ML19276H942

Inservice Insp Program,10-Yr Plan Book, Revision 2

ML19276H942
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/1977
From:	Guasco G, Uziel A, Yoli A NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML18037A254	List: ML18037A253 ML18037A304 ML19276H942
References
PROC-771005, NUDOCS 8005130359
Download: ML19276H942 (500)

Text

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INSERVICE If3SPECT10N TEN-YEAR. PROGRAM PLAN BOOK NINE MILE P0 INT UNIT'l Prepared For NIAGARA M0 HAWK POWER CORPORATION Syracuse, flew York BY NUCLEAR ENERGY SERVICES, INC.

Danbury, Connecticut 06810

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Prepared by:

A. Ctiel GT Masco.

Approved'by:_

ffd A. Yoli/Proj Mgr.

Approved by N, J'>

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Approvedby:/.J.Manion,Dir.QA 7

Date: Sep t ernhe r 17. 1976

e APPEtIDIX ti ilRC REGULATORY GUIDE 1.26 4

Revision 2 U.S. fJUCLEAR REGULATOHV COMfAISGiON June 1975 s i

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REGULATORY GUIDE 1.26 QUALITY GROUP CLASSIFICATIONS AND STANDARDS FOR WATER, STEAM, AND RADIOACTIVE-WASTE-CONTAINING COMPONENTS OF NUCLEAR POWER PLANTS A. INTRODUCTION cf four quality groups, A through D, methods for assigning components to these quality groups, and the General l>.cuna Criten.on 1,,, Quality Standards and specific quality standards applicable to each quality Records, of Appenduc A, General Design Critena for group. The initial portion of this system is described in Nuclear Power Plants, to 10 CFR Part 50, Licensing 50.55a of 10 CFR Part 50, which requires that of Production and Utih,zation Facilities, requires that components of the reactor coolant pressure boundary be structures, systems, and components important to safety designed, fabri:ated, crected, and tested to the hig'iest be designed

• fabnested, ciccted, and tested to qudity aveitable national standards; du.s corresponds to the standards co:mnensurate wnh the importance of the quality standard required for quality Group A of the safety functions to be performed. Section 50.552, NRC systern. This guide describes a method for

Codes and Standards, of 10 CFR Part 50 tequirca that determining acceptable quality standards for the components of the reactor coolant pressure boundary be remaining safety-related components containing designed, fabricated, crected, and tested m accordaace radioactivc mztenal, watcr, or steam,i.e., qudity Group i

vath the iequirements for Class I components of B, C, and D components. Other systems not covered by Section III of the ASME [50i!er and Pretsure Vessel Code this gmde, such as instrument and service air, diesel or equivalent quality standards Tlu.s gu de desen.bes a engine and its generators and aux.liary support systems, quality class.fication system related to specifiyi national diesel fuel, emergency and nonnal ventdation, and fud i

standards that may be used to determine quality handling, should be designed, fabri:sted, erected, and standards acceptable to,the NRC staff for satisfyi"3 tested to quality standards crmmenqur.ae with the G:ncral Design Critenon I for other sah, elated ufety function to be perfo:med. Evaluation to es:ablish

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com, onents con::nnmg radioactive matenal, water, or the quality group classificatica of these other systems

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sten.. m watei-cooled nudear po,ver plants..he should include consideration of the ruidme; orovided in Adsisory Committce on Reactor Safeguards has been regulatory positions C.1 and C.2 of this guide.'

consuhed conceining tlus guide and.has concurred m the regula*ory position.

C. REGULATORY POSITION D. DISCUSSION After reviewing a number of applice.tions for 1.The Group B qudity standards given in Table 1 of construction pennits and o;,erating licenses t nd after this guide should be applied to water-and discussions with representatives of professiona! societics steam-cc ntaining pressure vessels, heat exchangers (other and industry, the NRC staff las develop:d a qurdity than turbines and condensers), 3 ct.;g: tanks, piping, classification system for safety relatcd components pumps, and valves that are either part of the reactor containint; rad:oactive material, water, or steam in coolant pressure boundary defined in 650.2(v) but 2

water. coo'!cd nucle r poveer phnts. The system consists exclu3cd from the requirements of @50.55a pursuant to footnote 2 of that section or are not part of the re.tetor coolant pressure boundary but part of:

l 'Jitians po.or to 1971 uf the / SMI. Daikr :nd Prenure \\.essel l

Cede, Section !!!, ".Wdor Power Plant Companents," use th:

2 term Gns A inl'eu of Oass 1.

