ML20126M096

Forwards Modified Response to Question 411.23,per 810605 Telcon

ML20126M096
Person / Time
Site:	Fermi
Issue date:	06/09/1981
From:	Colbert W DETROIT EDISON CO.
To:	Kintner L Office of Nuclear Reactor Regulation
References
EF2-53-500, NUDOCS 8106110345
Download: ML20126M096 (53)

Text

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EF2 - 53,500 Mr.

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Kintner Division of Project Management Office of Nuclear Regulation U.

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Nuclear Regulatory Commission Washington, D.

C.

20555

References:

1.

Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 2.

Letter, W.

F. Colbert to L.

L.

Kintner, EF2 - 53,427, June 2, 1981, " Response to Q. 411.23"

Subject:

Revised Response to Q. 411.23 The attachment is a modified response to Q.

411.23 based on a telecon with the NRC Staff (Mr. Jack Spraul) on June 5, 1981.

Sincerely, l

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W.

F.

Colbert Technical Director Fermi 2 Project NFC/AEW:jl Attachment cc:

Mr.

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i Clarification to NRC Ooen Item - Q List Table 3.2-1 of the FSAR has been supplemented in accordance with the attachment. The items identified as " Seismic Category I" in Table 3.2-1 will be subject to the pertinent provisions of 10CFR50, Appendix B during the operational phase.

In addition, non-Category I Leems as identified in the attached detailed response will also be subject to the pertinent provi-sions of 10CFR50, Appendix B during the operational phase.

A complete listing of these items will be provided in a future FSAR amendment.

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NRC OPEN ITEM "Q" LIST REQUEST FOR ADDITIONAL.1NFORMATION ENRICO FERMI 2 NUCLEAR POWER PLAffI 411~.0

' Quality Assurance Branch 411.23 ' Section 17.1. 2. 2 o f the standard format (Regulatory Guide 1.70) requires the identification of safe.ty related structures, systems and components controlled by the quality assurance program. You are requested to sup-plement and clarify the Fermi 2 list inTable 3.2-1 of the FSAR in accordance with the following:

i a '. The following items do not appear in Table 3.2-1 of the FSAR. Add the appropriate items to Table-3.2-1 and provide a det::=itment that the remaining items are subject to the _ pertinent requirements of the FSAR operational quality assurance program or justify not doing so.

j Item 1:

List'of items provided in a document titled " Summary List

- QA Level 1 (' Safety-Related') Systems, Structures, and Major Components."

'7&H A++- i+g74/h.Cs.de'sD To NY O' p;g ees listed in the document titled "Surnary Lis t. - QA Answer:

Levell- ( ' Sa f ety Related ' ) System, structures, and major

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Item 2:

Biological shielding within reactor building, auxiliary

' building, radwaste building,'and control center complex.

Answer:

Biological (sacrificial) shield' wall, reactor building, auxiliary building, and control center complex radiation i

shielding are being added to table 3.2

,1,Section XXXVI

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Item 3:

Missile ba-riers within reactor building, auxiliary building, control center complex, and RHR complex.

of Item 2, 3,g'ned in Table 3.2-1,Section XXXVI, as item is conta Answer:

This wnd 7.

part Item 4:

MSIV leakage control system a) Piping, within RCPB isolation valves.

t b') Piping, other upstream system lines.

c) Piping, downstream system from steamline, d) Piping, other downstream system from steamline.

e) Valves, within RCPB.

f) Valves, other.

l g) Heater, h) Blowers.

Answer:

This' item is being added to Table 3.2-1, Section XLI with the exception of c, d, g and h which are not e-r'-

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Item 5:

Main steam piping to turbine stop valves.

i Answer:

This piping is included in Table 3.2-1.

Section XXXII, Item 1.

However, this item is being revised to read " Main steam piping to third MSIV".

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i-Item 6:

Piping and valves, main steam-branches.

Answer:

This piping is included in Table 3.2-1,Section XXXII, Item 2.

.However, this item'is being revised to read

" Piping and valves, main steam branches upsteam of ' third

. MSIV to the - first isolation valve.

Item:7:

Main steam dump line and' valve.

'Aeswer:

- This piping is deleted from Table 3.2-1, due to the.

addition' of the third MSIV.

7 Item 8:

Spent fuel pool and liner, dryer / separator pool.

Answer:

This item is included in Table 3.2-1 Section XXXVI, Item 2.

Item 9:

Nuclear boiler system - mechanical modules and instrumen-tation with safety function.

Answer:

This item is included in T,able 3.2.1 Section II, Item 13.

Itec 10:

Residual heat removal system - mechanical modules.

Answer:

This item is included in Table 3.2-1,Section IX, Item 10.

Item 11: HPCI booster pump.

Answer:

This item is included in Table 3.1-2, Sec tion XI, Item 8.

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Item 12:. Fuel preparation machine.

Answer:

This item is ' included in Table 3.2-1,Section XIII, Item 1.

-Item 13: General. purpose grapple.

' Answer:

'D11s. Item is included in Table 3.2-1,.Section XIII, 1

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Item 2.

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Item 14:. Steam line plugs.

Answer:

This ' item is Jincluded in Table 3.2-1 Section XIV, Item 1.

Item 15:. Dryer an,d separator sling.

Answer:

This item is included in Table 3.2-1 Section XIV, Item 2.

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Dryer and head strongback.

l ltem 16:

Answer:

This item is included in Table 3.2-1,Section XIV, Item 2.

Item 17:

Control rod grapple.

Answer:

This item is contained in Table 3.2-1,Section XV, Item 1.

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Item 18: " Refueling equipment platform assembly.

Answer:

This. item is contained in Table 3.2-1,Section XVI, Item 1.

Item 19:

Fuel. storage racks.

l-Answer:

This item ts contained in Table' 3.2-1,Section XVII,-

Item 1.

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Item 20:

Defective ~ fuel. storage.onta ner.

Answer:

' This' item is contained in Table. 3.2-1 Section XVII, Item 2.

Item 21:

Sacrificial shield.

Answer:

See item 2.

Item 22:

Stabilizer truss system - earthquake (FSAR Section 3.8).

Answer:

Reactor vessel stabilizer truss are being added Table 3.2-1, Section 1 / 7dN / 7.'

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Item 23:

Support truss sys tem - pipe break (FSAR Section 3.8).

Answer:

Support truss sys tem is being added to Table 3.2-1,Section XXXVI) rT&M j I

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Item 24:. Safety-related masonry. walls (see. IE Bulletin 80-11).

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Answer:

Safety-related masonry salls are being added to Table 3.2-1, Item XXXVI IT M j '

3 Item 25: ' Cont ain' men t isolation valves 'for the a) MSIV' leakage control system l

b) Feedwater system l

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c) RHR to containment spray. header I

i Answer:

This. item is included in Table 3.2-1 under ' the appropriate system.

Item 26:

Containment /drywell hydrogen monitoring system.

-Answer:

Containment /drywell hydrogen monitoring system is not j

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- safety-related and is not added ' to Table ' 3.2-1.

This item is being added to the operational QA program, j

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Item 27:

Primary containment' vacuum' breakers.

Answer:

Primary containment vacuum breakers is included in Table 3.2-1, Section XXVIII, as part of Item 1.

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. Item 28:

Automatic depressurization system.

' Answer:

Automatic depressurir.ation system is included in Table 3.2-1,Section II, "Tr%S$/ JF i

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-Item 29: MSIV leakage control system.

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l Answer:

See Item 4 j

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l Item'30:

Leak detection system.

. Answer:

' Leak-detection Jis included in the appropriate system under the heading electrical modules.

Icem 31:. Radiation monitoring. (fixed and portable).

Answer:

Radiation monitoring is considered to be part of the Process. Radiation Monitoring System.

Safety-related monitors are listed in Table 3.2-1,Section VIII, non-safety related monitors are. being included in the

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operational QA program.

Item 321 Radioactivity' monitoring (fixed and portable).

