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Category:TEXT-SAFETY REPORT
MONTHYEARML20216G0111999-09-30030 September 1999 Year 2000 Readiness in U.S. Nuclear Power Plants ML20206N2191999-04-30030 April 1999 Operator Licensing Examination Standards for Power Reactors ML20205A5291999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1998.(White Book) ML20211K2851999-03-31031 March 1999 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance ML20205A5991999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1998.(White Book) ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML20203D0541999-01-31031 January 1999 Fire Barrier Penetration Seals in Nuclear Power Plants ML20155A9281998-10-31031 October 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1998.(White Book) ML20154C2081998-09-30030 September 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1998.(White Book) ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20203A1521998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20153D3371998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20236S9771998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Pressurized Water Reactors ML20236S9681998-06-30030 June 1998 Evaluation of AP600 Containment THERMAL-HYDRAULIC Performance ML20236S9591998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Boiling Water Reactors ML20217Q7971998-05-0404 May 1998 Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively ML20247E3951998-04-30030 April 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1997.(White Book) ML20217F3801998-03-31031 March 1998 Risk Assessment of Severe ACCIDENT-INDUCED Steam Generator Tube Rupture ML20202J3051997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1997.(White Book) ML20197B0431997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1997.(White Book) ML20211L2931997-09-30030 September 1997 Aging Management of Nuclear Power Plant Containments for License Renewal ML20210K7801997-08-31031 August 1997 Topical Report Review Status ML20149G9431997-07-31031 July 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1997.(White Book) ML20210R2131997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the System 80+ Design.Docket No. 52-002.(Asea Brown Boveri-Combustion Engineering) ML20140F0801997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design.Supplement No. 1.Docket No. 52-001.(General Electric Nuclear Energy) ML20140J4301997-05-31031 May 1997 Safety Evaluation Report Related to the Department of Energy'S Proposal for the Irradiation of Lead Test Assemblies Containing TRITIUM-PRODUCING Burnable Absorber Rods in Commercial LIGHT-WATER Reactors ML20141J9391997-04-30030 April 1997 Safety Evaluation Report Related to the Renewal of the Operating License for the Research Reactor at North Carolina State University ML20141C2411997-04-30030 April 1997 Circumferential Cracking of Steam Generator Tubes ML20141A5791997-04-30030 April 1997 Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 (Changes, Tests, or Experiments).Draft Report for Comment ML20137A2191997-03-31031 March 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1996.(White Book) ML20134L3601997-01-31031 January 1997 Standard Review Plan on Antitrust.Draft Report for Comment ML20134L3631997-01-31031 January 1997 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance.Draft Report for Comment ML20138J2461997-01-31031 January 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1996.(White Book) ML20135D5711997-01-31031 January 1997 Operator Licensing Examination Standards for Power Reactors ML20133E9161996-12-31031 December 1996 License Renewal Demonstration Program: NRC Observations and Lessons Learned ML20149L8261996-10-31031 October 1996 Reactor Pressure Vessel Status Report ML20135A4981996-10-31031 October 1996 Historical Data Summary of the Systematic Assessment of Licensee Performance ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20128Q0761994-11-0404 November 1994 Coordinating Group Evaluation,Conclusions & Recommendations ML20149H0671994-11-0404 November 1994 Safety Evaluation Supporting Amend 27 to Amended License R-103 ML20149G4281994-09-28028 September 1994 NRC Perspectives on Accident Mgt, Presented at 940928 Severe Accident Mgt Implementation Workshop in Alexandria, VA ML20149F7581994-08-25025 August 1994 Topical Rept Evaluation of WCAP-13864,Rev 1, Rod Control Sys Evaluation Program ML20149F4151994-08-0404 August 1994 Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:TOPICAL REPORT EVALUATION
