Text

Forwards Addl Info Per Equipment Qualification Branch Questions 270.1a,1c & .8 Consisting of Tables Listing Principal Component,Safety Function & Safety Class
	ML20083J815
Person / Time
Site:	Perry
Issue date:	01/04/1984
From:	Edelman M; CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Youngblood B; Office of Nuclear Reactor Regulation
References
	TASK-2.B.1, TASK-2.B.2, TASK-2.D.1, TASK-2.D.3, TASK-2.F.1, TASK-2.F.2, TASK-TM PY-CEI-NRR0084L, PY-CEI-NRR84L, NUDOCS 8401100323
	Download: ML20083J815 (42)
	v • d • e

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S4 it u P O. BOX 5000 -. CLEVELAND. OHIO 44101 - TELEPHONE (216) 622 9800 - ILLUMINATING BLOG.

- 55 PUBLIC SOUARE Serving The Best Location in the Nation i

MURRAY R. EDELMAN VICE PRESIDENT NUCLEAR January 4, 1984 f

PY-CE1/NRR-0034 L I

I Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission l

Washington, D. C.

20555 l

I l

Perry Nuclear Power Plant l

Docket Nos. 50-440; 50-441 l

Equipment Qualification Questions l

Dear Mr. Youngblood:

l During a meeting on November 1, 1983, with the Equipment Qualification Branch (EQB) the NRC staff requested additional information on our response to the EQB questions in your letter dated March 23, 1983.

l Enclosed is the additional information requested for questions 270.la, 270.lc, and our response to question 270.8.

This letter and its attachments finalizec the responses to all questions f rom the March 23, 1983 letter.

l Very truly yours, h

Murray R. Edelman Vice President Nuclear Group k

MRE:kay Attachments cc: Jay Silberg, Esq.

John Stefano Max Gildner Q. Decker, E.G. & G. Idaho 8401100323 840104 PDR ADOCK 05000440 A

PDR l

\\o 270.1.

Based on the informa'.on contained in Section 3.11 of your FSAR we are unable to determine if all essential systems and components have been identified and included in your harsh environment qualification program. Provide the following additional information for our review:

A comparison of the systems in Table 3.2-1 of the FSAR with the a.

systems included in your October 25, 1982 master list.

Justification should be provided for the exclusion of any safety-related systems (e.g., all components of the system are located in a mild environment, system is not required for accident mitigation, etc.) Identify the class lE function (s) performed by each system.

b.

A list of the TMI Action Plan equipment which you have previously committed to qualifying by fuel load in the format provided in your October 25, 1982 letter for safety-related

~

equipment.

A list of safety-related equipment located in a harsh c.

environment which has been exempted from qualification for harsh environmental conditions. Individual components in exempted systems need not be identified.

d.

A list of all essential equipment in a harsh environment (i.e.,

NUREC-0588, Appendix E, categories 2a & 2b) in the format of your October 25, 1982 letter.

Certain equipment, such as terminal blocks, splices, and cable, are not currently included in the master list of equipment.

l l

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4

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T l

270.1 (C:nt'd) i.

Response

t The " October 25, 1982 mester list" was a sort of all class IE equipment in the Equipment Qualification Review List (EQRL). The EQRL (see Section 3.11.3.1) is a continuously updated computerized data base for all safety-related electrical and active mechanical equipment (as defined in Section 3.11.1.1) in both harsh and mild environmental zones.

The EQRL also provides a column label "EC" for equipment category. The EQRL legend pages provide exact definitions for equipment category per NUREC 0588, Appendix E as follows:

paragraph 2a is A1, paragraph 2b is A2, paragraph 2c is A3 and paragraph 2d is A4.

As stated in Section 3.11.1.1, Table 3.2-1 is the basis for the EQRL.

a.

Attached is a copy of Table 3.2-1 which has been modified to:

1) demonstrate correlation to the EQRL, 2) identify the class IE function performed by each system, in terms of the six safety functions listed in Section 3.11.1.1 items a through f.

Justification is provided for each line item of Table 3.2-1 which is not in the EQRL. A c arrent copy of the EQRL sort titled " Safety-Related Equipment Identification and Environmental Qualification Summary" is attached to the letter transmitting these revised responses, b.