Answer:

Radioactivity. monitoring is considered to be part of the

^

Process Radiation Monitoring System-Gaseous ef fluents.

Radioactivity monitoring equipment is ' not safety-related and is not being~ added to Table 3.2.1.

This item is being added to the operational QA program.

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' Item 33i Radioactivity sampling (air, surfaces, liquids).

Answer:

Radioactivity sampling is ' considered to be part of the l'-

Process Radiation Monitoring System-Gaseous ef fluents.

Radioac tivity sampling. equipment, is not safety-related and is not being added to Table 3.2-1.

This item is being added to the operational QA program.

Item 34: Radioactive; contamination measurement and analysis.

Answer:

Radioactive contamination measurement and analysis is considered as part if the Heath Physics system.

Radioactive contamination measurement and analysis is not i

safety related and is. not being added to Tapje 3.2-1. This equipment is being added to the operationaf[ program.

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--o-Item-35:

Personnel: monitoring internal (e.g. whole body counter) and external (e.g., TLD sys tem).

Answer:

Personnel monitoring is considered to be part of the Health Physics System.- This equipment is not safety-related. and not being added to Table 3.2-1.

Item is being added to the operational QA program, i

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Item 36:

Instrument storage, calibration, and maintenance.

Answer:

Instrument storage, calibration, and maintenance items are controlled by plant procedures. Table 3.2-1 contains systems, structures, L and components, therefore these Ltems are not 'being added to Table 3.2-1.

These item are being' added to the operational QA program.

Item 37:

Decontamination (facilities, personnel, and equipment).

Answer:

Decontamination is not a safety-telated function and is not being added to Table 3.2-1.

This item is being added to the operational QA program.

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I Item 38:

Respiratory protection, including testing, o

l Answer:

Respiratory protection is not a safety-related item,.

j and is not being added to Table 3.2-1.. This item is being L

added to this operational QA program, t

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Item 39:

Contamination control.

procedures, Answer:

Contamination control is regulated by plant and is not being added to Table 3.2-1.

This item is.being added to the operational QA program.

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Item 40: Radiation shielding.

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Answer:

Radiation shielding includes primary containment, reactor building, auxiliary building, masonary walls, and sacrifi-1 cial shield wall are currently; included in Table 3.2-1, l

. Item XXXVI.

l Item 41:

Meteorologic.1 data collection programs.

Answer:

Meteorological data is not classified as safety equipment j

and is not added to Table 3.2-1.

This item is being added l

to the operational QA program.

Item 42:

Breakwater.

Answer:

Breakwater is included in Table 3.2-1, Section XL.rW f

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W i"t'2 4 & M Item'43: 'Feedwater spargers.

Answde:

Feedwater spargers are not classified as safety.related i

equipment and are not being added to Table' 3.2-1.

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s Item 44:

Expendable and consumable items necessary for the

'I functional performance of safety-related structures, systems, and components (i.e. weld rod, fuel oil, boric acid, snubber oil, etc.)

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n ace 14 " ** "' p cgspy g g s Answer

These items are bought b plant ~ '- '!:: '- ;. They are noe being added to Tab 1e 3.2-1.

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Item 45:

Measuring and test equipment used for saf ety-related structures, system, and components.

Answer:

This equipment is not considered safety-related and is not being added to Table 3.2-1.

This equipment is added to the operational QA program.

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. Item'46i Air' pressurization system -(~with its associated piping and

instrumentation) used in the operation of the main steam line ~ isolation valve leakage control system.

Answer:

Air - presurization system is being added in Table 3.2-1, 7

Section XLI efSNS et ym/_/.4'.

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Item 47:

Charcoal adsorber units, duct work,.and other system components related to. the control room pressurization and recirculation system.

Answer:

This item is included in Table 3.2-1,Section XXXIX,

/MM/ rWe'd/ /'s item'48:

Chlorine and radiation monitors associated with the control :oom ventilation system.

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Answer:

Radiation Monitors are categorized as part of the Process

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. Radiation' System.

Table 3.2-1 is updated.,to include this item. Chlorine detectorsfare not safety-related and are I

not being added to Table 3.2-1, but they will be added to the' operational'QA program.

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The following items from Table 3.2-1 need expansion and/or clarification.as noted.' Revise the' lis t as indicated or justify not doing so.

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Item 1:

Control center complex (including the cable spreading room) should be under the controls of the operational quality assurance program (XXXVI-6).

1 Answer:

Control center complex is included in Table 3.2-1 and is under the controls of the operational quality assurance J

program.

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Item 2:

CRD hydraulic system containment isolation valves should be under: the controls of the operational quality assurance program (IV-1).

Answer:

Not applicable to Fermi, CRD return line and associate isolation valves were deleted,4 r4N /4W7' 4:745 / 4M GED/15/1.9 1'

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I e Item 3:

Neutron monitoring system TIP -piping and containment a

isolation valves should be under the controls of the operational quality assurance program (VI-l & 2).

Answer:

Neutron monitoring system TIP piping and containment isolation valves-are included in Table 3.2-1 and is being added to operational' quality assurance program.

1 Item 4 Identify the safety-related instrumentation and control systems to the same scope and level of' detail as provided in Chapter 7 of the FSAR.

Answer:

Safety-related instrumentation a'd control systems and components are identified in detail in Chapter 7 of the ESAR M Wd4M WAMC f# W C AC.e:W 9 64444 $dAdh7 s491Vt;'*WCf fu'/d.-WJ, Item 5:

Item VI, Neutron Moniltoring System, should include sub-item 5, Instrumentation and Control for Rod Block Monitoring System and Rod Sequence Control System.

Answer:

This item is being added to Table 3.2-1,Section VI, Item 5.

l-l Item 6:

Item XVI, Re fueling Equipment, should include sub-item 3, Instrumentation and Control for Refueling Interlocks.

Answer:

This item is not safety related and therefore is not being added to Table 3.2-1.

This item is being added to the operational QA program.

i Item 7:

Item XIX, Reactor Water Cleanup System, should include sub-item 9, Instrumentation and Control for Demineralized Water Make-up and Ultimate Heat Sink.

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This item is not -- '

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2 Item 8:

It'em XXXIV, AC Power System, should'be expanded to include a) Diesel generator _ packages including auriliaries

-(a.g. lube sys tem, ' j acket cooling, air start system, governor, voltage regulato'r, excitation system),

b) 4160 volt switchgear.

c) 480V load centers..

d) 480V motor control centers.

e) Instrumentation, control, and power cables (including underground cable system, cable' splices, connectors, and' terminal blocks).

i f) Conduit and ' cable trays and their supports.

(. Instal-lations containing class.1E cables and'other installa-

'tions,whose failure may. damage other safety-related

.'i t ems. )

g) Transformers.

h) Valve operators.

i) Protective relays and control panels.

j) AC control power inverters.

k)L120V AC vital bus distribution equipment.

1) Containment electrical penetration assemblies.

m)'Other' cable penetrations (fire stops).

i-Answer:

The safety-related items in the above list will be added l

to Table 3.2-1,Section XXXIV.- AC control power inverters are not applicable to Fermi.

However, Fermi uses small AC l

control power inverter dedicated to specific systems and ae considered as instruments in the sys tem.

For Item. (f) only the support for the conduit and cable

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IJ Item 9:

Item XXXV, DC Power Systems, should be expanded to include a) 125V batteries, battery chargers, and distribution equipment.

b) Cables.

4 c) Conduit and cable trays and their supports.

(Installa-tions containing class IE cables and other installa-tions whose failure may damage <other safety-related items.)

d) Battery racks, e) Protective relays and' control panels.

Answer:

The -safety-related items ' of the above are being added to the table. For Item (C only the con' uit and cable tray # M6 d

ed.

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- Item 10: Just as Item VIII addresses Process Radiation Monitors, an item should be added to address Effluent Radiaticn Monitors.

