ML19221B082
| ML19221B082 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-05.2.4, NUREG-75-87, NUREG-75-87-5.2.4, SRP-05.02.04, SRP-5.02.04, NUDOCS 7907120388 | |
| Download: ML19221B082 (6) | |
Text
NU REG-75/087
.fpa nrog%s U.S. NUCLEAR REGULATORY COMMISSION 3'
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STANDARD REVIEW PLAN
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OFFICE OF NUCLEAR REACTOR REGULATION SECTION 5.2.4 REACTOR COOLANT PRESSURE BOUNCARY INSFRVICE INSPECTION AND TESTING REVIEW RESPONSIBILITIES Primary - Materials Engineering Branch (MTEB)
Secondary - None I.
AREAS OF REVIEW General Design Criterion 32, " Inspection of Reactor Coolant Pressure Boundary," requires that components which are part of the reactor coolant pressure boundary (RCPB) shall be designed to pemit periodic inspecCon and testing of important areas and features to assess their structural and leaktight integrity. The following areas relating to the in-service inspection program f or AEC Quality Group A components of the RCFB are reviewed.
These components are also ASME Boiler and Pressure Vessel Code (hereaf ter "the Code"),
Section III, Code Class I components. Inservice inspection programs are based on Section XI of the Code, " Rules for Inservice Inspection of Nuclear Power Components."
1.
System Boundary Subject to Inspection The inservice inspection (ISI) program for tho. pcrtions of the reactor coolant pressure boundary consisting of Code Class I components is reviewed. Steam gene-ator inservice inspection is covered separately in Standard Review Plan 5.4.2.2,
" Steam Generator Inservice Inspection." Augmented inservice inspection for high energy fluid system piping between containnent isolation valves is reviewed in Standard Review Plan 6.6.
2.
Accessibility The descriptive irifmtion that pertains to the general and specific provisions for access to corponents covered by the Code,Section XI, is reviewed. In addition, the renote access equipment needed to perfom inspections in a radiation field is reviewed.
3.
Examination Techniques and Procedures Ine descriptive information that pertains to Section XI, Tabl, s IWB-2500 and IWB-2600 is reviewed.
4.
Inspection Intervals The schedules of exam: nations and insptctions in the applicant's safety analysis report (SAR) and plant Technical Specifications are reviewed. In addition, those inspections USNRC STAND ARD REVIEW PLAN
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which are performed during the inspection interval, such as during refueling outages, are reviewed.
5.
Examination Categories and Requirenents The Technical Specification tabulation of examination categories is reviewed. The SAR areas of review include category designation and the area and extent of examina-tion of each category.
6.
Evaluation of Ervination Results a.
The proposet evaluation methods for any indications of structural defects detected du ing ISI examinations are reviewed.
b.
The repair procedures proposed for components that reveal unacceptable structural defects during ISI examinations are reviewed.
7.
System Leakage and Hydrostatic Pressure Tests The descriptive information on leak tests and hydrostatic pressure tests of Code Class 1 components is reviewed.
II.
ACCEPTANCE CRITERIA The acceptance criteria for the areas of review described in Section I are as follows:
1.
System Boundary Subject to Inspection The applicant's definition of the RCPB is acceptable if in agreement with the following criteria: For pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power sys'. ems, the inspection requirements of Section XI of the Code must be met /or all Class 1 pressure-cortaining components (and their supports) except for those components excluded under IWB-1220 of Section XI.
The system boundary includes all pressure vessels, piping, pumps, and valves which are part of the reactor coolant system, or connected to the reactor coolant system, up to and including:
The outennost containment isolation valve in system piping that penetrates the a.
primary reactor containment.
c.
The second of two valves normally closed during normal reactor operation ir, system piping that does not penetrate primary reactor containment.
c.
The reactor Coolant system safety and relief valves.
2.
Accessibility The design and arrangement of systen components are acceptable if in accordance with IWA-1500. " Accessibility," of Section XI.
Adecgate clearances for general access arc demonstrated as follows:
Sufficient space is provided for personnel and equipment to perform inspections.
a.
b.
Provisions are made for the removal ard storage of structural members, shielding components, and insulating materials, to permit access to the components being inspected.
c.
Provisions are made for hoists and other handling machinery needed to handle items in b, above.
d.
Provisions are made for alternative examinations in the event structural defects or indications reveal tnat such alternative examinations are required.