MONTHYEARML20149F7581994-08-25025 August 1994 Topical Rept Evaluation of WCAP-13864,Rev 1, Rod Control Sys Evaluation Program ML20059L1061994-01-12012 January 1994 Draft Topical Rept Evaluation of B&Wog Rept 47-1223141-00, Integrated Plant Assessment Sys/Structure Screening.... Applicant for License Renewal That Refs B&Wog Sys Screening Methodology Will Be Required to Develop Own Procedures ML20059D1911993-12-30030 December 1993 Topical Rept Evaluation of RXE-91-005, Methodology for Reactor Core Response to Steamline Break Events ML20058P2181993-12-10010 December 1993 SER Accepting Siemens Nuclear Power Corp Submittal of Topical Rept EMF-92-081, Statistical Setpoint/Transient Methodology for W Type Reactors ML20058H9851993-11-26026 November 1993 Topical Rept Evaluation of WCAP-10216-P, Relaxation of Constant Axial Offset Control. Rept Acceptable ML20059H8481993-11-0202 November 1993 SER Accepting Proposed Changes in Rev 3 to OPPD-NA-8302-P, OPPD Nuclear Analysis,Reload Core Analysis Methodology, Neutronics Design Methods & Verification ML20134B4761993-10-30030 October 1993 Topical Rept Evaluation of Rev 3 to NP-2511-CCM Re VIPRE-01 Mod 2 for PWR & BWR Applications ML20058M9851993-09-30030 September 1993 SE of Topical Rept, Transient Analysis Methodology for Wolf Creek Generating Station ML20056G4171993-08-18018 August 1993 Topical Rept Evaluation of Rev 4 to OPPD-NA-8303, Transient & Accident Methods & Verification. Proposed Changes in Rev 4 Acceptable Except for Use of Cents Computer Code for Transient Analyses ML20056E9661993-08-0606 August 1993 Sser Re Topical Rept HGN-112-NP, Generic Hydrogen Control Info for BWR/6 Mark III Containment Hydrogen Control ML20056E3811993-08-0505 August 1993 Safety Evaluation of RXE-89-002, Vipre-01 Core Thermal- Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications. Rept Is Acceptable for Ref in CPSES Core thermal-hydraulic Analyses ML20056E3961993-08-0505 August 1993 Safety Evaluation of RXE-90-006-P, Power Distribution Control Analysis & Overtemperature N-16 & Overpower N-16 Trip Setpoint Methodology. Methodology Acceptable ML20056E4681993-08-0505 August 1993 Supplemental Safety Evaluation for Topical Rept HGN-112-NP, Generic Hydrogen Control Info for BWR/6 Mark III Containments. Change Requests Consistent & Compatible W/ 10CF50.44 & Acceptable ML20056E2571993-08-0505 August 1993 Corrected Safety Evaluation for Topical Rept RXE-91-001, Transient Analysis Methods for Commanche Peak Steam Electric Station Licensing Applications. Corrections Made to Second Sentense of Second Full Paragraph on Page Two ML20056D9921993-07-29029 July 1993 Topical Rept Evaluation of OPPD-NA-8301,Rev 5, Reload Core Analysis Methodology Overview. Proposed Changes in Rev 5 Acceptable ML20057A2661993-07-14014 July 1993 Topical Safety Evaluation of CEN-387-P, Pressurizer Surge Line Flow Stratification Evaluation. C-E Owners Group Analysis May Be Used as Basis for Licensees to Update plant- Specific Code Stress Rept for Compliance W/Bulletin 88-011 ML20056E1261993-06-29029 June 1993 Safety Evaluation of CENPD-382-P, Methodology for Core Designs Containing Erbium Burnable Absorbers. Rept Acceptable for Reload Licensing Applications of Both CE CE 14x14 & 16x16 PWR Lattice Type Core Designs ML20057B5431993-06-26026 June 1993 Errata for Sser Re Topical Rept HGN-112-NP, Generic Hydrogen Control Info for BWR/6 Mark III Containments, for Use in Issuance of Final Approved Version of Topical Rept ML20128B8101993-01-19019 January 1993 Safety Evaluation Accepting Methodology Described in Topical Rept RXE-91-002 Reactivity Anomaly Events Methodology for Reload Licensing Analyses for CPSES ML20126E0381992-12-0909 December 1992 Safety Evaluation Accepting Topical Rept NEDC-31753P W/Ter Recommendations W/Listed Exceptions ML20056D9351991-01-11011 January 1991 Topical Rept Evaluation Accepting Proposed Methodology for Fuel Channel Bowing Anaylses & for Referencing in Reload Licensing Applications W/Listed Conditions ML20235Q7121989-02-22022 February 1989 Safety Evaluation Re Review of WCAP-10271,Suppl 2 & WCAP-10271,Suppl 2,Rev 1 on Evaluation of Surveillance Frequencies & out-of-svc Times for ESFAS ML20206L9611988-11-23023 November 1988 Topical Rept Evaluation of PECO-FMS-0004, Methods for Performing BWR Sys Transient Analysis. Rept Approved,But Limited to Util Competence to Use Retran Computer Code for Facility ML20205M0091988-10-25025 October 1988 Safety Evaluation of Topical Rept YAEC-1300P, RELAP5YA: Computer Program for LWR Sys Thermal-Hydraulic Analysis. Program Acceptable as Licensing Method for Small Break LOCA Analysis Under Conditions Stipulated ML20204G8371988-10-18018 October 1988 Safety Evaluation Accepting Topical Rept 151, Haddem Neck Plant Non-LOCA Transient Analysis, Except for Issue of Feedwater Event ML20155G7991988-10-12012 October 1988 Topical Rept Evaluation of TR-045, BWR-2 Transient Analysis Using Retran Code. Methods Described in Rept Acceptable for Reload Analysis When Listed Conditions Satisfied ML20155G3201988-09-26026 September 1988 Safety Evaluation of TS NEDC-30936P, BWR Owners Group TSs Improvement Methodology. GE Analyses Demonstrated Acceptability of General Methodology for Considering TS Changes to ECCS Instrumentation Used in BWR Facilities ML20155B0501988-09-22022 September 1988 Topical Rept Evaluation of Suppl 1 to NEDC-30851P, Tech Spec Improvement Analysis for BWR Control Rod Block Instrumentation. Analyses Acceptable to Support Proposed Extensions to 3 Months ML20151K9921988-07-26026 July 1988 Topical Rept Evaluation of Nusco 140-1 Northeast Utils Thermal Hydraulic Model Qualification,Vol 1 (Retran). Rept May Be Generally Ref in Future Licensing Submittals.Further Justification by Util Required ML20150D9651988-03-21021 March 1988 Topical Rept Evaluation of Rev 0 to TR-040, Steady State & Quasi-Steady State Methods for Analyzing Accidents & Transients. Util Methods Acceptable for Performing Reload Assembly Mislocation Analysis W/Listed Exceptions ML20150D7671988-03-21021 March 1988 Topical Rept Evaluation of Rev 0 to TR-033, Methods for Generation of Core Genetics Data for RETRAN-02. Uncertainties in Input Parameters & Impact on Retran Results Should Be Determined for Qualification of Model ML20236D2621987-10-21021 October 1987 Topical Rept Evaluation of CEN-348(B)-P, Extended Statistical Combination of Uncertainties. Rept Acceptable ML20235D7041987-09-22022 September 1987 Safety Evaluation of Rev 0 to Topical Rept TR-021, Methods for Analysis of BWRs Steady State Physics. Rept,Methodology & Util Use of Methodology Acceptable ML20239A5461987-09-0909 September 1987 Safety Evaluation Supporting A-85-11, Retran Computer Code Reactor Sys Transient Analysis Model Qualification for Use in Performing plant-specific best-estimate Transient Analyses at Plant ML20215M3591987-05-0606 May 1987 Safety Evaluation Supporting Util Use of Suppl 1 to MSS-NA1-P, Qualification of Reactor Physics Methods for Application to PWRs of Middle South Utils Sys ML20212M7781987-02-17017 February 1987 Topical Rept Evaluation of WCAP-10325, Westinghouse LOCA Mass & Energy Release Model for Containment Design - Mar 1979 Version. Rept Acceptable for Ref in Licensing Actions ML20210N7331987-02-0404 February 1987 Safety Evaluation Supporting CEN-161(B)-P,Suppl 1-P, Improvements to Fuel Evaluation Model. Mods to Fission Gas Release & Fuel Thermal Expansion Models Acceptable ML20215B2331986-12-0404 December 1986 Corrected Page 1 to 861031 Topical Rept Evaluation of Rev 2 to STD-R-05-011, Mobile In-Container Dewatering & Solidification Sys (Mdss). Word Effective Inserted Before Words Pore Sizes in First Line of 4th Paragraph ML20214C5221986-11-14014 November 1986 Topical Rept Evaluation of Rev 0 to TR 020, Methods for Analysis of BWR Lattice Physics. Collision Probability Module Code Acceptable for BWR Fuel Lattice Calculations ML20213F6531986-11-10010 November 1986 Safety Evaluation of Rev 2 to Vol 3 of XN-NF-80-19(P), Exxon Nuclear Methodology for Bwrs,Thermex:Thermal Limits Methodology Summary Description. Rept Acceptable for Ref in Licensing Applications ML20207A8281986-11-0505 November 1986 Suppl 3 to Topical Rept Evaluation Re Submittal 2 to Rev 3 to CEN-152, C-E Emergency Procedure Guidelines. Rept Acceptable for Ref ML20215N6901986-11-0404 November 1986 Topical Rept Evaluation of BAW-10155, FOAM2 - Computer Program to Calculate Core Swell Level & Mass Flow Rate During Small-Break Loca. Rept Acceptable W/Listed Restrictions Re Ranges of Core Flow Rate & Pressure ML20215N3921986-10-31031 October 1986 Topical Rept Evaluation of STD-R-05-011, Mobile In-Container Dewatering & Solidification Sys (Mdss). Rept Acceptable for Ref in License Applications ML20211D6921986-10-16016 October 1986 Safety Evaluation of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification,Vol II (Vipre). Rept Acceptable for Establishing Input Values & Selection of Correlation Options & Solution Techniques for Calculations ML20206S6511986-09-15015 September 1986 Topical Rept Evaluation of Addenda 3 to WCAP-8720, Improved Analytical Models Used in Westinghouse Fuel Rod Design Computations/Application for BWR Fuel Analysis. Rept Acceptable for Ref in Licensing Applications ML20212N2001986-07-23023 July 1986 Topical Rept Evaluation of Rev 1 to XN-NF-85-67 (P), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel. Rept Acceptable as Ref for Application to Jet Pump BWR Reload Cores,W/Listed Conditions 1994-08-25