Answer:

This item is being added to Table 3.2-1,. JIfdW#Md7d

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Item 11:

Item XXIII, Off-Gas System, should include sub-item 9, Steam Jet Ejectors..

Answer:

Steam jet air ejectors are not safety-related and are not added to Table 3.2-1.

Item 12:

Items XXVIII, Primary Containment Atmosphere Control System, and XXXI, ECCS Equipment Area Cacting System should each include sub -item 2, All Other Components.'

Answer:

This item is not being added tu the' Table 3.2-1.

All components with safety function cave been included in the i

table.

Item 13:

Item XXIX, Standby Gas Treatment System, should 'oe clarified tc> include the deep bed charcoal absorbers and duct work.

' Answer:

This item is not being added to Table 3.2-1.

All components with safety function have been included in the table.

i GED/15/1.12

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c.. Enclosure 2 of NUREG-0737, " Clarification of TMI Action Plan Requirements" (November.-1980) identified numerous items that are safety-related and appropriate for OL application and therefore should. be on the Q-lis t.

These items are listed below.

Add the appropriate items. co the Q-list. and provide a commitment tha t the remaining items. are subject -to the pertinent requirements - of the FSAR-operational'QA program or justify not doing so'.

Item 1:

Plant-safety parameter display console.

(I.D.2)

Answer:

Not safety-related. hhWC/df!s

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Item 2:

~ Reactor coolant system vents.

II.B.1 Answer:

No equipment changes are necessary.- ggy/pesey; p&d;-

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Item'3:

Plant shielding.

11.3.2 Answer:

Shielding is being added to Table 3.2-1.. >$c?/#N IX///,

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Item 4:

Post accident sampling capability.

II.B.3 7

Answer:

Table 3.2-1 will be revised to reflect the additional equipment.

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l Item 5:

Valve position indication.

II.D.3 i

Answer:

This item is included in Table 3.2-1,Section II, Item 13 and 14.

4 Item 6:

Dedicated hydrogen penetrations.

II.E.4.1 Answer:

This item is adequately covered in Table 3.2-1, Sec tion XXXVI.

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Containment isolation dependability.

II.E.4.2

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No additional' equipment is required. Existing equipment j

Answer:

are covered under the appropriate section of Table '3.2-1.

Item 8:

'Accida.nt monitoring ins trumentation.

II.F.1 Answer:

Table 3.2-1 will be revised for QA I equipment as needed.

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Item 9:

Instrumentation for detection of inadequate core-cooling.

t Answer:

This activity is under review by 3'4R Owners Group.

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HPCI and RCIC initiation levels.

.II.K.3(13)

Answer:

No equipment' changes required, logic changes only.

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Isolation of HPCI and'RCIC.

II.K.3(15) t Answer:

Equipment changes required are included in the appropriate section of Table 3.2-1. (.%C71 m' X/, s'fGHT J2 6 If, l JCC7tW X11, i TCNJ [f $ //),

i Item 12:

Challenges to and failure of relief valves.

II.A.?(16) logic changes Answer:

No equipment changes required e=

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only.

Item 13: ADS actuation.

II.K.3(18)

Answer:

This equipment is included in the Table 3.2(al,Section II, Item 14 GED/15/1.14

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'l Item 14:

Restart of core spray and LPCI.

II.K.3(21)

Answer:

- No equipment changes required, logic changes only.

- Item 15':, RCIC suction.

' II.K.3(22)

Answer:

Equipment is included' in Section XII, Item 10t, Table 3.2-1.

Item-16:. Space. cooling: for HPCI and RCIC.

II.K.3(24) i a,

- t Answer:

No equipment. changes. required.

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- Item'17:

Power on _ pump seals.

.II.K.3(25) 1..

Answer:

No equipment changes required.

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' Item 18:

Common reference level.

II.K.3(27)

JAnswer:

No equipment changes required.

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' Item 19:

ADS valve, accumulators, and associated II.K.3(28) l

- equipment and ins trumentation.

l Answer:

Not applicable. to Fermi.

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Item 20:

Emergency plans.

III.A.I.1/III.A.2 Answer:

Emergency plans meet criteria of NUREG 0654.

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s Item'21:

Emergency support facilities.

III.A.I.2 Answer:

These facilities meet tWREG 0696 requirements. r-- U / r r oj W/u M M W /?-rt.4 /2fk!fM M [

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s?.Af 'J.,;/J,Jhy Item 22:

Inplant 12 radiation monitoring.

III.D.3.3 Answer:

See Part a, Item 31.

~ Item 23:

Control-room habitability.

III.D.3.4

• a Answer:

No. equipment changes required c: 9 # -

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Reactor Assembly Af' //

Fuc1 Asse

bly fg/L t2-f, irgM Reactor Vesset f4,fgfj Z f sygs/ Af,f Reactor Vessel Sui YAfdd K2"/, /fdP/J [> 4 y

Reactor Vessel Stabilizer 7,##t5 3 7-/, /f6 T,3 Shroud and Shroud Support, yJvjg' Jg-/, f rp/I,f g

includ!.ng Core Spray.Sparger Cote Spray Line y g g g 3 g j,, yg,, # f j '

Core Support ppgf3

,yg. pidff

. Top Guidc

-ygg jg-/,

,ygp,df f Orificed Fuel Support

-r,v grg g f f.,-/, f r,f +fd.I,_6' I

Fccdwater Sparger

-f,4ffg J g-/,

syg,,p'j7,f Control Rod Including Velocity

\\

Limttcr 7;Qpfd.]Z-f, /fd Y I.Y Control Rod Drive ggjg.f

, 7g,f.eg, g (sntrol Rod Guide Tube p//d 46;/, r76e/ E. 8 Control Rod Drive Housing ppgg,.rgf.

,gy,,/ - y Control Rod Drive Housing I ',}

SU?9OCL

~

7,.*iff ddj Z'f /19t*'I, J>l Jet Pump Asse=b1y 7Js/ /d5, E-/, / 7d' e/-T-l' Power Range Seutron Detectors

ggggg, gje g,/S

. _ ~. _ _ _ _ -

I

/ --

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l

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b/f0/bT'VN, Nuclea r P.nlle r Svs tem Prirw ry P res su re. Bounda r/ Piping and Isolation Valves for the following systems:

Teeduater -.

PR//5JZ-f /f&'/

Y W

e Matn Steaa _ __

gyffj[-/, /rgpf 22', d'-

~)

Steam to H?CI _-.

fgggs Jf-/,sfds/ Y sb Reactor Vesse1 licad Spray

ppg &J[-g /fg# 21 7 Core Spray pgrydg3 C-/, /7d' M#E'~ / ~

low Pressure Coolant

/

Injection _

74s/g6.4 T-/, /Gir/g,3 yggg'dj i-/, jfgefj, J Residca1 !!es t Removal' Standby Liquid Control 7)fd463Z'/s /W/# 3 7'.

t Reactor 'Va te r Cleanup y p f g g 3 p j f g /s/d2, I

Safety /Rc1Lai Valves 7;9stg f f.Z-/, 7 7s' +/ $, 9 Main Stcan Line Flow j

Re_s t ric t o r 7}%ddddC'7,' /TC H.E,*,/

r__

- w

=-

+

sw 7' /N M// Mto/&/

Main Stes= Line Suspension

,T#ggg g g--f jy !!!:A/#j,f l

l

.,\\

l-

=ys l

l

.-m..

.o

~'

. ;= :

e, Tncident Deteetton Circuttry

. _., 8AW5WS Core Scandby Cooling Systees Initiatin; Channels and togie, _

7sfgg;:n-/. /rp/ E,///.

