ML19221B008
| ML19221B008 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-06.6, NUREG-75-87, NUREG-75-87-6.6, SRP-06.06-01, SRP-6.06-1, NUDOCS 7907120202 | |
| Download: ML19221B008 (6) | |
Text
NUREG-75/087
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4 U.S. NUCLEAR REGULATORY COMMISSION ier; g 5"f/
STANDARD REVIEW PLAN W*%
OFFICE OF NUCLEM REACTOR REGULATION
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SECTION 6 6 INSERVICE INSPECTIt., uF CLASS 2 AND 3 COMPONENTS REV'EW RESPONSIBILITIES Primary - Materials Engineering Branch (MTEB)
Secondary - Reactor Systems Branch (RSB)
I.
AREAS OF 'itulEW Gener;l Design Criterion 36, " Inspection of Emergency Core Cooling Systen;" Criterion 39, "Irapection of Containment Heat Removal System; ' Criterion 42, " Inspection of Containnent Atmosphere Cleanup Systems;" and Criterion 45, " Inspection of Cooling Water System," of Appendix A to 10 CFR Part 50 require that the subject systems be designed to permit appropriate periodic inspection of important component parts to assure system integrity and capability.
The following areas relating to tu irservice inspection (ISI) program for AEC Quality Group B and C (ASME Boiler and Pressure Vessel Code,Section III, Code Class 2 and 3) con-ponents are reviewed:
1.
Components Subject to Examination The descriptive inferi"ation in the applicant's safety analysis report (SAR) is reviewed to establish that all the ASME Boiler and Dressure Vessel Code (hereaf ter "the Code"),
Section III, Subarticle NA-2140, Class 2 and Class 3 components are included in the ISI program. The Reactor Systems Branch verifias that the systen classifications as Code Class 2 and 3 agree with Subarticle NA-2111 of Section III and with the de-finitions of the general design criteria.
2.
Accessibility The descriptive infarTnation, including dra.vings, is reviewed by the Materials Engineering Branch to establish that the Code Section XI, Subarticle IWA-1500, pr visions for systen accessibility are included in the applicant's layout and design of these systems.
3.
Examination Techniques and Procedures The.vquired examination techniques and procedures, including the requirements of SE irticles IWC-2600 and IWD-2600 of Section XI, are reviewed for their conformance to Subarticle IWA-2200 of Section XI of the Code.
USNRC STANDARD REVIEW PLAN Stendeed somew ptene are prope,ed for the guidance of the Ottice of Nucleet Reector Regutation staff toeponoebe for the rewow of oppketione to construct end opeeste nucteer power plants These documents are made==es6eb8e to the pubuc se part of the Commiesson a pohcv to inform the nucseer 6ndustry and the genersi pubhc of seguietory procedures and potecree Stenderd review piene are not subetetutee for roeutetory guidee or the Comm.coson s eequhettene and comphence wrth them as not required The stenderd review plan sections are hoved to Rev+sion 2 of the Standard 7ormet and Content of Safety Anas eio Repoete v
for Nucteer Power Ptente Not au sectione of the Standard Format have e correspond 6ng review pien Pubhohed etenderJ review P4ene wiM be rev eed periodnesty. no approprieve. to occommodete cornmente end to refioct new informet.on end ooper e
Coenmeries and suggeottone for improvement wtfl be cone *dered and should be sont to the U S Nuclose Requietory Commise*en Omco of Nudeer Reactor Regutet6en Wressington. D C 2Gh5 i /V e i *. V WV @
4.
Inspection Intervals The required examinations and inspections listed in the SAR are reviewed and com-pared to Table IWC-2600 and Subarticle IWD-2600 of Section XI to ferify that they will be performed within the designated inspecti'an interval and conply with sub-articles IWC-2400 and IWD-2400 of Section XI to t ify that they will be performed witnin the designated inspection interval and comply with Subarticles IWC-2400 and IWD-2400 of Section XI.
5.
Examination Categories and Requirenents The technical specifications are compared to Table IWC-2520 and Subarticle IWD-2600 of Section XI to verify that the examination categories and ISI requirements of each ategory are in agreement.
6.
Evaluation of Examination Results The information conce.H% repair praedures is reviewed for compliance with Articles IWC-4000 and IWD-4000 of Section XI.
Because Articles IWC-3000 and IWD-3000 are still in course of preparation, as an interim step, evaluation of examination results for Class 2 and 3 components is reviewed for compliance with Article IWB-3000 for Class I components.
7.