TMI Action Plan (see Appendix 1A) hps been rev.iewed and the following is a list of safety-related equipcent which has been committed to be qualified prior to fuel load.

The MPL Numbers are listed as in the EQRL sort submitted in a) above.

App. lA Item Equipment Description MPL Wumber a

II.B.1 Safety Relief Valves B21-F041A-C, K (existing equipment)

B21-F047B-D, F-H B21-F051A-D, G II.B.2 All PNPP safety-related electrical and active mechanical equipment is qualified to radiation doses in accordance with Regulatory Guides 1.3 and 1.4.

270.1 (Cont'd)

App. lA Item Equipment Description MPL Number II.D.1 Safety Relief Valves B21-F041A-C, K (existing equipment)

B21-F047B-D, F-H B21-F051A-D, C II.D.3 SRV Position Indication IB21-N410A thru V IH22-P090 II.F.1 1.

High Range Noble ID19-P300, ID19-J300 Cas Monitors ID19-P400, ID19-J400 1D19-P500, ID19-J500 2.

High Range Gamma ID19-N100A,B, ID19-J100 Nonitors 1D19-N200A,B, ID19-J200 3.

Containment Pressure ID23-N270A, 8 Monitors 4.

Suppression Pool Water IC43-N090A, B Level Monitors 5.

Containment and Drywell IH51-P022A, B Hydrogen Monitor II.F.2 No additional instrumentation is required.

The EQRL, which is sorted on equipment category A3 (NUREG 0588, c.

Appendix E, paragraph 2C), provides the scope of equipment in a harsh environment exempt from qualification for harsh environment.

A copy is attached to the letter transmitting,these,.revi. sed responses.

The basis for justification of these exemptions is discussed in attached revised Section 3.11.2.2.2 Qualification Analysis.

d.

The EQRL, which is sorted on equipment category Al and A2 devices, provides the required list of NUREC 0588, Appendix E, category 2a and 2b devices.

A copy is attached to the letter transmitting these revised responses. Equipment such as terminal blocks, splices, and cable are provided on a separate list which is also attached to the letter transmitting these revised responses.

--,--7

1

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h.

The expected inservice maintenance procedure and schedule.

The qualified life will be expressed in the most purposeful terms for the particular application.

Justification is provided in the qualification documentation of the means used to estimate the qualified life.

3.11.2.2.1.7.9 Service Conditions For the aging program, the following service conditions are used to determine the contributing factors for the equipment qualified life:

a.

Normal service conditions.

b.

Abnormal service canditions.

3.11.2.2.?

Qualification Analysis Analyses are used for environmental qualification when such analyses can be shown to be conservative.

In general, qualification by analysis is limited to simple constructions and used to supplement the type testing (discussed in Section 3.11.2.2.1).-

Such analyses, performed for full environmental qualification or to supplement the type testing, are justified in the test plan, test specification, or qualification repo,rt.,

Class 1E or active equipment, classified as safety-related either by association or because it is in the primary pressure boundary and not required to function to mitigate the consequences of an accident, may be exempted from qualification for harsh environment conditions by analysis of the possible failure modes present when subject to that harsh environment.

Each of the possible failure modes is identified and analyzed to determine if it has an effect on performance of the safety functions of other safety-related equipment. For pressure boundary equipment analyzed in this manner it will be necessary to qualify the pressure boundary function as discussed in Section 3.11.2.2.5.2.

b 3.11-21

-y e

-s s.-

4 3.11.2.2.3 Operating Experience Operating experience, if available, serves as a basis for determining the qualified life of aquipment (e.g., systems or elements, components, modules and other constituent parts of systems).

IEEE Standard 323-1974 defines operating experience as an " accumulation of verifiable service data for conditions equivalent to those for which the equipment is to be qualified."

e r

3.11-21a

TABLE 3.2-1 MOOT F n E.O som m-c. rc me.% %

cc::rr== c' *-emcman-3:rgbefetyI2)

Principal Component (I)(9fS1EM NP)

Cisee Con.u.a.ame i ro E.ov.l I.

Reactor System (E>l'6) [ N C-1.