Automa tic 3cpressuri::a tion Sys te-In1,tia e ing_ChanneIc a,nd_Lo;;ie rA g g f g-/- /tdH/ 8,/M Reac tor P.nci rcula t ion S vs tem j

Recirculation Pumps 7,A/g(5,gd:-/ /75p/ J,p'

996/f ] d'f jf D,/, $..S~

. Recirculation Vaivcs N'df /=s'.O// C&fh'V'

" ^ ~ ~ '

5.x -

_Racircula tion Pipin;;

<pp/g _-f, g-/,, f r5// 5, /

j ff/ /E,2 t

Recireulation' Loop Suspcesi:.

pyg J, g-/j

-.Recircu. l.uion. L. cop Res t ra in:s 7,pp g g / f ;/ / f54_22Z 3

/

A Control Pod !!vd raulie S vs tem

)

Portions of the !!v(.raulic C:r.:ra *.

Unit Necessary to'r Scra

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l

.i..ns..t r...e_x.c n t a t io n __.

)/4* dd a 1 C*/, s K.& f 2,,9 j,

76NNi h Insert and Withdrav I.ines

-7)d g 4 S f, E -/j /

I#//6/ 6M /'T6'/ M* I

Scram Discharr,e. Volume f

Feedwa ter control "svs tem (Prica ry Pressure twundary integrity - only) 7pp g & f, 7 -/

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./

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s l'

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Accumu la to r

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A Puops_.

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Explosive Va1ves _ _

gj,tyggj gg j;,ggfJ g

' ?$PL

.~. -. -.

... /Wdd!3Z%' /'"fA/.-. #/ $

- Ins trumenta tion Powe r Supply and Instrumentation fryg(d'ffj'-fy /j'd Af 2, f Controls and Electrical Equipeent

.y4ddd 48"/ /f5A/ I, f Neutron t'onitor Svs ten Guide Tube Valve Assembly _.

_ _7g/g fg-/ fygA/ [ f_

Intermedia te ?.ange Moni tor and fffg,5 ffd,/76// 3,3 Detectors Avera;c Power P.ance Moniter

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ver _

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?

,, r i y

/d Cutde Tubes y,pgg33 gt Reactor Protection Svstem

.s

%/jfd'S'd 2-/, /;"dFe' / //h Electrica1 Alarm 6 Trip Systc=_

.---e.*e

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Pritaary Containment and Reactor Vessel Isolation control system Trip Systems A and 5

^,pg pp,yg,s7 _T7, 7 j /g Isolation Initiation Channels gg gf g,g,4 Proces s Radia t ion "onitori ne Svs tem Building Vents, Steam Line, and

j

. Standbv Cas Trea teent Ef fluent

~

p fg-pf g, l Monttortng _

Residual Heat Rer.sval Svsten Heat Exchangees

/ 75' N g, /,d s

/

ps 77 g g, g-Piping and VaIves for 1

-low Pressure Coolant

).

Injection

/,- g p / E, /

Con ta itee nt Cooling

/.fsAf./.L. 7

' Shutdown Cooling

,p7

,g7-

. 1ns t ru=en ta tion

,rgp/ g,/) d,/

Controls and Electrical

/ f M j,/() 3// ffs f

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/

i RUR Se rvice *,?a ter Svs ten N

RHR Service k'a ter Pu=ps, Piping,

e U

and Valve _s _

_ _ _ _ / 7'd// /W. /r+%"a! $

i Controls and Elcetrical 3"IP**"'

... ~.

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4O Go r

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/rge/ A f d/g, _

r b*P*-.. -. -.. -..

,. /fAM J, j Insttu=entation pppsg. g99 y,,.o l'

F Controls and '

trical i

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Equipment. _.

/fS' A/ y,,7f

..s High Pressure Coolant Injection System Piping.and Valves Suction Line to Condensa:e s

/ fd? M N/ Ed S_t_o..r.. a..S c.

Turbine Stea= Supply and Discharge

,/tf' Ar J/, y Suppression Pool Suetion and e

Puep Discharge

/ r'g # J/. 6 N

j y g,,- _fy+

Pu=p y

Turbinc

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_. _ j g,*'#S /v / B>/.9 i

Controls and Elcetrical'Equipeent jgp-/g,p fj, s'f g e

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Pump

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_ Ins trumenta tion Controls and Electrical Ec;ui; cn:

_g,y/ g//;,g f5 r

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Isotaeion alves jfpfJy;/// g*

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Va ccu= B re a ke r 't.1 t ve s 4

Control Room ?anels

/7'2#d, //[. /

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...s f f M EN E */,/ -

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.a Renetor Feedater Suno!

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Exercisable Check Valves.

_ _ _ _., /75A(A ' /

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/72?d l/'//,5 j'/,/d Station Service and Cooling k*a cer Sys t er.s b

Those serving Engineered Safc-

)

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Electrical E y(; ent d'/ // /4 8, Q /4,// E.y.

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Electrical Power Sources Associa ted with Above' Sa fe ty Re-lated !.quipecnt-N F O 4/d & S # :P&C#C 6/EI

Vital Pouer Sys tems

__ _,,/ # f n f J X I'/,l/ $. N.'F f f

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l_fSAl 5NWl,.

Con t ro l 4 A uxi l b.- Foon v e l s. -"$

s f Excluding :;ucica r S:ccm Supp;,. Sjs:cci

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-v-r

.t TABLE 3.2-1 STRUCTU RES, SYSTEMS AND COMPONENTS CLASSIFICATION 16 (O

Ig)

IbI U** I II Y 9"'II'F P'I"8IP8I

,),

s<.. o r c.

A.....

con.t.

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4

TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPOffENTS CLASSIFICATION- (Cont'd)

Quality Quality (f)

Fr!nctpel(g) tel g

Scog+ of Group Assurance Construction Pr incipal Comge;nent ypg Location Cat egory Classification Requi r es=ent e Code Remarke g,,

10.

valves. main steam I

A S

IIPVC-1 laotatice valves CE C

11.

Valwee. Other. Leolation watwee n=d within E

C I

A B

III-1 th) 12.

Valves. in s t r urnen t at ion beyond outermost teolation valves E

R.T NA D

5 316.S (h) 13.

Mechanical M ules.

A ns t r ursent at ion, wit h ygg yQ CE C

I HA S

teone safety functton j

14.

Elect r ical m*utes with sa f et y f unct ten CE g C jN.p 8 I

ta 5

leone 15.

Cable, with safety function E

C.R.A I

ut to IEEE/10C/tlG-12 32 m

III.

Reactor Pecirculation Sy st em CE C

I A

S 331.7-1 (h) 1.

Flping y

t.,

2.

P ag e su s pe n s ion, M

rectaculation line CE C

I taA 5

E11.1-1 e

Y 3.

Pape restraints.

N rectaculation line CE C

1 IIA 5

Hone k

CE C

I A

3 NPVC-1 5.

Valves CE C

I A

5 NPVC-1 (h) 3 4.

Puw.s e CE C

I NA S

None 6.

Notor, pump 1.

Electrical ecoules. with safety functton CE C.R I

HA E

teone 8.

Cable with safety function C

R.A I

NA IEEE/ICC/WG-12-32 gg U

IV.

CPD Mydraulic Eyeter i %tv r-4a.a.sae r--

-til-W m

i C.5 1--

CE a

1 S

III-2 th) 3 a

r ewr.. 1.;.e 1.

Valves, other E

R 34A D

5-316.S th) 2.

valves g

0 La s

C i

3*

>=

e 4

isotes appear as separate list at end of table m

l l

TABLE 3.2-1. STRUCTURES, SYSTEMS AND COMPONENTS CLASSII'ICATION (Cont'd)

Oua1ity Oue1ity(f)

Principal (9) ten

,8' Scope of Group Assurance Const ruc tion g

Pr incipal Com!=onent Surply locatson Category Clas's a f scat non Re<nuaremente Code Remarke

4. --Mpanvr retw. eCr-1Lr w4thtvr 11UIsrtNU-

-t 0,0 i

a 1t ittwt-S.

Piping, scram discharge volume lines E

R I

e a

!!!-2 6.

Pigang, insert and w i t hd r a w lines E

C,R I

B B

!!!-2

-- 7.

Piping. other E

R NA D

5 831.1.0 th) 8.