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e.
Provisions are made for the necessary operations associated with repair or replace-ment of system components and piping.
9 3.
Examination Techniques and Procedures The applicant's examir.ation techniques and procedures used for ISI of the system are ccceptable if in agreement with the following criteria:
a.
The visual examination techniques are acceptable if in agreement with IWA-2210 of Section XI of the Code. A visual examination must be employed as a basis for a report of the general condition of the part, component, or surface. The report must include such conditions as scratches, wear, cracks, corrosion or erosion of the surfaces, misalignment or movement of the part or component, and evidence of leaking. Surface replication methods are considered acceptable provided the sur-face resolution is at least equivalent to that obtainable by visual observation.
b.
The surface examination techniques are acceptable if in agreement with IWA-2220 of Section XI of the Code. A surface examination is required to verify the presence of surface or near surface cracks or discontinaities. The surfuce must not be immersed or flooded with water at the time of examination. Acceptable techniques are magnetic particle examination and liquid penetrant examination.
c.
The volumetric examination methods are acceptable if in agreenent with IWA-2230 of Section XI of tne Code. A volumetric examinatinn is required to indicate the presence of subsurface discontinuities with a method or technique capable of examining the entire volume of metal beneath the surface. Specific acceptable methods of volumetric examinat i:n are radiog aphic examination and ultrasonic examination.
d.
Alternative examination.nethods to those given above in a, b, and c, are acceptable provided the results are equivalent or superior. The acceptance standards for these alternative methods are given in Section XI, IWB-3100,
" Evaluation of Nondestructive Examination Results."
4 Inspection Intervals The inservice inspection program is acceptable if tte required examinations and pressure tests are completed during each tm-war interval cf service, hereafter designated as the inspection interval. In addition, the scheduling of the program must comply with the provisions of IWA-2400, " Inspection Intervals," of Section XI of the Code.
It is inte..ded that inservice exaninations be performed durinq normal plant outages such as refueling shutdowns or maintenance shutdowns occurring during the inspection interval. Except as specified in Table IWB-2500, " Examination Categories," at least 25; of the required examinations must be completed by the expiration of one-third of the inspection interval. Credit is allowed for no mnre than 33-l/3% of the re-quired ISI even though additional examinations a e completed during this period.
At least 50% of the required examination must le completed by the expiration of the second one-third of the inspection interval. Credit is allowed for no more than 66-2/3% of the required inspections. The remaining required examinations shall be completed by the end of the inspection interval.
5.2.4-3 147 082
5.
Examination Categories and Requirements The examination categories and requiraments as specified in the SAR are acceptable if in agreement with the criteria of IWB-2500 and IWB-2600 of Section XI of the Code.
Every area subject to examination falls within one or more of the examination cate-gories indicated in Table IWB-2500 and must be examined at least to the extent specified. The method of examination for the components and parts of the pressure-containing and pressure-retaining boundaries that are listed in the requirements of IWB-2600 of Section XI are tabulated in Table IWB-2600.
6.
Evaluation of Examination Results d.
The standards for examination evaluation are acceptable if in agreement with the requirements of Section XI, IWB-3000, " Standards for Examination Evaluatie-The applicant's program for flaw evaluation is acceptable if it agrees with Table IWB-3410. " Evaluation Standards."
b.
The prcpose d program regarding repairs of unacceptable indications or replace-ment of components containing unacceptable indications is accytable if in agreement with tr.e requirements of Secticn XI, IWB-4000, " Repair Procedures."
The criteria thut establish the need for repair or replacement are described in Section XI, IWB-3000.
7.
Sys_ tem Leakage and Hydrostatic Pressure Tests s
The pressure-retaining Code Class 1 component leakage and hydrostatic pressure test program is acceptable if the program agrees with the requirements of Section XI, IWB-5000, " System Leakage and Hydrostatic Pressura Tests."
IWB-5222, " System Hydrostatic Test Pressure," presents criteria and a table of equivalent test tempera-tures versus test pressures at which the system must be tested. The applicant's pro-gram is acceptable if in agreement with IWB-5222 in regard to the temperature-pressure relationship of the system at test, and if in agreement with the Technical Specifica-tion requirements for operating limitations during heatup, cooldown, and system hydrostatic pressure testing. In some cases, these limitations may be more severe than IWB-5222.