Reactor vessel 1

go t tutL90E_D - hs5%IE. MEJC.M A*41CAk--

2.

Reactor vessel support skirt 1

3.

Reactor vessel appurtances, pressure retaining portions 1

4.

CRD housing supports 2

5.

Reactor internal structures, engineered safety features 2

Y 6.

Non-safety class reactor internals NSC Sd C 4- % EF~T y 7.

Control Rods Controlroddra,ves}3 gggggg 2

McrT 8.

2 t E (.OOF_O - QA %sq E M m A m tA L 9.

Core support structure 2

l 10.

Fuel assemblies 2

!(

u >

s II.

Nuclear Boller System (6'2,.1)

o. b,C.gt. [

1.

Vessels, level instrumentation condensing chambers I

uc5T t eacL\\.)DE.D - %*WV 6. MDA' S %\\-

2.

Vessels, air accumulators 2

3.

Piping, relief valve discharge 3

4.

Piping, main ste.am, within outermost isolation valve 1

5.

Piping, feedwater within outermost g

isolation valve 1

6.

Pipe supports, main steam 1

l r

7.

Pipe restraints, main steam 2

8.

Piping, main steam, between O

isolation valve and M.O.

k stop valve 2

y

~

A em.ec more eV -tw w eekh4,Aoo % hshA,,p m s.u.s.g A so. h Q o3. E.MER.GutM REax.xog woTCowd cD Co4T**WMESTT h T-RE_ea L.

k;) Co aTa.i.4MEuT \\cAtAt ed e.) REACTOR MEAM REMo4Ab.

ed Qp se_ roA Cora.E. Cootwa%

4.\\ Wt.7X9c4%@

TABLE 3.2-1 Continued)

- (woossnEo' rec. Raeonu To 2.70.1 tQ Rev i 4

I I

/

afetyI2)

Prine i pal Componen t ( I }(9tSTE.M M./54miciton1 C1 a s s Cocu2.E LKTsod 70 F_INR.L.

9.

Piping, main steam between M.O. stop valve and turbine i

{

stop valve NSC M#AF E.M 10.

Piping conuected to main steam between isolation valve and l

M.O. stop valve 2

g gggge_pggyg greg g e4 11.

Piping connected within outermost M.S. isolation valve 1

12.

Piping connected to H.S. between isolation valve and stop valve I

beyond its first isolation valve NSC 13.

Safety Relief Valves 1404- %FE'T9 I

14 Valves, main steam isolation wao q g valves 1

15.

Valves, other isolation within E

M.S. isolation v41ves 1

IMC.t ODE.D N

16.

Valves, M.D. stop valves 2

i

~7%F_ vart u W\\ME_ OR IF_ Fmme,d i

17.

Valves, other isolation between M.S. isolation valves and i

l H.O. stop valves 2

18.

Valves, instrumentation in V

piping connected to M.S. betveen isolation valves and stop valves beyond their first isolation gog cap tg g

valve NSC 19.

Mechanical modules with safety function

~

2 thiC\\. u O E D

'4 20.

Electrical modules with safety O

function 2

g 21.

Cable, with safety function 2

y 6

gg g

g a

g t

1 l

i TABLE 3.2-1 (Continue

< -,.. w n a. ~ d)w,e ve.mu \\

k m Safety (2.

2

{

Pr i nc i pal Componen t ( I k"R51E.>4 dh, t.:t'ed Cl a s a ConRE14:TC4 "To EORL 22.

Piping, SRV position 3

MOT 14CA uoED - PASE-W E Mt?.C M*) tc. A(

hydraulic sensing line up to first isolation valve i

i 23.

Piping, SRV position 2

bydraulic sensing line, i

from first isolation

g valve to pressure switch 24.

Valves, isolation 3

a SRV position hydraulic sensing line U

25.

Valves, isolation 2

SRV position y

hydraulic sensing line J

i l

=

l c.

i i

y i

i

t i

TABLE 3.2-Ik(Continued)

(Mon 1F1EO 809. RE94N>#=E fo T10.\\ C) Ps Q l m ASafety(2)

Principal Component (I)dHSTE.M M*)

ectm.a Cl a s s C O RELEl A T t O C O QQ i

i 111 Recirculation System (.B3b) [ :McME_

i 4

1.