81ydraulic control unit CE R

I IG S

taone (1) 9.

Elec*rical modules, wit h safety functton CE.

R I

HA 5

Hone d

10.

C alit e, with setety functiose E

R.A I

laA B

IELE/ICC/WG-12-32 V.

StarwSby Liqu!J Control System 1.

Standby liquid control tank CE R

I D

S API 650 (q) 3 2.

Ptsy CE D

I C

S HPVC-2

).

Ptaap sautor CE R

I t:A 5

Home T

4.

Valves, emploalve CE R

I C

S HPVC-2 RJ S.

Valves, teolation and I

within E

C.R

'l' A

B III-1 (h) y (f) 6.

Valves, t>eyond leolation valves l'

R I

C a

181-3 (h) 3 7.

Papang, within isolat ton valves E

C.R 1

A B

lll-1 th) 8.

Paping. t< yond toolation vatwes 1:

R I

C D

111-3 (h) 9.

Llectrical etxtules, with Q

safety lunctaor CE D

I ttA 5

ta ne o

3 10.

Cat.n e. wath saf et y function f

C.R.A I

NA B

IEEE/ICC/WG-12-32

// Ac'C WMt.iUNW 4)s A

5 (E

VI.

taeutron Monitoring System o

3 1.

B'n g ang. TIP C[

R I

e 5

331.1-2 2.

Valves, asolation. TIP s utes y st em GE R

I in 5

NPVC-2 y

3.

Liettratal esmiules. I Pr*

I an.I Al Ptg 01, t

I taA 5

None 4

Catet e. tem and APRt9 E.

C.P.A I

taA 3

IrtL/ICC M )2

$, ym ygg/M&Ds!7s#W fDW$

m ists.w MwnM*mh h5 g

I NA 3

Coxr&L j m Jggasdct (b

-uMff'

~

Notes agag ea s as segia s at e last at end of t alet e As 1.

$l

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3 3

3 3

2 1

1 G

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CC tud C

t I

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~

C.

2 14

./

I C

a I

1 2

4 Ce

- e r

8 3 vn 3 e I n nr s L o

3

+

I o ot r.

f a

3 3

.e 3 s I i ps I

s t T 3

3 l-l I

I I

a as8 BB 8S sa L

I c

1 a

A A

AA s

<~

B C

A eM Ag at i=

1 r

u i

A.

h_

w I

I I

I I

I I I I a

i s

]

~

r e

k,a.

c C

CC n.

n m

m m.

aa a D

a o

a.R N'

a 6

w N"

e I.

gE t

E E

eE r r 1

C C

t E CC r

rC ca s

a, e

p su iu M

a m.

r D i

a FC n

m e

d _

AM t.-

A S

d J

X' f eW o c

n e

. (J Tm i t.

s n

e s.

n t

o

( *s c

t f, "o o

/

n t

f - ~e t

A s

/

m y

- s -.

o

'a nr s

s e s.

/

j. o t.

e v e.

n J n. lo e oiy t

t l t t e

uo we e

e et t

/

7s v.

e t

s ov ov oOon u.ct t n e

[

oe

- r r e nnd n t

• e t d d a.s o

or e

~

ono o t" e n e e ed i m g e gn h i ot t s l

o m.

yh e.

o /, o y ad aet t yt e

e e e l t t t t. i e i s e e r

ah sh y wn bt ot

.t b

e o es e c c e o

,o n et s, s ae e.

t n

ecf =

n a ys s

,o e

a

.8 t s e es ed gt gt a

t a

nn n

e.

e oe eet e

t pw8

.v vh c ht t.

e t mt ea t ipe m

oie%hW1es.l aml =C e.

o al e c rs e l Ct l c et n d e a e sa o

a e l mpM eP mP m WW v

E e

t e.

s1 2.

3.

4.

s47.

e1 0nf2 1 an1 O

G 1

d' I

I M

h S

I PO 9.J 2*

I h

s (f

P-TABl.E 3.2-1 STRUCTURES, SYSTEMS At3D COMPOtll:llTS CI.ASSIFICATIOli (Cont'd!

Watity Quaktty(f)

Principal (g)

(el 5< og-e of G r oug.

Amourance Constructioen I.acat ion Category Clasaltication Re<gui r esnen t e Code Res6erk e Pr ine npal C&gonent g ylt R.

Core 5psey 1.

PLpang, within outerwest isolet ton valven E

C.R 1

A B

I!!-l (h) 2.

Ptemng, tcyond outesumost t sot at scwo valves L

R I

B B

III-2 (h) 3.

Peps GE H

I n

S HPVC-2 4.

Fwp mto's CE P

1 t4A S

Hone S.

Yelves. asolation and within E

C.R 1

A S

I!!-!

(h) 1 6.

Vatwes. t eyond outemost isolatnon vatwes f~

R I

B B

III-2 (h) l 1.

Elect r ical solut es wit h safety functnon Cr R

I NA 5

Hone 8.

C at> t e. wit h saf et y f unct ion E

C.R.A I

ttA B

ILEE/ICC/WC-12-22 ITI

.' SU. ANWf[df,/NMfL//Y ffg,.MMT gg 3

Q ggg$

g 21.

High e Gav ant Injection 1.

St ensa turbine CE R

I IIA 5

Hone

())

)i y

2.

Pagang, suction line frte condensate st or age tank E

R.O 1

8 9

111-2 (h) 3 (f) p 3.

P a g'i ng. t us ta nne steam supply R

I B

B III-2 y

and d a schange E

4.

Partng. return test line to i

cosidens et e storage tank twyund s e c oswl tsoletnon va1ve r

R.O I

D 5

831.1.0 y

5.

Papang. within outermost isolation valve E.

Ch I

A B

III-1

)

6.

Papang. a ugagir e s a lon 3.o01 euct ton and pep dte(haroe E

A I

B D

III-2 th)

CE R

I B

5 NPVC-2 7

Main gwp CE R

I B

NPVC-2

'f 9.

Pwste pus p 9.

Valwes. t.eyond outerm et anotatson walven E

P I

B B

I11-2 a

10.

Vanwen. cater asonation

)

E C.R I

A B

III-1 (h),

and = tt han Notes appear as s'Israte tiet at erwl of table

. ~.

TABLE 3.2-1 STRUCTURES, SYSTD1S A:JD COMPO!1E:2TS CLASSIFICATIOtl (Cont'd)

Quality Quality (f)

Principal (g) tel Scope of Group Assurance Construct!orn Pr inc t 'a l Cesagaent,

_sugy ty,,

tocation Ca g g Cl a s a l f ic a t ion Requiremente Code Remarke i

11.

Vanwes. teyond isolat ton vanwee. mt or operatest E

R I

h B

III-2 th) 12.

E l ec t r ica l menlutra, with safety function CE A

I NA S

Hone 13.

Electracal aunt!!ary equigeent CE A

I ttA 5

Hone 14 Cat.le with saf et y f unct ion E

R,A I

t4A B

IEEE/ICC/WG-12-32 Ut son (f ing U % 'I Y

WNQ~

f q$

g f

gggg onl XII.

Peact ae Systee 1.

P i gs t ng, wit hin outermont isolation walves E

C.R 1

A B

III-1 (h) 2.

P a gi a ng.

t+ yoekt out e s mon t isolation valven E

a I

B B

!!!-2 th) 0Q P1 ing, return test line 3

).

3 M

t o ceindens at e storage tank b

t,e y on.1 second luolatton a

valve and vacuur swp y

d a nc har ge line t o con-(f) tanneent isolatten valves E

P.O.A I

O S

B31.1 (hl

)

4.

I'ung s CE A

1 8

5 tiPVC-2 3

5.

Valves, isolation e rwl within E

C.a 1

A B

111-1 th) 6.

valves. Other E

p 1

a B

III-2 th)

MOW CE A

I HA S

Hone (j) 7 Tusbane 3

6.