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
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d TOPICAL REPORT EVALUATION INSTRUMENTED INSPECTION TECHNIQUE AS AN ALTERNATIVE TO THE HYOR0 STATIC TESTING ..
REQUIREMENTS FOR ASME CLASS 1, 2, AND 3 -
- SYSTEMS AND COMPONENTS -
SUBMITTED BY H.A.F.A. INTERNATIONAL INCORPORATED L -
! TOPICAL REPORT HAFA 135 (N)
APRIL 1985 4
1.0 BACKGROUND
Pressure tests of nuclear power' plant systems and components are
_ performed primarily to determine their preoperational and continued 3 _ inservice structural integrity and leak tightness. 10 CFR 50.55a i states in part that pressure tests of systems and components of boiling 4
]- .
and pressurized water-cooled nuclear power facilities shall be performed in accordance with the requirements of Section XI of the ASME Boiler and j -
, Pressure Vessel Code. The owners of the facilities are required to up'date
- the testing programs to later approved editions and addenda of Section XI l at ten year intervals and, in many instances, compliance with the newer
) requ,irements is impractical because of the existing system or component j design. In such cases, the Regulation allows relief to be granted by ,the
) --
Comm'ission if the necessary findings can be made. The Regulation also
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' allows' proposed alternatives to the requirements to be used when authof-f , ized by the Director of the Office of Nuclear Reactor Regulation if the
!i alternatives would provide an acceptable level of quality and safety or
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compliance with the specified requirements would result in hardship or 1
, _ unusual difficulties without a compensating increase in the level of l _ quality and safety. !
i ,
i As an alternative method for pressure testing systems and components, i H.A.F.A. Int'.ornational Incorporated submitted to the staff for review l the topical report, " Instrumented Inspection Technique as en alternative l f to the Hydrostatic Testing Requirements for ASME Class 1., 2, and 3 Systems l and Components." This report is evaluated for applicationfof the alternative l' method to pressure tests required by Section XI.
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! TOPRP ENVHAFA C PDR
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2.0 SCOPE AND S M4ARY OF REVIEW +
The information and data contained in the topical report re presented j to demonstrate that the Instrumented Inspection Technique is capable of j
detecting and locating external system leakage, intersystem valve leakage, reducing personnel exposure to radiation, detecting small leaks, elimi-nating overpressurization of lower pressure rated piping and components, and is therefore a suitable alternative to Section XI requirements for
)- _
hydrostatic tests. The staff's review considers the Code requirements j_ and the impracticalities associated with implementation of the require-ments, and application of the Instrumented Inspection Technique as an j _~ , alternative. Although the Topical report refers to hydrostatic testing, 1 its intent is to apply to pressure testing in general, i.e., system leakage *
~
f tests, system functional tests, system hydrostatic tests, and system l l pneumatic tests. The staff's review therefore encompasses pressure tests in general.
'8ased on our review and evaluation, we have concluded that sufficient
~ __ . information has been presented to support the conclusion that the
! g _, Instrumented Inspection Technique is a suitable alternative for the -
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f pressure test requirements of Section XI. Application of the alternative j , method provides added assurance of system and component structural integ- ;
j , rity and leak tightness when compared to conventional pressure testing l l~ ,
methods. Implementation of the Instrumented Inspection Technique is not l.
intended to circumvent Section XI Code requirements for pressure tests but !