Piping 1

MGT IRC.LODED - PAsGn\\/E. MEckwd K.A.L 2.

Pipe suspension, recirculation line 1

}

3.

Pipe restraints, recirculation line 2

4.

Pumps 1

5.

Valves 1

Y 6.

Pump motors NSC MO*4 - SA.FQ9

)

7.

Electrical modules, with safety i

function 3

1 AWDE D i

y 8.

Cable with safety function 2

MA:tERtALS OC Cous1gocitOQ l gg l

o

IV. CRD Hydraulic System (C.\\ \\ [ o.[

A 1.

Valves, isolation, water return line 1

I QC.WDED TMOSC. %s tu ACTW E OS. T.E_ F04C..t so d 2.

Valves, scram discharge volume lines 2

1 3.

Valves, insert and withdraw lines 2

p 4.

Valves, other NSC MO4-SAM E T9

{

5.

Piping, water return line within l

1 solation valves 1

NOT ~' # W D O - A *

M EC M * *C h -

]

6.

Piping, scram discharge volume lines 2

I 7.

Piping, insert and withdraw lines 2

d I.

8.

Piping, other NSC 404 - SAF CTV j

g 9.

Hydraulic control unit 2

n uC.Lu O t _O 1

10.

Electrical modules, with safety I

function f,

2 9

)

g 11.

Cable, with safety function 2

5 MtGr_Q.stA OFC% gzqycy g u p 4

i e

CD i

j

)

l 1

i TABLE 3.2-d(Continued)

(Moomit.O FOR QEsmse ]o T70.% o.) tREV I Safety (2)

/wst efA IgkeAistEMM./ku. acted Class Principal Component CWRO ATsod 7c) E.<DGtL V.

Standby Liquid Control System (p,.4 %) M i

j 1.

Standby liquid control storage l

2 gm intLucqO-mule MEQ%4%CAA 2.

Pump 2

s Mc.Lu OE_ O '

3.

Pump Motor 2

p i

l 4.

Valves, explosive and within 2

gue.toop_e 7%CSE \\MsTR ACTWE: on IE FoucTsoed 5.

Valves, isolation and Piping between I

6.

Valves, beyond isolation valves 2

y 7.

Piping, within isolation valves 1

4cri i4cto oco - PA%W E. ME cwa 4 sca L.

j 8.

Piping, beyond isolation valves 2

4 l

9.

Electrical modules, with safety d

14 function 2

IM CLO DE.t>

10.

Cable, with safety function 2

utcTEggm s oF Co49.;TROCTiod LtST D VI.

Neutron Monitoring System (,CSI)[CL 1.

Piping, TIP 2

ScT suCLUDED - Pr#unf E. MEC.M A.u tC A L i

2.

TIP subsystem 2

4 i

3.

Electrical modules, IRN and APRM 2

gqqweg

]

4.

Cable, IRN and APRM 2

y gyggg gge, op c.ogg.ygoc7g o y tis t-

)

VII. Reactor Protection System

(,C"7 4)[ CL.

1.

Electrical modules 2

inc.Lu o C. O j

2.

Cable 2

M ATEpsnA % o 5: Coustnuctso 3 LtsT i

i

6, F

TABLE 3.2-1MConeinoed) t (Moow:s t.o FCR., Respo4%E. -'To 00 1 a.) Q,g.sj k I-I Priocipal Component (I)(9t=JTEM il C N MLA M70EDEL i

i i

VIII. Process Radiation Monitors (DQ [D\\#)

o.3b,h I

1.

Electrical modules, main steam line i

and reactor building ventilation i

moottors 2

134CLuoE.O 2.

Cable, main steam line and reactor building ventilation monitors 2

METE.O t %.S OF COgestt2_ucTgo A Lgs 7 i

4 3.

Main steam line 2

iM CbO D E.C) 4.

Containment vent exhaust 2

g w e.L o D E. O d

5.

Off ras I

' NSC wo4- %A G E.7T h

6.

Carbon bed vault NSC 7.

Steam packing exhauster p

NSC 3r IX.

RHR System (E.W) [ o b>C d t".O i

i i

i t.

