD 3
47W803-2 2
Auxiliary Feed Water system piping and Code Case Functional Functional components as described below:
N-498 Normally isolated Class 2 portion of hydro test AFW to Steam Generator 2. From 3 attemative 831 and 3-872 to 3-922.
Normally isolated Class 2 portion of AFW to Steam Generator 3. From 3-830 and 3-871 to 3-921.
3 47W803-2 3
Auxiliary Feed Water system piping and Functional Functional Code Case components as described belew:
N-498-1 From 3-805 through MDAFW Pump A.
hydro test attemative A to 3-831 and 3-832.
From 3-806 traough MDAFW Pump B-2 B to 3-830 and 3-833.
From 3-810 through TDAFW Pump A-S to 3-871,3-872,3-873 and 3-874 26 47W850-10 2
Fire Protection system piping and Code Case Code Case Code Case components as described below:
N-522 App.
N 522 App. N-522 App.
J test J test J test Portion of system penetrating containment from FCV-26-243 to 26 attemative attemative altemative 1296.
j 31 47W865-5 2
R_ actor Building Instrument Room Chilled Code Case Code Case Code Case Water system piping and components as N-522 App.
N-522 App. N-522 App.
described below:
J test J test J test attemative altemative attemative Portion of system penetrating containment from FCV-31C-224 to FCV-31C-225 and 31C-734.
Pottion of system penetrating containment from FCV-31C-222 to FCV-31C-223 and 31C-752.
Portion of system penetrating containment from FCV-31C-231 to FCV-31C-232 and 31C-697.
Portion of system penetrating containment from FCV-31C-229 to FCV-31C-230 and 31C-715.
g.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGEM ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV I ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS ist 2nd 3rd PERIOD PERIOD PERIOD 31 47W865-8 3
Shutdown Board Rooms Chilled Water Inservice Inservice Code Case system piping and components as N-498-1 described below:
hydro test attemative From Compression Tank and Air Separator through CW Pump A-A, Water Chiller Package A-A and Air Handling Units 1 A-A and 2A-A to pump suction.
From Compression Tank and Air Separator through CW Pump B-B, Water Chiller Package B-B and Air Handling Units 18-B and 2B-B to pump suction.
59 47W856-1 2
Demineralized Water system piping and Code Case Code Case Code Case components as described below:
N-522 App.
N-522 App.
N-522 App.
J test J test J test Portion of system penetrating containment from 59-522 to 59-633.
altemative attemative attemative 61 47W814-2 2
Ice Condenser system piping and Code Case Code Case Code Case components as described below:
N-522 App.
N-522 App.
N-522 App.
Portion of system penetrating J test J test J test containment from FCV-61-191 to FCV.
attemative attemative attemative 61-192 and 61-533.
Portion of system penetrating containment from FCV-61-193 to FCV-61-194 and 61-680.
qs l
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 33 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 62 47W809-1 2
Chemical and Volume Control system Code Case Code Case Inservice 47W809-2 piping and components as described N-498 N-498 47W811-1 below:
hydro test hydro test Letdown line from FCV-62-70 through attemative attemative Regenerative Hx, Letdown Hx (TCV-(Unit 1)
(Unit 2) 61-79 and LCV-62-118 aligned to VCT) and VCT to charging pump suction header.
Exces letdown from transition piece and RCP seat retum line from RCP seals through Seal Water Hx to connection to charging pump suction header.
Charging pump suction header to the first normally closed valve.
From charging pumps suction header through Centrifugal Charging Pumps A-A and B-B (including miniflow line) to seal injection check valves62-560, 561,562 and 563, charging check valves62-716 and 717, pressurizer spray isolation valve 62-84 and high head safety injection valves FCV 39 and FCV-63-40.
62 47W809-2 3
Chemical and Volume Control system inservice Code Case Inservice 47W809-5 piping and components as described N-498-1 below:
hydro test attemative Boric Acid Tanks A, B and C through Boric Acid Transfer Pumps and Boric Acid Blender to FCV-62-138,62-929,62-935,62-936 and FCV-62-144.
i
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 34 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 ATTACHMENT 2
~
PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 62 47W809-1 3
Chemical and Volume Control system Not Not Not 47W809-2 piping and components as described Required Required Required 47W809-3 below:
47W809-4 From TCV-62-79 through Mixed Bed 47W811-1 Demineralizers A and B and Cation
[
47W819-1 Bed Demineralizer to 62-1075 (in retum line to Reactor Coolant Filter).