- to provide an added margin of reliability of the test results. The staff i
- finds that the Code requirements, where practical to meet, will be complied l with and in situations where the requirements are impractical, the regu- l lations will be followed prior to implementation of the alternative testing method. However, the Code requirement for the four-hour hold time prior to visual examination of insulated systems and components may be reduced I
to two hours if the alternative method is utilized.
l l
The remainder of this safety evaluation includes summariehof Section XI Code requirements for pressure tests and the topical report,'and the bases
~ '
for our conclusions.
3.0 CODE REQUIREMENTS The Section XI Code requirements for pressure tests given below are a summary of those from the 1980 Edition through Winter 1981 Addenda.
These requirements are cited for explanatory purposes only and are not cited to limit the alternative testing method to the requirements in
, this edition and addenda.
3.1 SYSTEM TEST REQUIREMENTS The Code requires that pressure retaining components within each system
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boundary be subjected to system pressure tests under which conditions 1
visual examination, VT-2 , is performed. The required system pressure
~ tests are defined as:
aw
,%_ (a) Systems Leakage Test - A pressure test conducted following .
~
opening and reclosing of a component in the system after pressuri-l
- zation to nominal operating pressure.
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(b) System Functional Test - A pressure test conducted to verify operability of systems (or components) not required to operate during normal plant operation while under system operating pressure.
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1 A VT-2 is a visual examination that is conducted to locate evidence of leakage from pressure retaining components or abnonsal leakage from components with or without leakage collection systems as required during conduct of system pressure or functional tests.
] .*
4 (c) System Inservice Test - A pressure test conducted to' perform 1
visual examination VT-2 while the system is in service'urider operating pressure, i
(d) System Hydrostatic Test - A pressure test conducted during a plant shutdown at a pressure above nominal operating pressure or system pressure.for which overpressure protection is provided.
, (e) System Pneumatic Test - A pressure test conducted in lieu of a hydrostatic pressure test.
~
~ ' Pressure and temperature requirements are defined for the type of test-being performed and the system or component Code Class. System ,
boundaries are located at the intersection of Code Class changes and the pressure test hold time depends on whether or not the system or component is insulated.
For Class 1 systans and components, all pressure tests except the hydrp-static test are required to be performed at not less than the nominal i, g , operating pressure associated with 100% rated reactor power. The hydr.o-
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,- static test is required to be performed at not less than 1.10 times the nominal operating pressure at 100*F or less.
However, the pressure can be lowered incrementally with increasing temperature to 1.02 times the operating pressure at a temperature of 500'F provided limiting conditions j
specified in the Technical Specifications are not violated.
For Class 2 systems and components, all pressure tests are required to 4
be perfonned at nominal operating pressure except the hydrostatic test I
pressure is required to be at least 1.10 times the lowest pressure
~
setting of safety or relief valves provided for overpressure protection l l for systems with a design temperature of 200*F (93'C) or less and 1.25 i times this pressure for systems with a design temperature above 200'F (93'C).
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ThesysteminservicetestandsystemfunctionaltestofCkass3 systems are required to be performed at nominal operating press 0rt. 'The' test I pressure requirements for hydrostatic tests are the same aTtho's'e for Class 2 systems, i.e., 1.10 times the lowest setting of safety or i
relief valves provided for overpressure protection for systems with a design temperature of 200'F (93'C) or less and at least 1.25 times this j
! pressure for systems with a design temperature above 200'F. For j systems not provided with safety or relief valves, the system design l l
pressure is required to be used during the hydrostatic test.
l Test temperatura for Class 1, 2 & 3 systems and components constructed ~
of ferritic steel is required to meet the criteria specified for .
- fracture prevention. For systems constructed of austenitic steel, test I temperature limitations are not required to meet fracture prevention ~
criteria. The pressure test hold time is required to be ten (10)
}
minutes for systems that are not insulated and four (4) hours for
{ insulated systems.
1
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The accuracy of test gages used in pressure testing is required to j g __ provide results accurate to within 0.5% of full scale. The test gages-
~
4
_ ,- are required to be calibrated against a standard dead weight tester or a calibrated master gage. The test gages are required to be calibrated
, before each test or series of tests, where a series of tests is a group j~ ,
of tests that use the same pressure test gage or gages and that are '
l conducted within a period not exceeding two (2) weeks.
I
?
! 4.0 SUpttARY OF TOPICAL REPORT The information contained in the topical report included (1) rationale for the alternative testing, (2) a description of the Instrumented ~
i l Inspection Technique, and (3) the results of tests perfome'd on systems 1 l at four facilities. A summary of these aspects is given'below.