E l ec t s ac a l awwtu t e s wit h h

saf e t y f unct ion CE A

1 NA 8

Hone (L

9.

Cable, wit h saf et y f unct ion E

p.A.O 1

HA IEEE/ICC/WG-12-22 l3 3

10.

P agateg, es.ctLon inne f e ten conden. te storage tank E

m.o I

a a

III-2 th) g 9{

// MceW. MODx/LCS, tA/37x' WM/ %'f67V fc4vic'noh W A

f WA 6

4/p/g Hot.e.i.e.ar a.

s e pa r'a t.

ii.t at end of tabt.

u C3 C

O w

4 (h

s.

i TABLE 3.2-1 ST11UCTUllES e SYSTEMS AND COMPONENTS CLASSIFICATION--(Cont'd) i sel are tel

'I-I P*

Ibl Sce64 of Cs oup.

Aneusence ConetcuCLIOR g

g Fetaci d geronent 3rly tecetton Category Clees t f ac et ton Requ a r enant a Code Damarke Eltt.

Fuel Ses w ace Equlgeent

1. Fue t gss epos et ton esechine CE C.S I

tea I

gaone

2. Gene s e t pus gene ge ogy t e CE C.A I

NA S

gwone I

Elv.

Reactos tueseuse Veneet Segwnce Equtgeent

1. Steam IIne Estuqe CE C

I gen 5

esone 2, Deyes en4 seposetos ellag se=S head ot songt ec h CE C

3 m

S peone KV.

In-Wesset Seewise E*3= Lgment

1. Conteet so.1 gsegyle CE C

I MA E

enone e

NVI.

De f ue I kng E qu t g=nent

t. Pefuellva egutg=ent

.g 4.J plotform e s e e=d> t y tE C

I sea -

S Mone 2.

metuelseg tiettown E

C 8

m B

$8t-2 Kvtl.

Stosege E qu a gment e

[

1.. men e.use,. v.cm.

CE C.,

t

.A r

mon.

T1 2.

Defett4ve fuet e t os age y

4 comisines CE A

on.

.T svtII. moowe ss e system Art.(Se s t.

Tante. et m sphesic weseets E

w kA C.C 5

113-5 4 S.96.1. VIII

2. Meet eachewies e end vist &

e.egesetose E

w W\\

C.D 5

TIP.A-C thi

).

Ptplag erwt wolves I

C.S.w M4 C.O 5

335-3.811.1.0 (kl e twve E

w M4 C.O 5

118-3.938.1.0 th. kl

%. Votwee. contetswent 4

teolotton E

C.R I

B III-2 th) 1 6.

Vetwee.

fa. controt o

end fattes synte.

E w

MA C.O 5

III-3.831.1.0 thi esot e s e61g e s se segesete test et end of table i

i 4

a l

9

~

t TABLE 3.2-1 STRUCTURES, SYSTEMS-AND - COMPOWENTS CLASSIFICATION ' (Cont'd)

~

. Quality 'I Quality Principal I

I8I Scope of Group Assurance

-Construction Principal Congenent Supply location Category Classification Requirements Code Remarka 7.

Valves, other E

W EA D

S B31.1.0 8.

Mechanical modules E

W NA D

S None (k)

KIX.

Reactor Water Cleanup System 1.

Vessels: filter /

demineraliser CE R

NA C

S III-3 2.

Heat enchangers, regenerating GE R

NA C

S III-3 TEMA-R nonre9enerating ltubeside CE R

NA C

S III-3 TEMA-R ushett side CE R

84A D

S VIII TEMA-R l

3.

Piping, within outermost isolation valves.

C.R I

A B

III-1 4.

Piping, beyond outermost isolation valves E

R NA D

S B31.1.0 (h,1) 5.

hanps CE R

BJA D

S HPVC-3 (1)

(yg 6.

Valves, isolation valves y

]

and within E

C.R I

A B

III-1 th 1.as) 3 y

4 7

Valves, beyond outernost CE R

HA D

NPVC-3 (h,1) f()

isolation valves E

R NA D

S B16.5 th,1) j 8.

Mechanical modules CE R

NA la S

lione (it,1)

-g g

i a

p XX.

ruel Pool Cooling and Cleanup y

System 1.

Vessels, f ilt er/ demineralize r s CE W

4A C

S HPVC-3 2.

Vessels, other E

W NA tlA 5

None 1

3.

steet exchangers CE R

84A C

S VIII TEMA-R j

4.

Piping E

W.R t.A C

S III-3 (h) g 5.

Pumps GE R

!!A C

S NPVC-3 (h)

U 6.

Valves E

w,k IIA C

B III-3 (h)

O.

9 g

xxI.

t'ain Control Rour Panels D

1.

Electrical modules, with safety f unction CE A

I HA B

Hone 2.

Cable, with safety function E

A I

NA D

IEEE/ICC/WG-12-32 g

I C4 C

D G

Notes appear as separate list at end of table g

w

~t Os i

3

)

r

~ - '

2-.

__u

4 TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPONENTS CLASSIFICATION (Cont'd)

Pstactp.1(gl tel (fl Qu.14ty Ou.ttty Scogw of t.s <*up Assue.nc.

Con.truction r.

c a e t Cm>*'m.

5=rrir t-at t a.a cm r>= r ca.. 48.c.ttoa

• .sute.

at.

Cod.

m a.rke r

mani.

toc.t e.n.t..a r.cm.

a.

rt.ct.tc.i nod.t..

cc m.m.w I

na s-e.on.

.itn..r tv ronctton t

m.m.w.m B

un a

woa.

==

a sere / scc /wc-12-22 i.

c.ui.... a..r.ty e ction r

e.a.w.n 11111.

Off-C.. Sy.t.a 1.

T.nk.

E T

MA D

5 vit!

V 4 I I.TEs*A-C 3.

M..t

..cbang.a.

E T

MA O

5 858-3 3.

Ptplas E

T hA C

5 m31.1.0 E

Y NA C

S eson.

Pg.

S.

v.tv...

flo. contson E

T MA C

5 soon.

4 v.tv... Oth.t E

T NA C

5 Mon.

7

h. c h.n l e. t.=wlu t...

.Bth..t.ty reactton r

T na ma s

soon.

e.

r.....s......

E r

ma o

s want M W W).EN N m#Ths-mA w 3A m ~3 Jgt,L -

[Tl i

7) n Iv.

ann s...tc. w.t.: synt a

C e

sas-3 e

a.

rtran, E

n.o.m E

n 1

C o

318-3 M

y 2.

ro r.

e E

N I

MA D

gaon, T

FJ 3.

r w emotor.

181-3 4

e.

v.tv..

E se.a a

C a

S.

En.ctate.

Deudu l...

V'

.ith..r.tv s.ctton E

n a

na m

non.

s.

c.et..

stm..e.tr roact ton a

n.o.m a

un a

trer/ scc /uc-ta-sa 33

.6t629 ypgg 2/M& d/MLb W F.t.r}7,g 6 g

3 g

6 sPh.at s.cvic..na coonan, w uv f

Ey.t.==

(

1.

Paptag.no V.t..ra secmittg p.st of pain.sy cev.taina.nt k,oeM.sy E

C.R I

B B

151-2 t

t a

3 i

4 foot...m r.... g'. s. t. St.t

.t.nd of t.bt.

g i

a a

V I

1

fh

/*'%

t'%

Pi d

TABLE 3.2-1 STRECTURL:S, SYSTEME AND COMI'O'IENTS CLASSIFICATION (Cont'd)

/

Quality QualatyI Principal Scoge of Group Assurance Construction Pr inc E g a 1 ( osag.3nent

_{o, ggj{,

gwat um

{aj e,<ggy' Classatscation pequ i s eraen t a Code Remarks XXVI.

I ns t ruraent and %esvece Att Sy st er 1.

vessets, accur=.latore.

aug ter t in.

safety-aelated syst ems F

C.P I

C B

!!!-]

2.