III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case.
1.
System Boundary Subject to Inspection The information furnished in the SAR is reviewed for agreement with Section 11.1 of this plan, and to verify that any differences between the applicant's definition of the RCPB and Section II.1 are identified and justified by the applicant, e.g.,
" Pressurizer: not applicable, as plant is a BWR." or, "no longitudinal welds in beltline region as vessel is constructed of forged rings."
2.
Accessibility The descriptive infonr.ation concerning accessibil.ty furnished in the SAR is reviewed for compliance with Section II.2.
The reviewer verifies that the clearances supplied 147 083 5.2.4-4
for general access to the system coupenent listed 'n Table IWB-2500 of Section XI are adequate.
The.eviewer verifies that adequate p:ovisions are made for remote inspection of those components affected Ly radiation fields af ter plant start-up. These components in-clude the beltline welds and reactor vessel nozzle interior surfaces. The reviewer verifies that remote inspection devices proposed for periodic inservice inspections will be used for the preservice baseline inspection program to demonstrate feasibility.
3.
Examination Techniques and Procedures The reviewer verifies that the examination techniques described by the applicant are the same as those in Section 11.3.
If alternative examination methods are proposed by the applicant, they are reviewed to verify that the results are equivalent or superior to those in IWA-2CC, 2220, and 2230 of Section XI, and that the acceptance standards of IWB-3100 of Section XI are met.
4.
Inspection Intervals The Technical Specification program for inservice inspection is reviewed to establish that the inspaction schedule for every area and component in the program is in agree-rrent with Section 11.4.
5.
Examinatior. Categories anj Requirements The descriptive information in the SAR and the Technical Specification ISI program are reviewed to establish that the applicant followed the requirements of Section 11.5.
The reviewer determines that the table supplied in the Technical Spec' icatiers follows Table IWB-2600 of Section XI where it is applicable to the given ree: tor system, and that the table contains the followilg headings and applicable information:
Examination Category, Components and Parts ta b2 Examined, Method, Cxtent and Frequency of Examinations, and Corrents.
6.
Evaluation of Exan: nation Results The criteria statemei ts provided by the applicant are reviewed for agreement with Section II.6 as follcas:
a.
The reviewer verifies that the applicant's criteria incorporate IWB-3000 of See +'on XI regarding standards for examination evaluation.
b.
The reviewer verifies that the applie's criteria incorporate IWd-4000 of Sec; ion XI regarding repair procedures.
7.
System Leakage and Hydrostatic Pressure Tests The reviewer determines that the Technical Specification on hydrostatic pressure test-ing for system leakage of the RCPB adheres to Section II.7 of this plan and incorporates the table in IWB-522,Section XI.
The Technical Specification on operating limitations during heatup, cooldown, and systen hydrostatic pressure testing must be referenced.
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IV.
EVALUATION FINDINGS The reviewer verifies that adequate infomation is provided in accordance with the require-rents of this review plan, and that his evaluation supports conclusions of the following type, to be included in the staf f's sa fety evaluation report:
"To ensure that no deleterious defects develop during service, selected welds and s, eld heat-affected zunes will be inspected periodically. The applicant has stated that the designs of Code Class I conponents of the reactor coolant pressure boundary incorporate provisions for access fer inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, and that methods will be developed to facilitate the remote inspection of those areas of the reactor vessel not readily accessible to inspection personnel. The conduct of periodic inspections and leakage and hydrostatic testing of pressure-retaining corponents of the reactor coolant pressure boundary in accordance with the requirements of Section XI of the ASME Code provides reasonable assurance that evidence of structural degradation or loss of leaktight-integrity occurring during service will be detected in tir.e to permit corrective action tefore the safety function of a corponent is corpromised.
Comoliance with the inservice inspections required by this Code constitutes an 3cceptable basis for satisfying the requirements of General Design Criterion 32."
V.
REFERENCES 1.
10 CFR Part 50, Appendix A, General Design Criterien 32, " Inspection of Peactor Coolant Pressure Boundary.'
2.
ASME Boiler and Pressure Vessel Code,Section XI, Section III, " Nuclear Power Plant Components," and " Rules for Inservice Inspection of Nuclear Power Plant Corponents,"
Division 1, " Rules for Inspection and Testing of Cocpenents of Light-Water Cooled Plants," Anerican Society of Mechanical Fngineers.
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