From LCV-62-118 (and various other inputs) through Holdup Tanks A and B, Holdup tank Recirculation Pump and Gas Stripper Pumps A, B and C to 62-926A.
63 47W811-1 2
Ssitty injection system piping and Functional Functional Code Case components as described below:
N-498 High head saftey injectionline from hydro test altemative FCV-63-39 and FCV-63-40 to RCS Class 1/2 boundary valve 62-581.
i From FCV-63-5, FCV-63-6 and FCV-63-7 and FCV-63-11 through Safety Injection Pumps A-A and B-B (including miniflow to FCV-63-3) to RCS Class 1/2 boundary valves63-543,63-545,63-547,63-549,63-553 and 63-555.
Co!d Leg Accumulators 1 through 4 to J
RCS Class 1/2 boundary valves 63 622,62-623,63-624 and 63-625.
i Low head safety injection lines (RHR)
INSIDE containment including s
containment sump and RHR retum lines.
g.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE35 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 ATTACHMENT 2 PRESSURE TEST SCHEDULE P', S DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS
~
1st 2nd 3rd PERIOD PERIOD PERIOD 63 47W811 1 2
Safety injection system piping and inservice Inservice Code Case 47W812-1 components as described below:
N-498 Refueling Water Storage Tank and hydro test 47W830-1 attemative 47W855-1 piping to first normally closed valve (i.e., HCV-74-34) and CVCS, SIS, RHR, and CS pump suction isolation valves LCV-62-135, FCV-62-136, FCV-63-5, FCV-63-1, FCV-72-21 and FCV-72-22.
67 47W832-3 2 and 3 Essential Raw Cooling Water system inservice Inservice Code Case 47W845-1 piping and components as described below N-498 47W845-2 (Class 2 only at containment penetrations):
(Class 2) or ERCW Screen Wash Pumps A-A, B-8, N-498-1 47W845-3 47W845-4 C-B and D-A to associated traveling (Class 3) hydro test 47W845-5 screens.
j 47W845-6 attemative ERCW Pumps J-A, K-A, Q-A and R-A 47W860-1 through Train A supply header, associated heat exchangers (except Containment Spray Hx), coolers, Train A discharge header to FCV-67-364.
ERCW Pumps L-8, M-8, N-B and P-B through Train B supply header, associated heat exchangers (except Containment Spray Hx), coolers, Train l
8 discharge header to FCV-67-365.
67 47W845-2 3
Essential Raw Cooling Water system Functional Functional Code Case piping and components as described N-498-1 below:
hydro test attemative Containment Spray Heat Exhangers A and B.
Normally closed ERCW supply to MDAFW Pumps A-A (FCV-3-116A to FCV-3-1168) and B-B (FCV-3-126A to FCV-3-126B).
Normally closed ERCW supply to TDAPN Pump A-S (FCV-3-136A to FCV-3-136B and FCV-3-179A to FCV-3-179B).
g.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 36 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REVI ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 68 47W813-1 1
Reactor Coolant system piping and Leakage Leakage Let.kage 47W809-1 components as described below:
every RFO every RFO every RFO and 47W810-1 All Class 1 piping and components.
47W811 1 Code Case 47W859-2 N-498 hydro test attemative 70 47W859-4 2
Component Cooling system piping and inservice Inservice Code Case components as described below):
N-498 From FCV-70-143 through Excess hydro test Letdown Hx to FCV-70-85.
attemative 70 47W859-1 2 and 3 Component Cooling system piping and inservice Code Case Inservice 47W859-2 components as described below (Class 2 N-498 47W859-3 only at containment penetrations):
(Class 2) or N-498-1 47W859-4 CCS Pumps A-A and B-B through Train A supply header, associated heat (Class 3) exchangers (except Excess Letdown hydro test alternative Hx), coolers, Surge Tannk, Thermal Barrier Booster Pumps and Train A retum header to CCS pumps.
CCS Purro C-S through Train B supply hea jer, associated heat exchangers, coolers, Surge Tannk and Train B retum header to CCS pumps.
70 47W859-1 3
Component Cooling system piping and Functional Code Case Functional components as described below:
N-498-1 Piping between normally closed valve hydro test attemative pairs on the CCS pump discharge header and CCS heat exchanger discharge header.
