ML19221B100
| ML19221B100 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-05.4.2., NUREG-75-87, NUREG-75-87-5.4.2., SRP-05.04.02.02, SRP-5.04.02.02, NUDOCS 7907120424 | |
| Download: ML19221B100 (3) | |
Text
NU REG-75/087 fgR Rrc %
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U.S. NUCLEAR REGULATORY COMMISSION
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STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION SECTION 5.4.2.2 STEAM GENEFATCR INSERVICE INSPECTION REVIEW RESPONSIBILITIES Prira ry S'a terial s E'
- ing Eranch (MTEG)
Secondary - None I.
AREAS OF REVIEW General Design Criteria 1 and 32 of Opendix A of 10 CFR Part 50 raquire that components which are part of the reactcr coolant pressure boundary (RCPB) nr other comparents 1":portant to safety be designeJ to pernit periodic inspection and testing of critical areas for struc-tural and leaktignt integrity. The cesign of the steam generators as described in the preliminary safety analysis report (PSAR) is reviewed to establish that use of the specified inspecticn techniques is feasible. The provisions rade for baseline inspection prior to startup, the rethods to be used for tne inspections, and the inservice inspectiori prograr are reviewed in the final safety analysis report (FSA) and plaat Technical Specifications.
II.
ACCEPTANCE CRITERI A The design of the steam generators to provide access for an inservice inspection (ISI) progran, and the proposed ISI progren should follow the AS"E Coiler and Pressure Vessel Code (hereaf ter "the Code").Section XI, and the recomendations given in Regulatory Guide 1.83,
" Inservice Inspection of Suan Generator Tubes."
Specifically, the steam generators should be designed to pernit inspection of any ccsonont, including individual tubes, and the repair or replacenent of any component. The tube exanination equiprent and procedures should be cap 3ble of detecting and locating defec+.s with a penetration of 20: or rore of uhe wall thickness. A pertarent record of test data should be provided. A baseline tube inspection should be scheduled prior to startup. Tne sarple selection and testing of tubes, the inspec-ticn intervals, and tne actions to be taken if defects are identified should follow the recon-nendations of Regulatory Guide 1.83.
Section XI provides for the volLratric inspection of the following components: longitudinal and circunferential welds, including tube-sheet-to-head or snell welds on the prinary side; prinary nozzle-to-vessel head welds and nozzle-to-head inside radiused section; primary nozzle to safe-end welds; prinary side pressure-retaining bolting; integrally-welded primary vessel supports; circumferential butt welds on the secondary shell side; and USNRC STAND ARD REVIEW PLAN Stendere review p6ene are peepered for the guedence of the Office of Nuclear Reector Regulation staff responsible for the review of appl 6cetione to construct and operate nuclear power plente These dccumente are made eveeleb6e to the public es part of tt'e Commsesson e polsc y to enform tee necesor 6ndustry end the genered pubhc of regulatory procedures and po66c,ee Stendard review piens are not subotnutes for regulatory guedes or the Commission a regulatione ad4 8
cornpironce weth theen es e of required The stonderd review plan sectioes are heyed to Revieson 2 of the Stendard Forme: and Content of Safee, Ane yees Rap s1{
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for poucteer Power Plante Not ett sections of the Stenderd Format howe e correspondmg recew plan Putstiohed ster 6d6ed review plane wdf be revised per odiceHy se oppropriate to accomenodete commente end to refisct new knformation and esper once Camerente eq ouggeenone for improvernent w.H be considered and should be sent to the U S Nuc4eer Reguletory Commiseson. Office of Nucteer Reactor Reguisesen. Weehengton D C 2"E86 7 90712 0 4M
nozzle-to-vessel welds on the secondary side. The volumetric inspections are supplemented, as detailed in the Code, by visual and surface inspections for both prirary and secondary sten generator Code Class 1 and 2 components.
III. REVIEW PROCEDURES The reviewer will select and emphasize raterial from the procedures described below, as ray be appropriate for a particular case. He deternices that the design of the stea gerera-tors, as described in the PSAR, Will perrit access for the specified inspection techniques of all stean generator corponents including tubes. He also evaluates the design of the steam generator as described in the FSAR and the Technical Specification inservice inspection progran to deterniae the degree to which the reccrrendations of Regulatory Guide 1.83 and Code Section XI have been followed. The reviewer determines that the techniques to be used for inservice inspection are those listed in Section XI.
He deterrines that the inspection technique f or the tubes, the selected number of tube sanples, the inspection intervals, and the actions to be taken in the event cefects are observed are in accordance with the posi-tions stated in the guide. He determines that a baseline inspection will be made prior te startup of the plant. Standard Review Plan 5.2.4, " Reactor Coolant Pressure Boundary Inservice Inspection nd Testing," covers the ISI of Class 1 con ponents of the stear gen-e ra tors. Standard Review Plan 6.6, " Inservice Inspection of Class 2 and 3 Components," is applicable to ISI of the balance of the corponents of the stem generJtor, which are all Class c components.
IV.
EVALUATION FINDINGS The reviewer verifies that suf ficient inf ormation has been provided in accordance with the requirements of this review plan, and that his evaluation supports conclusions of the following type, to be included in the.* > f t's safety evalu3 tion report:
"The steam generators have been designed to permit inservice inspection of all Code Class 1 and 2 components including individual tubes as recomended in Regulatory Guide 1.83, " Inservice Inspection of Stean Generator Tubes," and ASME Code Section XI.
[The inservice inspection orogran f or the steam generators is in accordance with the recomendations of the at;ove-cited Regulatory Guide and A5h Code Section XI with respect to the inspection rethods to ue used, provisions tcr a t;aseline inspection, selection and saTaling of tubes, inspection interval.
and actions to be taken in tra event defects are identified.*] Confornance with Fegula tary Guide 1.83 and ASME Code Section XI constitutes an acceptable basis for neeting in part the requirenents of General Design Crithia 1 and 32.
V.
EEFER!NCES 1.
10 CFR 50, Apperdix A, General Design Criterion 1, " Quality Standards and Records."
2.
10 CFR 50, Appendix A, General Design Criterion 32, " Inspection of Reactor Coolant Pres sure Bounda ry."
- The statement enclosed in brackets should only t,e included in the staf f's safety evaluation report for an FSAR.
5.4.2.2-2 7
] [
3.
ASME Boiler and Pressure Vessel Code,Section XI, " Inservice Inspection of Nuclear Power Plant Coc.ponents," Division 1, " Rules for Inspection and Testing of Components of Light-Water Cooled Plants," Icerican Society of Mechanical Engineers.
4.
Regulatory Guide 1.;3, " Inservice Inspection of Steam Generator Tubes."
147 148 5.4.2.2-3