System Pressure Tests The pressure test program is reviewed for compliance with Subarticles IWC-5200 and IWD-5200 of Section XI to establish that leakage arJ signs of structural distress are inspected for on a peric'lic basis. In addition, for Class 2 components, a review is perforred to determine that all applicable systems and cocponents are pressure tested at acceptable combinations of temperature and pressure.
8.
Augmented ISI to Prntect Against Postulated Piping Failures The augmented inservice inspection program to provide assurance against postulated piping failures of high energy fluid systems between containment isolatio,. valves is reviewed.
II. ACCEPTANCE CRITERIA The acceptance criteria for the areas of review described in Section I of this plan are a' follows:
1.
Ccmponents Subject to 'nspection The applicant's definition of Code Class 2 and 3 components and systems subjects to an ISI program is acceptable if in agreement with the definitions of Code Section III, Subarticle NA-2140, and Section XI, Table IWC-2600 and Subarticle IWD-2600. The interpretation of coda classifications by the applicant is subject to review by the Feactor Systems Branch for compliance with safety criteria pertaining to component classificatian. (Refer to M-2110 of Section III.)
2.
Accessibility The design and arrangement of Class 2 and 3 systems are acceptable if the applicant includes allowances for adequate clearances to conduct the examinations specified in IWC-2600 and IWD-2600 at the frequency specified by IWC-2400 and.WD-2400.
Special 148 013 6.6-2
design considerations are given to tnose systems that are intended to be examined during normal reactor operation.
3.
Exaninatin Techniques and Procedures Since acceptance criteria for the required examination techniques and procedures are identical to those for the reactor coolant pressure baundary (RCPB), Standard Review Plan 5.2.4, "RCPB Inservice Inspection and Testing" (Ref. 3),Section II.3,
" Examination Techniques and Procedures," is incorporated by reference in this plan.
4.
Inspection Intervals The inservice inspection pr7 ram schedule given in the SAR is acceptable if the re-quired examinations are completed during each ter -year interval, hereaf ter design-ated as the inspection interval, and as required by Subarticles IWC-2400 and IWD-2400 of Section XI.
5.
Examination Categories ard Requirements The ISI examination categories and requirements for Class 2 and 3 components es-tablished by the SAR are acceptable if in agreement with the following criteria of Section XI: IWC-2520, IWC-2600, and IWD-2600. The areas subject to examination and the extent of examination for the Class 2 components shall comply with the require-ments specified under the examination categories of Table IWC-2520.
6.
Evaluation of Examinations Pesults Articles IWC-3000 and IWD-3000 of Section XI concerning evaluation of examination re-sults are still in preparation. The appliccnt's evaluation of examination results should be consistent with that for Code Class I components. Thus, Standard Reviaw Plan 5.2.4, "RCPB 'nservice Inspectior, and Testing,"Section II.6, " Evaluation of Examination Results," is considered acceptable (Ref. 3).
7.
Systen Pressure Tests The SAR program for Class 2 and 3 system pressure testing is acceptable if it meets the following criteria of IWC-5000 and IWD-5000 of Section XI:
a.
Class 2 Systens (1) The system hydrostatic test pressure shall be at least 1.25 tires the system design pressure (P ) and conducted at a test temperature not less D
than 100*F except as may be required to meet the test temperature require-ments of IWA-5230.
(2) When system hydrostatic testing is required to be conducted at temperatures above 100 F in order to meet the fracture toughness criteria applicable to ferritic materials of which the system components are constructed, the test pressure may be reduced in accordance with the table given in IWC-5220.
(3) For components that are not required to function during reactor operation, the system test pressure shall not be less than 100 percent of the pressure developed during the conduct of a periodic system perforTnance test.,
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(4) Open-ended portions of a system (e.g., suction line from a storage tank, or discharge line of a containment spray header) extending to the first shutoff valve may be exempted from the test requirements of IWC-2510.
b.
Class 3 Syster_s_
(1) The system test pressure shall be at least 1.10 times tt ? system design pressure.
(2) Open-ended portans of a system (e.g., suction line from a storage tank) extending to the first shutoff valve may be exempted from the tast re-quirements of IWD-5200.
c.
Storage Tanks The nominal hydrostatic pressure developed with the tank filled to its design capacity shall be acceptable as the system test pressure.
8.
A.gmented ISI to Protect Against Postulated Piping Failures High energy fluid system piping between containment isolation valves should receive an augmented ISI as follows:
a.
Protective measuros, structures, and guard pipes should not prevent the access required to conduct the inservice examinations specified in the Code,Section XI, Division 1 b.