72 47W812-1 2
Containment Spray system piping and Not Not Hydrostatic components as described below:
Required Required (unimpaired fl0W Containment Spray ring headers from FCV-72-39 and FCV-72-2 to spray method) nozzles and RHR Spray ring headers from FCV-72-41 and FCV-72-40 to spray nozzles.
go TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 37 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV 1 ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 72 47W812-1 2
Containment Spray system piping and Code Case Functional Functional components as described below:
N-498 From FCV-72-22 and FCV-72-23 hydro test through CS Pump A-A and CS Heat attemative Exchanger A A to FCV-72-39 and 72-502.
From FCV-72-20 and FCV-72-21 through CS Pump B-B and CS Heat Exchanger B-B to FCV 72-2 and 72-504.
74 47W810-1 2
Residual Heat Removal system piping and Not Not Hydrostatic 47W811-1 components as described below:
Required Required (visual Containment sump including piping unimpaired fl0W and components to first isolation valve FCV-63-72 and FCV-63-73.
method) 74 47W810-1 2
Residual Heat Removal system piping and Code Case Functional Functional 47W811-1 components as described below:
N-498 From FCV-63-1, FCV-63-72 FCV-63 hydro test 47W812-1 73, FCV-72-20, FCV-72-23 and FCV.
attemative 74-21 through RHR Pump A-A and RHR Heat Exchanger A-A to HCV-74 34, FCV 74-28, FCV-72-40, FCV-63-8 hot leg injection line containment penetration and cold leg injection lines i
containment penetrations.
From FCV-74-24 through RHR Pump B-B and RHR Heat Exchanger B-B to FCV-74-28, FCV-72-41 and FCV 11.
Normally isolated piping in the heat exchanger bypass line from HCV 34 to HCV-74-36 and HCV-74-37.
Normally isolated piping in the RHR letdown line from 74-530 and 74-531 to FCV-62-83.
77 47W809-7 2
Waste Disposal system piping and Code Case Code Case Code Case 47W830-1 components as described below:
N-522 N-522 App.
N-522 App.
~
Portion of system penetrating App. J test J test J test containment from FCV-77-9 to FCV.
attemative attemative attemative 77-10 and 84-512.
--. o
'y 5
~
l l
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE38 ASME SYSTEM PRESSURE TESTING PROGRAM BASIS DOCUMENT REV1 4
ATTACHMENT 2 PRESSURE TEST SCHEDULE SYS DRAWING ASME BOUNDARY TYPE OF PRESSURE TEST TEM CLASS 1st 2nd 3rd PERIOD PERIOD PERIOD 77 47W851-1 2
Floor and Equipment Drains systerr piping Code Case Code Case Code Case and components as described below.
N-522 App.
N-522 App.
N-522 App.
Portion of system penetrating J test J test J test containment from FCV-77-127 to FCV.
altemative attemative attemative 77-128.
77 47W851-1 3
Floor and Equipment Drains system piping Unimpaired Unimpaired Unimpaired and components as described below:
Flow Test Flow Test Flow Test From Elevation 693' drain through the Crane Wall.
78 47W855-1 3
Spent Fuel Pool Cooling system piping inservice Inservice Code Case and components as described below:
N-498-1 From Spent Fuel Pool sut.Jon strainers hydro test attemative through Spent Fuel Pit Pumps, Spent Fuel Pit Heat Exchangers and Demineralizer to Spent Fuel Pit discharge diffuser, 78 47W855-1 2
Spent Fuel Pool Cooling system piping Code Case Code Case Code Case and components as described below:
N-522 App.
N-522 App.
N-522 App.
J test J test J test Portion of system penetrating containment from 78-557 to 78-558.
attemative attemative attemative Portion of system penetrating containment from 78-560 to 78-561.
81 47W819-1 2
Primary Water system piping and Code Case Code Case Code Case components as described below:
N-522 App.
N-522 App. N-522 App.
.I test J test J test Portion of system penetrating containment from FCV-81-12 to 81-attemative altemative attemative 502.
43 47W881-5 2
Containment Penetrations X-93 and X-103.
Code Case Code Case Code Case N-522 App.
N-522 App.
N-522 App.
47W881-6 J tem J test J ted attemative attemative attemative J