Heat exchangers, primary side 2

@ t MO. ODE b - PAS 9 W MEI.3A4stAA,

}

2.

Heat exchangers, secondary side 3

g 3.

Piping, within outermost isolation

)

j i

valves 1

4.

Piping, beyond outermost isolation a,

valves f

m 2

If

?

5.

Pumps 2

]

U 6.

Pump smotors ggetg o t b 2

1 1

7.

Valves, isolation, LPCI line between 1

}

U 8.

Valves, isolation, other 2

l

r ~.

TABI23.2-lhContinued)'

4 (mscsE.o con.nespoesE.7o TO.\\ o-). Ute.v i Principal Component (I)(9fSTG.u @

a Ca

@ EELA7 TON 'TO N E L

.i!!

9.

Valves, beyond isolation valves 2

10.

Mechanical modules 3WCt.uoE.C)

TwasE. taasTR A.CtWE. OEL 2E. FuoacTsod 2

11.

Electrical modules, with safety g

1 function 2

g get uDE C) 12.

Cable, with safety function 2

g gggg o p.

c:o % w so a ug7 13.

Suppression pool strainers 2

MdT WWDE Q - Pasi.Ss M E ME.C.,%A.w \\C.,A L O

' i l

1J l

!, N e

l l

l i

i O

1 e

i I

i

k TABLE 3.2-I (Continued)

(MoDtFito FoR. NGE. ro ?p.Ia}. gg,q {

Principal ComponentIIbisMu M Caa CocataFvCTion To EQL X.

Low Pressure Core Spray [,,E.7 Asb>Cet k i

1.

Pi ng, within outermost isolation gqg ge 2.

Piping, beyond outermost isolation valves 2

3.

Pumps 2

g 1

4.

Pump motors 2

tuttuoE_O 5.

Valves, isolation and piping between 1

(.Vaa-VEUb) 6.

y I

Valves, beyond outermost isolation y gy,,

F 7.

Electrical modules with safety 14cwe -Mi WM WEOS.1E. Fogo d 2

i function a

M 8.

Cable with safety function 2

tMC W E-O

~

2 wa:TE.n.as,,s, op cogsTg.octso i tse,T p XI.

High Pressure Core Spray (E.T2-D/O.ibCfd ii t

1.

Day Supply diesel tank 3

]

2.

Piping, within outermost KyST suCLOOED - PAnsVE MEc%m gcAL isolation valve 1

3.

Piping, diesel service water 3

4.

Piping, return test line to condensate storage tank beyond second isolation

+

valve NSC d

5.

Piping, beyond outermost isolation valve, other 2

6.

Pump, HPCS Y

2 14C.wEO 7.

Pump motor HPCS 2

4 8.

Pump, diesel service water 3

9.

Valves, beyond diesel shutoff valves 3

,wcw at,o _ m sg m gg og 7p_ g 10.

Valves, outer isolation and within 1

4 j

~

t

-f

+

g e

3 j

TABLE 3.2-kContinued)

(MocissEb FCE RESMSE. ro To 4N Re.V \\

A ss9 Safety (2)

Principal Component (I(15pfstEM M mod Class O N W Tto 4*TO E.Q R L 1

}

11.

Valves, beyond isolation valves, A

~

motor operated 2

1 12.

Valves, diesel service water 3

13.

Valves, other 2

V 14.

Electrical modules, with safety function 2

luo.uEC.D 15.

Electricrt auxiliary equipment 3

5 49.WO' ECD 16.

Cable with safety function 2

17.

Electrical Auxiliary equipment g i g q,% q, OF Co4%,TnutTiod u W vith safety function 2

14ccooE.O r.

XII. RCIC System (E.E.1) o-h i iC tik f

h 1.

Piping, within outermost isolation

).,

valves 1

MOTLNCuc h P W M MEC%NmC C i

2.

M p.ng, beyond outermost isolation i

v. van 2

r' 3.

Mcy & return test line to con-

- m M storage tank beyond second y

(

f s

i i<

ri valve and vacuum pump 4

4a schargir line to containment gdg ugmy l

I f

isolation valves NSC i

4.

Pumpe 2

14C.\\ O DE.D

{

5.

valves, isolation and piping l

between 1

4 luctubE.0 @ ALVE.S,{,

s 6.