Passng and valves an lanes tetween eleve ac c umu l a t or s and s a f e t y-r el at ed syntces E

C,P I

C-B 331.)

5 k

l l lll

• fl

{

6 4.

dk>l Ou C

r,h E

B R B,'s u.i t

m f-

~

V r

sw a

c n

1 y

s -s m s o % % d a /a b u dp 1

1 B

s ->

y Yr: Nn a 7cq & G f F

nf 5

B K

9 9'6. '// + ) # M A &< g A'f I

f}.

swG F

u ng s, A;.

ii 0

/04 44 modbs L

hf 3

0 y

.gsre y3

_ _~

'l

/)

./ -

/

f 4

i t

4 XXVII.

Diesel-Cenerator Systems 1.

bay tanks r

et I

C B

III-)

7.

l' aping and watwes. fuel oil snsten and onesel servate wates s y st em E

tt I

C a

III-) (see rig. 9.5 2) 3.

I'ums s. fuel ont systec D]

and diese* service g

3 'T1 water system F.

It I

C E

III-3 tese rig. 9.5-2) y 4.

Fuet ont syntesi s.

It i

C b

t.one (see rig. 9.5-2) y S.

ruer rotors. diesel T) m service water s y st em

[

18 l'

t.'A b

Hone (f) 6.

Diesel-generators E.

6 I

t. A B

S k>n e p

7 E. l ec t s s c a l owxtu l e s wit h saf et y f unc t ions

[

lt I

stA B

kone 6.

Catite, with saf ety functtons E

St. O. R I

flA B

!((E/ICC/lfG-12-32 REVIII. I t amary Cont a6nment Atrw3sg her e Cont ro! S y st em 4.

I'aring and valves is om g-r Eme r y c on t a i reer t throuct.

g est e r teolatta walve f

R I

B b

III e G

.3 RXIR.

a.andby Sas Tseetrent System 6

g 1.

ouct ena vanwes estreme o

y of ftiter untte pd4d M M.

p fg. EMET IA '-@

r R.A I

O 9

311.1.0 p

p,_

• !! ahs c r;- d E

A 1

tlA

[

Mne dOObNf b

b 1

i, 3

r-f ase van e

e 7

gg P3

P

4 150tes opg eae as seg=ar ate list at end of table iO i

i K

v

-T

di N

3

' 'Y h

i N#d li

%4 (3

?

I.

j {

w

. g t

+h no O CQ f

1 kA a

as e

e<

d GEQS O

',i.

4

.)

P 4

3 me 1

t s

W y._

y R

3 is [q

. ~

ea n

4 N

s e

a s

y

.X X

^

h 1

l h

h h

h

?

t TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPOtlEllTS CLASSIFICATION (Cont'd)

I Quality.

Qua11ty Principal Scope of Cs oug>

Assurance Construction' Principal Cwgaent p lyly Location Category Clasenfication paquasemente Code Remarke 8

RXR.

Wr9ency squagment Cooling teate r Sy st een 1.

All cmponente utth safety functions E

D I

C D

III-3 RIRI.

tre s g e ssc y Co r e Cou t ing System Equigewnt Asea Cooling System. H"/AC I.

All c mg w ents with safety function E

R.

I C

E tese Table 3.2-2)

KER11.

Pp ses Conwet a ton System 1.

Main steam papang to 7g4cW

//f//

tu.'. i --

teca C

p.T I

O 5

931.10 (a) y gy I

O S

331.1.0 (al "T1 2.

5 s pie. 3 m e.J walvca, saa t n Laaartwo //9 N N /

p.T

-S-

"3&rk u a t e ssi

=

-T J

/

E k.T esA D

5 831.1.0 (n.o)

IV 44

-) &Ne t..

.-t.ine-*We tve s

~ j.

Feedwates papan3 fyp4fp Y

KERIII}. Condensate /M6t'nq /Jobra44Qt, /ff Stoseqe and p

1.

Condensate atosage tank E

O HA D

5 USAS B96.1 (pl

-J Transfes System 2.

P a pasu; asw1 valves E

to NA D

5 B31.1.0 E

M sah D

S (see Table 3.

Other cwgment s 3.2-2)

RKKtV.

Aun t! L ar y AC Power Syst emt a

1.

All ceg=snents with omfety fun (ston E

A B

C D

IEEE-)OS 2.

Primasy Electrical E

D I

C B

1 Li~E - 3 44

]

Pessetsatnons sin-Hc.EEE-317

{!rhemvs/Ee /@ M,

g

/

1. <ruw oo.nruoq C'

Ce C 1

b 3 -l Uots n ev vs uc

/,$df./ 7Yd Y

( V/WK$

1 yxtv6 Aw itn'41/

E C,(

~5.

g y

y u) gaws, e,;.vis nrxv.y P, l(,, i F

P-r it6 7

TABLE 3. 2 - 1.

STRUCTURES, SYSTEMS At3D COMPONENTS CLASSIFICATION Qu. atty Qu.11ty" Patacap.1 scopo et Csoup As.ur.nc.

construction

...ci,.t cm

.t asiy_

tu.tio.

cason ca...iet<.ii.,

.u s.....

coa.

a.

W.~ /Piro Dnq 06 PodM [Costf) j)

Diesel generator packages including auxiliaries (e.g., lobe sys ten, jacket cooling, air s tart sys tem, governor, vol tage regula tor. - exci ta tion sys temf Agreat E

t4 E

NA awo xwy /csrccrsort rewpmay)

($

li) 4160 vol t switchgear.

E. -

A,H

(

s4 s

() 480V load centers.

E 8,14 K.

NA 5

d) 480V motor control centers.

E O.f,N 1

M b

1p)

Instrumentation, control, and power cables (including under-ground cable system, cable splices connectors, and terminal blocks).

E.

ALL t&

d4 3

[)

Conduit and cme trays end 15.dr supports.

(Ins talla tions containing class IE cables and other installations whose fa i l ure may damage o ther s a fe ty-re la ted i tems.) E.

AK y

blA-6

) Trans formers.

E A. A K

4A S

t) Valve operators.

~

4 gt

.T-S l

):

Protective relays and control panels.

(E -

14 I

q QA S

AG-controlzpower :inver_ters

,3 120V AC vita 4 Mstw' S'M'VMU msav bus dis tribution equipment. E A

f HA 5

3 74 P RE.

.n ops F_

AtL I

MA 5

p 4

TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPONENTS CLASSIFICATION

~

Quattty Quality Fri.ncipal Scope of Caoup Assurance Construction Principal Cuesenent AQ location Categosy C144618Acattoes me.nu t r ement a Code Ammat tia 1

U 3xnw.

DC Power System (1

g, Ag g cegan.ent s se tt h g

C D

s a f et y f 4ac t ion sgyrd nWLi dc a) 12SV batteries battery chargers a andgis tribution n

equipment.

E ft k

MA 6

b)

Cables.

~ e.

A-

'k_

+4A

.5 c)

Conduit and esWe trays --' M supports.

(ins talla tions containing class 1E cables and other irs talla tions whose failure may darr. age other safety-related itecs.)

C.

ALL 3-4-9m.

WA.

S 4

w

.4 e

1 i

)

1

s.

t 6

TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPONENTS CLASSIFICATION 4

I III '

N Qualit'y ? '

'Oma'tity talacapa!

gg Scop

• of Gaoup Rasusmace Cosmetruction

)

Principeh Commenentg,g gg,-

gg, sugply tocatton Categosy Claeolflet1Aun Requiremente Code Amunasha 1

RRRWI.

Civl! Structuses 4-

- 1.

Psamasy containment r

-P 1

3-3' 1II B '

4

' 2.