For those portions of high energy fluid system piping between containment is-olation valves, the extent of inservice examination completed during each in-spection interval (IWA-2400, ASME Code Section XI) should provide 100 percent volumetric examination of circumferential and longitudinal pipe welds within the boundary of these portions of piping, c.
For those portions of high energy fluid system piping enclosed in guard pipes, inspection ports should be provided in the guard pipes to permit the required examination of circumferential pipe welds. Inspection ports should not be located in that portion of the guard pipe passing through the annulus of dual barrier containment structures.
d.
The areas subject to examination should be defined in accordance with Examin-ation Categories C-F and C-G for Class 2 piping welds in Tables IWC-2520.
III. R_E/IEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case.
Far each area of review the following review procedure is followed:
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1.
Components Suoject to Inspection The applicant's components and system classifications under Class 2 and 3 are re-viewed for agreement with Section II.l of this plan. The interpretation of code Classifications is the responsibility of the Reactor Systems Branch, should a discrepancy occur between the SAR and Section 11.1.
The applicant's classification of Class 3 systems is reviewed for agreement w h Section II.1 of this plan. Any safety-related, fluid-carrying conponents not in-cluded ir Class 1 or Class 2 and ot a part of the containment structure are in-cluded in Class 3.
2.
Accessibility The design anc arrangement of Class 2 and 3 systems are reviewed in terms of accessi-bility for ISI to establish thct the design meets the requirements of Section 11.2 cf this plan. No remote inspection progran is required for Code Class 2 or 3 components.
3.
Examination Techniques and Procedures The reviewer verifies that the examination techniques as described by the SAR are tne same as those specified in Section II.3 of this plan.
4 Inspection Intervals The inservice inspectica progran for Class 2 and 3 components in the plant technical specifications is reviewed to establish that each area and component in the progran is 9
inspected on a schedule in agreement with Section II.4 of this plan.
5.
Exanination Categories and Require ents The examination categories and parallel inspection requirements described or tab-ulated in the technical specifications are reviewed to establish that they are in agreement tith Section II.5 of this plan.
The technical specification table or description is acceptable if it follows Tables !WC-2520 and IWC-2600 in terris of headings and arrangecent for Class 2 components and IWD-2600 for Class 3 corponents.
6.
Evaluation of Examination Results The reviewer verifies that the eva;uation of examination results described in the SAR is in accard with Section II.6 of this p;a.
7 S gten Pressure Test The system pressure test program is acceptable if it ents the criteria of Section II.7 of this plan.
8.
Aurented ISI to Protect Against Postulated Pipino f ailures The reviewer verifies that the aupented inservice inspection progran as descriLed in the SAR reets the acceptance criteria identified in Section 11.8 of this plan.
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IV.
EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided in accordance with the requirements of this review plan and that his evaluation supports conclusions of the fallow-ing type, to be included in the staff's safety evaluation report:
"To ensure that no deleterious defects develop during service in ASME Code Class 2 system components, selected welds and weld heat-affected zones are inspected prior to reactor startup and periodically throughout the life of the plant. In addition, Code Class 2 and 3 systems receive visual inspections while the systems are pressirized in order to detect leakage, signs of mechanical or structural distress, and corrosion.
" Examples of Code Class 2 systems are: residual heat removal systems, portions of chemical and vol me control systems (in PWR plants), portions of control rod drive systems (in B'.R Plants), and engineered safety features not part of Code Class 1 systems. '.xamples of Code Class 3 systems are: component coeling water systems, and portions of radwaste systems. All of these systems transport fluids. The applicait has stated that the design of Code Class 2 and 3 systens meets the require-ments of ASME Code Section XI.
Compliance with the inservice inspections required by the Code and staff technical positions constitutrs and acceptable basis for satisfying applicable requirements of General Design Criteria 36, 39, 42,and 45."
V.
REVERENCES 1.
10 CFR Part 50, Appendix A, General Design Criterion 36, " Inspection of Emergency Core Cooling System;" Criterion 39, " Inspection of Containment Heat Removal System;"
Criterion 42, "Insoection of Containment Atn sphere Cleanup Systems;" and Criterion
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45, " Inspection of Cooling Water Systen."
2.
ASME Boiler and Pressure Vessel Code, Seuion III, " Nuclear Power Plant Components,"
Sections fa-2140 and NA-2110, and Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Conponents," Division 1, " Rules for Inspection and Testing of Components of Light-Water Cooled Plants," Anerican Society of Mechanical Engineers.
3.
Standard Review Plan 5.2.4, "RCPB Inservice Inspection and Testing.'
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