Valves, return test line to con-densate storage beyond second f

U isolation valve,and vacuum pump ge,4 5,AFE.79 a

discharge Iine tn containment j

7' isolation valves NSC 5

!.S i

J

l TABTI3.2-Ikcontinued)

(, Mot:>isseo coe Gue seo.4A ro 2. ro.1 o). Gtcy l A. Safety (2)

Principal ComponentIIk wwg4 4 Class Count _Wsod 70 "ML r

7.

Valves, other 2

tactuoEO -7%st wrm AcTWE. ca. UE. FouC"Tiod 8.

Turbir,e 2

g g e,, w o g_ o l

9.

Electrical modules, with safety function 2

g u e.LO OE D 10.

Cable, with safety function 2

uge u.s ALs os c.ouSTROCTson t gs T XIll.

Fuel Service Equipment (Wtt MME.

um i n ttooEO - muiVE_ MEcmou A.L XIV. Reactor Vessel Service Equipment ( S\\'b AboE.

2 :

XV.

In-Vessel Service Equipment (F Ah[Qout l.

Control rod grapple 2

XVI. Refueling Equipment (FtS)[Qo.as,,,,,

I.

Refueling equipment assembly platform 2

2.

Refueling bellows NSC 3.

Fuel transfer system T

.I v b

=

,.M

m TABLE 3.2-1 (Continued)

(rootmE.O so' tt. QEspS? To T10.\\ o ) GLE V 1 M u / Safety (2)

Prineipal Component (I(*HETE,M Mb/SuccTnoc CIass C_onctt.'.LA"Ygod ~TO E@k XVII. Storage Equipment (Flh [ dom.aE.

1.

f'uel Storage R'acks 2

McST i MClu DE.D - 9A.SSWE_ ME.C.MaMsCAb 2.

Defective fuel storage container 3

XVIII.Radwaste System (fa*J50fGO

,k

\\,

1.

Tanks NSC

@Q sAPGQ 2.

Ileat exchangers NSC 3.

Paping Noc.%AFETT i

a.

Between containment isolarion

{,

valves 2

Mc5'T b.

All others 1 uc Lo OE.C) - VAJ::s4 VE. M E.CR An sc AL _

NSC coq-sAS E,,7 4.

Pumps hSC MOO -S A FE."Ti j

5.

Valves

]

a.

Containment isolation 2

t Qc.LVOE t">

b.

Discharge flow cont ol NSC c.

All others M og_ qAS: E Ti NSC i

j 6.

Mechanical modules NSC

,I Y

i s

=

7 l

0

TABLE 3.2-kContinued)

(.w:aGdF_D FoR.RESPo*SE. To Tio.l o} 12s.v {

Principal Componentb (9tsw.24 M 4

ass Coo.qELA Tsod - To E.QRA XIX. Reactor Water Cleanup System (, ~6b

%C 1.

Vessels: Filter /demineralizer NSC Mod-SAF E.T9 2.

Heat exchangers carrying reactor water NSC Mod #a AF E T9 j

4 3.

Pump suction piping, to outermost isolation valve 1

4.

Pump discharge piping, to RHR and Moi s NCA.Mt:Tr D-PASGs4 E-MECMAM tCA,\\,,,,,.

blowdown 3

y 5.

Pumps NSC 6.

Valves, isolation valves and Nog-sA,psT9 piping between

.I 7.

Valves, pump discharge to RHR

\\MCLODE o (,V ALME.S}

v i

and blowdown 3

N tt.V OE D TeosE to sT W Acts o E. OS2. I.E. F09C:T io d E

8.

Filter /demineralizer NSC j

9.

Filter /demineralizer precoat gog gp p pg g

subsystem NSC l

10.

Nonregenerative heat exchanger shell and interconnecting piping carrying closed cooling water NSC y

(

4 i;

l l

l

^

4 TABLE 3.2-h(Continued)

(M00tFILO Foe,. Qt&FonSE. To T10.lo). RE-V k

/sarctv4 Safety (2)

Prineipal Component (IksM1EM kVthMmW C1aes Gperta.Tgod To EQRL i

I XX.