G1 cup A quality standards that are required for pcssure-ccntini1g compan:rts of the reactor coolant pressarc

' Lines indicate schstantice chsic.s from proinus isue.

bounhry r.re specificJ in Sectian 50.55a of 10 CFR Part 50.

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a. Systems or portions of systems' important to

a. Coeling water and auxinaiy feedwater syWms or

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efety that are desipried for (l) emergency core cooling, portions of these systems' imprtmt to ufety that are (2) postaccident containment heat removal, or (3) designed for (I) cmciyncy core coohn s (2) postaccident Ossion product removal.

postaccident containment heat remoul,(3) pmt.iccilent coatainment atmosphere demuli, or (4) re3idual heat

b. Systems or pcrtions of systems' important to removal fram the reactor and from th spent fuel 3 crage Lifety that are designed for (1) reaetor shutdown or (2) pool (including ['runary and secondary coehn '. qstems).

portions of these systems that ate required for their residual heat removal.

safety functions and that (1) do not op rate daring any

c. Those portions of the steam systems of boiling mede of noimal reactor operation and (2) cannot be water reactors extending from the outermost tested adequately should be cla,sitied as Group B.

containment isolation valve up to but not including the lIturbine stop and bypass valved and connected piping up

b. Cooling water and seal water systems or portions to and including the first ulve that is either normally of these systems' important to safety that are designed

' closed or capable of automatic closure during all modes for functioning of components and systems important to o'r normal reactor operation. Alternatively, for boiling safety, such as reactor coolant pumps, diesels, and water reactors containing a shutoff valve (in additwn to Control room.

the two containment isolation valves) in the main steam Ime and in the main feedwater line, Group B quality

c. Systems or portions of systems) that are stand trds should be apphed to those portions of the connected to the reactor coolant prenure boundary and steam and feedwater systems extending from the are capable of being isolated from that boundary during outermost contaimnent isolation valves up to and dl modes of normal reactor operation by two Valves, l iaetoding the shutoft valve or the fust valve that is either each of which is either normally closed or capable of normally closed or capable of automatic closure during automatic closure.8 all modes of normal reactor operation.

d. Radioactive waste treatment, handling, and d.Those portions of the steam and feedwater disposal systems,' except those portions of these [

systems of pressurized water reactors extending from systems whose postulated failure would not result in and including the secondary side of steam generators up conseivatively calculated potential offsite doses that

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to and includmg the outcrrnost containment isolation exceed 0.5 rem to the whole body or its equivalent to valves and connected piping up to and induding the first any part of the bodj. For those systems located in valve (ineladmg a safety or relief valve) that is either Semmic Category I structures, only single component normally closed or capable of automatie closure during failurcs need te assumed. (llawever, no credit for automatic isolation from other components in the all mod:s of normal reactor operation.

sistem or for treatment of released material should be taken unless the isolation or treatment capability is

e. Systems or portions of systems) that are connected to the reactor coolant pressure boundary and deaigned to the appropriate seismic and quality group are not capable of being isolated from the boundary standards and can withstand loss of offsite power and during all rnodes of nonnal reactor operation by two single filure of an active component.) Parts of these valves, each of which is either normally closed or capable systems beyond the processing steps (such as monitoring of automatic closure, tanks) may be classified as Group D if the r! ant Technical Specifications limit inventories to levels i

2.T; e Group C quality standards given in Table 1 of which, if released, would not result in conservatively this guide should be applied to water., steam., and calculated potential offsite doses that exceed 0.5 rem to radioactive. waste-containing pressure vessels, heat the whole body or its equivalent to any part of the exchangers (other than turbines and condensers), storage body.

tanks, piping, pumps, and valves not part of the reactor coolant pressure boundary or included in quality Group 11 but part of:

SCorrponents in inth'ent hnes raay te clas:ified as Group O*

praided they au capable of bein; i',olate t from the reactor 3The system boundary includes those portions of the system coulant pressure bounduy by an additianal vahe which has required to acccmplish the specined safety functica and high teakti;;ht inter,rity, connected piping up to and including the nrst valve (including a 6

safety or relief vabe) that is either norm:J1y closed or capable Ihe replatory positiun regardiag quahty group classifications cf automatic slosure when the safety functiin is required.

fy these system, n under revi,:w. In the preposed raison specific components inay be assened to appropriate quality 4The turbine stop valve and turbine bypass valve, although not groups conunenturate wah the need to rrotat the heahh and

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included ia quahty Group lb should be :ubjected to a quahty safety of the pubhe and operatis persoon:1. A separate suurance program at a Icvc! gnerrily equivalent to quality regulatory guide v,c1 be devclope t nd issued to replace this A

subsection of Rc;;otatory Guide 1.26.

Group D.

1.26 2

c. Other systems not covered by items 2.a through steam-containing components not part of the reactor 2.d above that contain or may contain radioa:tive coolant pressure boundary or included in quality Groups material and whose postulated failure would result in 11 or C but part of systems or portions of systems that conservatively calculated potential offsite doses (using contain or may contain radioactive material.

meteorology as recommended by Regulatory Guides 1.3 (Revision 2), " Assumptions U:,ed for Evaluating the D. IMPLEMENTATION Potential Radiological Consequences of a less of Coolant Accident for 11;iling Water Reactors," and I A Tlie purpose of this section is to provide informatio'n (Revision 2), " Assumptions Used for Evaluating the to applicants and licensees regardmg the staff's plans for Potenti.d Radiological Consequences of a loss of utilizing this regulatory guide.

C<>olant Accident for Pressurized Water Reactors ') that exceed 0.5 rem to the wl] ole body or its equivalent t Except in those cases in which the applicant proposes any part of the body. I or those systems located in an alternative method for complying with specified Scisimc Category I structures, only smgle component portions of the Commission's regulations, the quality failures nced be assumed. (flowcver, no credit for group classifications and standards described herein will automatic isolation from other components m the be used in the evaluation of submittals for Operating system or for treatment of released material should be li:ense o'r construction permit applichtioris dodekd

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taken unless the isohtion or treatment capability is after January 1,1975.

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designed to the appropriate seismic and quality group

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standards and can v ithstand loss of offsite power and a If an applicant wishes to useIbis regulathf guide (ri single failure of an active component.)

developing submittals for applications. docketed on'or 3.The Group D quality standards given in Table 1 of bcfore January 1,1975, the pertinent portions of the this guide should be applied to water-and application will be evaluated on the basis of this guide.

TABLE 1 QUA LITY STANDARDS Components Quality Group B Ouality Group C Ouality Group D Pressure Vessels ASME Boiler and Pressure ASME Boilcr and Pressure ASME. Doller and Pressure Vessel Code, Section Ill, Vessel Code, Section Jil.

Vessel Code, Section Vill

" Nuclear Power Plant Com-

" Nuclear Power Plant Com-Division 1 ponents,"a,1),c Class 2 ponents,"a,b,c Class 3 A' above ANSI B31.1 Powe'r Piping Piping A's above s

Pumps As above As above Manufacturer's st ndards..

Valves As above As above ANSI B31.1.

s Atmospheric As above As above '

API-G50,'AWWA D 100, or Storage Tanks ANSt 005.1 a

0-15 psig As above As above api 620 Storage Tanks

,g,y i..

e5cc Sectkin 50.53a for guidance wi'h reg.vd to the Code and Addenda to be applied.

bASME Codo N-symt of need not tm appheJ.

CThe specibe ep t.caNhty of ca& caw will be covered separa:ely in other regulatorv guides or in Comm:ssian regulatia.ns.where c

eppropriate. Apphcants proposing the un of code ca;cs not cowred by stadcs or regulations 5hould demonstrate that.r; ar.ceptcble

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level of c4u.thty arid saf ety v,ould be echieved.

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