Prac t or ' mus t+ Sing (including O"

f ene t stor age f ac alities)

F D'

I taA B

ACI.)!$. A15C t-*

W Mot es al 3 ear as segarate list at end of tatste 4

m e

4 t

T I-t 4

1 2

f

.t 4

J t

t i

T i

f 4

8 i

5 l

i'

f TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMPONENTS CLASSIFICATION (Cont'd)-

Qualit y

,Ne l a'a y Fanncipal Scos* of C a nus-As eus em e Conetsuctica Code Demerka C

Closeaf ar et non D ogs e ****.t e Principet Coogenent sug gjy_

lexetnon y33_

3.

Asentaesy tulldlag i

A 1

esa a

ACI lie, AI6C

.. med e.te.. tiding

=

a

.s Act 31.. AlsC 1

S.

C ha c ulat ing Wate s 1

P MA eth E

ACE 318. AISC F as-acouse 4.

Cont sul Cent er (W es Ilm kudlng c atste el+sendaag E

A I

eth 1.

see n Coal > t e e E

3*

I un a

ACI 310. ASEC soumi ExKVII. Poet LDCA toydsween Control Systee 1.

All contenent e with eefety runction E

R I

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853-2 RERVIII. keector Dolldisvg Crone E

P I

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OtAA* 70 g

RERflI. Cont eel Center Alt y

1 Conditiontag Systes 1.

Condenees coil and E

A I

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,eeencleted pip &ng 3.31.1.0 2.

(hllied wates piping E

A B

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$es 129 3

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3 II O

)

Hotes appear as seg,arate list at end of table.

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d TABLE 3.2-1 STRUCTURES, SYSTEMS AND COMIf0NENTS CLASSIFICATION tbl I

Senpo of g,

Group Assurance Comet s uct ice es tacapel Cemenent 1Q Location Categosr Claselftcetton m=quiremente Code Remarke 5IV leakage control system

)

Piping, within RCP3 isolation valves.

E.

A I

A s

3-1

)

Piping, other ups tream sys te, lir.es..

E A

1 C.

5 m -3

)-Pi p i n9 r-de-wnsr treant-systerf ron-s t eaml i ne--6

.]

. I D-S

~B3E' t-i H--Pipingr-ether-4 owns t-reemeyste t-4nes.

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)

Valves, within RCPB.

E A

1 A

S JII. - l l

) Valves, other.

E A,-

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IrB4ewt'rs.

>) /YK /*- o w tX e 5, s N,5T A UtiE4 M f!* d WirW S&rs Q /~udcisod t=_

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TABLE 3.2-1 ST11UCTURES, SYSTEMS AND COMPONENTS CLASSIPICATION s

NI NI Quality Quality prtacape!

sew. or c.a.ca.: cm-t,,,

_s.nin -

w u oa,,,

g,

c. w a...r.ac.

coa.sr eu o.

r c.t.,or r ca...utc.taon

=2.u - t.

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POST Acciokdf san l'L4NL]

b

8) 6 amp (.G T oLAruQ ynLVE5 4

l f IPIN61 g

g

.I g, g 3

3 -i, 3

2. 64spt:IJQsTAwdi 106lMQ 'DotdsMTES

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b 5

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e a

e 9

e 4

m.__

7 m.

m..,.

f 3

4-

.n..

EF-2-FSAR.

1

. 'yl.j.;.?,i-r O_

' TABLE'3.2-1 STRUCTURES, SYSTEMS,-AND COMPONENTS

- CLASSIFICATION-(Cont'd)

Notes I")A module.is an assembly.of interconnected components which constitutes an identifiable device or piece of equipment.

For example, electrical modules' include-

. sensors', power supplies,.and' signal processors:

and 3.

mechanical modules include turbines; strainers and-orifices.

(b)GE = supplied by General Electric i

i F

E supplied by the Detroit Edison Company

=

(c) Location abbreviations - are :

A-= $uxiliary Building 4

C = part of, or within, primary containment L

H = RHR complex-v i '-

M'.= any other location

{

O = outd6 ors onsite-

~

P = Circulating Water Pump. House

?

R = Reactor' Building r.

T = Turbine Building W = Radwaste Building e

(d)I = The equipment is constructed in accordance with the seismic requirements for the SSE and OBE as described l

.in Section.3.7.

NA = The seismic requirements for the SSE are not applicable to the equipment.

(*I The structure system or component is constructed'in

[

'accordance with the codes listed in Table'3.2-2.

t i-(f)3 = The structure system or component meets the OA requirements of 10 CFR part 50, Appendix B, in accordance with the QA Program described in l

i Chapter 17.

-_ _. ~

l1

)( =. The ' equip..cnt - is construe:cd in acccrda..cc with the scisiaic requirements as iescrd:cd in Section 3. l o c

j l.

~

k w

3.2-19 E

..e,.

EF 2-FSAR TABLE 3.2-1 STRUCTURES, SYSTEMS, AND COMPONENTS CLASSIFICATION (Cont'd)

S = The structure, system or component meets the QA requirements defined in the purchase' specification.

I9) Notation for principal construction codes are:

III-A,B,C,1,2,3 - ASME Boiler and Pressure Vessel Code,Section III Class A,B,C,1,2, or 3 or Subsection NE, Class NE (Pre-1971 versions of the code used the Class A,B,C,' designation while 1971 and later versions used the Class 1,2,3 designation.

Equipment was ordered throughout a period requiring use of both designations.)

VIII - ASME Boiler and Pressure' Vessel Code,Section VIII, Pressure Vessels, Div I.

B31.7-1,2,,3 - ANSI Nuclea" Power Piping Code Class I, II,III.

B31.1.0 - ANSI B31.1.0 Standard Code for Pressure Piping, Power Piping.

[

NPVC - 1,2,3 Draft ASME Code for Pumps and Valves for Nuclear Power, Class I,II,III.

IEEE 308-1971 - IEEE Criteria for Class IE. Electric System, for Nuclear Power Generating Station.

IEEE 317-1971 - IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations l

IEEE 344-1971 - Guide for Seismic Qualification of

^

i Class I Electrical Equipment for Nuclear Power

{

Generating-Stations.

IEEE/ICC/WG-12-32 Proposed Guide for Type Tests of Class I Cables and Connections Installed Inside the Containment of Nuclear Generating Stations TEMA-C,R-Tubu ar Exchanger Manufacturer Association,

' Class C,R AC1 318 - Building Code Requirements for Reinforced Concrete 1963 and 1971 1

~

1 l

I 3.2-20

i

.w

\\

EF 2-FSAR i

-TABLE 3.2-1 STRUCTURES, SYSTEMS, AND COMPONE!TS CLASSIFICATION (Con t ' d )

AISC - Specification for the Design Fabrication and Erection of Structural Steel for Buildings.

1 API 650 - Welded steel tanks for oil storage.

API 620 - Specifications for Welded Steel Storage Tanks.

B96.1 - USAS B96.1 - Welded aluminum alloy field-erected storage' tanks.

B16.5'- ANSI B.16.5 - Steel pipe flanges and flanged fittings CMAA - Crane Manufacturers Association Standard 1970 (other Civil and Structural Codes are given in Sec-tion 3.8).

(h) l. - All instrumect lines which are connected to the

. RCPB 'and are not utili:ed to actuate safety systems are Quality Group D from the outer isolation valve or the process shutoff valve.(root valve) to the sensing instrumentatioq3 2.

All*other instrument lines:

through the roo't valve; shall be-of the o

same classification as the system to

)

which they are attached o

beyond the root valve, if used to actuate a safety. system:

shall be of the same classi-l fication as the system to which they are "

l attached l

o.

beyond the root valve:

if not used to actuate a safety system, are Quality Group D 1

3.

All sample lines from the outer isolation valve or the process root valve through the remainder of the sampling system are Quality Group D.

i (i)The hydraulic control unit (HCU) is a GE factory-assembled I

engineered module of valves, tubing, piping, and stored water which controls a single control rod drive (C RD) by l

the application of precisely timed sequences of pressures and flows.

. Control is accomplished by slow insertion o

or withdrawal of the control-rods for power control, and rapid insertion for reactor scram.

3.2-21 u

- -,_