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4.1 TESTING RATIONALE I SectionXICoderequirementsforpressuretestsfailtoa5resithe l problem of intersystem leakage or adequately address small external !
leakage since small leakages may not penetrate insulation or appear !
at breaks in the insulation. To implement the requirements of the Code, in many in, stances, involves system preparations which could entail removal of valve internals, blanking safety or relief valves,
_ pin blocking spring hangers, shutting down both units of a two-unit
_ site when testing shared systems, and exposing testing personnel to accumulated doses of radiation which could be lowered in keeping with
_] the aims of ALARA (As Low As Reasonably Achievable). --
The Instrumented Inspection Technique is capable of eliminating or reducing many of the problems associated with implementing the Code requirements for pressure tests while meeting the intent of the Code and addressing problems that are potentially safety significant.
4.2 DESCRIPTION
OF THE INSTRUMENTED INSPECTION TECHNIQUE I L __
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( PROPRIETARY INFORMATION )
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4 4.3 TESTRESULTSOFIITAPPLICATIONONSYSTEMSATSEVENPLAN[S .
( PROPRIETARY INFORMATION )
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. i 5.0 EVALUATION
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5.1 APPLICATION OF IIT AS AN ALTERNATIVE PRESSURE TESTING METHOD The Instrumented Inspection Technique (IIT) is a pressure testing method that is performed in accordance with the rules of Section XI and the Regulation, 10 CFR 50.55a. The equipment employed enables testing personnel to locate leaks faster, detect smaller leaks, and detect intersystem leaks. The IIT is therefore an alternative pressure testing g method that provides superior quality and safety over conventional !
_ testing and is thus an acceptable alternative.
5.2 APPLICATION OF IIT AS AN ALTERNATIVE TO IMPRACTICAL CODE REQUIREMENTS 5.2.1 Test Pressure Requirement
~-
Attaining and holding the Code required test pressures in
=-
portions of Class 1, 2, and 3 systems have been cited in ~
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many instances by a number of licensees to be impractical to perform at their facilities. Supporting information justifying their determinations was provided to the Commission and relief from performing these tests at Code required test pressures was granted after review and evaluation. Sufficient data on small leaks in water-filled systems have been taken and the results analyzed to demonstrate that small leaks can be detected by IIT and that the e.hanges in the leakage rates between normal operating pressures and the Code required 7 pressures are relatively small. Based on the leak detection
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capabilitiesofIIT,thestafffindsthatitsapplicati)n
- in situations where the Code required test pressures .ars - .
impractical to attain and hold, and the tests are perfolwed -
at normal operating pressure, will provide added assurance that small leaks at the lower pressures will be detected.
We therefore find IIT to be an acceptable alternative method to be used for impractical Code test pressure requirements.
5.2.2 Test Hold Time The Code requirement for pressure test hold time of four (4)
~
'._ hours prior to visual examination of insulated systems is based on allowing sufficient time to elapse for a leaking i
fluid to penetrate the insulation and be detected by the -
VT-2 (visual) inspection. Since small leaks can be detected
. __ by IIT, it is not necessary to require the four-hour hold time.
Leakage detected by IIT can be located prior to or after achieving the required pressure. The staff finds that a
~
~
two-hour hold time is adequate for insulated systems prior to -
, the VT-2 inspection when using IIT as the alternative testing .
?- _
. method. I j 3:- .
6.0 CONCLUSION
S AND RECOW4ENDATIONS (1) Based on our review and evaluation of the information and data presented in the topical report, we conclude that the IIT will provide added assurance of the structural integrity and leak tightnessofsystemsandcomponentssubjectedtopressuretests and that the testing method provides an increase in the level of qualityandsafety,andisthereforeanacceptable'a(ternative testing method. -
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(2) Application of IIT where Code requirements are impr ctical to meet also increases the level of quality and safety ~becaus'e of the leak detection capabilities of the method employed.
(3) The four-hour hold time requirement for insulated systems may be reduced to two-hours because of the small leak detection and location capabilities of IIT.
Visual (VT-2) examination of the systems as required by Section XI should be performed after the two-hour hold time.
- w. (4) Prior to implementation of IIT, a system safety and operational review should be performed and testing procedures approved as described in the topical report. Impractical Code requirements -
and supporting information to justify the impracticalities should
^ ~~
be submitted to the Commission for evaluation as required by Regulations.
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