Fuel Pool cooling and Cleanup System (Ca41 b,d,(

~

l.

Surge tanks 3

_ OciT n<tODED - 92NE MEL%ust AA.,,

2.

Heat exchangers 3

3.

Piping 3

4.

Pumps 3

Y 5.

Valves 3

6.

Filter Demineralizer System, i K LuOE.S

]

Cask Pit Drain Subsystem, and ts c A. c s o *J VeoNE.S out Fuel Transfer Tube Subsystem dO N -%FFM i

a.

Piping and valves NSC b.

Tanks NSC e

n

]

c.

Pumps NSC d.

Vessels (F/D)

HSC 7.

RHR Connection 3

ggz gg,;.ct,oeCD-AsstslE_ MER.Ha MSC. A t s

j 8.

Pump motors 3

uoc I E i

XXI. Control Room Panels

(.Hl'6) a,b,C,,,d,C,(

I 1.

Electrical modules, with safety i

function 2

14CLVDCS alt. IE. PA.s4ct.S j

U 2.

Cable, with safety function 2

i

^

I' 3.

Safety Parameter Display Panel NSC

\\

5 E

Y i

1 e

i i

TABLE 3.2-1kContinued)

("ot$st.o FOR p.Es,9oose. To rio.\\aN

) p.v 4 \\

I (2)

Principal Component (IkERstE.x 4)

Ca Coctne \\ gttod ~TO E Q A.L XXII. Local Panels and Racks [.H22.[Hs

%b,c,.i d ge., k 1.

Electrical modules, with safety function 2

i MC.

ED 2.

Cable, with safety function 2

v ATE.Q.t ALS OF Cooc;tu.utTso d t gst XXIII.

Offgas System QdCo4c) [Nou1: _

1.

Tanks NSC SJod - SA.G M9 1

i

[

l 2.

Heat exchangers t

.NSC I

3.

Piping 1

NSC i

U 4.

Pumps NSC 5.

Valves, flow control NSC 6.

Valves, other NSC 7.

Mechanical Modules, with safety function NSC j

8.

Pressure Vessels NSC j/

XXIV. Main Steamline Isolation Valve ( D Leakage Control System

%k 1.

Piping and valves up to the first isolation valve of the inboard subsystem gg ggugf,.c, mw Ar itvE oc TE., FwT tN I

2.

Piping and valves, other 2

3.

Blowers p

2 t ectooE.o I

1 1

4 TABLE 3.2-Ikcontinued)

(,mootsseo roa. Rcsm45s. ro '2.?o.\\Q T2s_4 \\

Principal ComponentIbe.u oth N

Ca CoRRELaCTsod 70 %12 L XXV. Emergency Service Water System Mh g e.,4 1.

Piping 3

2.

Pumps 40Y,MCWOED - PA%WE MECMA.u\\CA.N 1

3 3.

Pump Hotors NCLucr O 3

l 4.

Strainers

(

3 5.

Valves QcT t ucwoE.D - t:%SSt\\l E., MECMA.O \\ CAL 3

i 6.

Electricc1 Modules, with Safety icC.LuoE.D m%E. wrta ACTS 9E.OR ~I.E 9 Ouchod Function 2

Cable, with Safety Function i 4c.LVDE.C) 7.

2 ma:TERge ot CcubNOC\\CM LicGT XXVI. Emergency Closed Cooling Water System (,V%'2 Se,k M

1.

Piping 3

M c"T t t4EtooE.0 - PA.5sW E_ vetwA,mca,g 2.

Pumps 3

Q 3.

Pump Motors g e ttootc>

3 4.

Valves 3

5.

Electric Modules, with Safety l

Function 2

V 6

Cable, with Safety Function 2

7.

Heat Exchangers yATct.in,LS os:co % h Tgo.3 (ggy 3

w erT gec.LuoE.o - Pass tVF_ MEC.H Au tCA.L XXVII. Plant Service and Cooling Water Systems (Plant Service Water, nuclear closed

)

cooling & Turbine Building Closed Cooling)

(_P41, PO > P4A) / k>

i 1.

Piping and valves forming part of primary containment boundary 2

3 t uctuCES 2.

Other equipment and piping NSC W-O\\ ATsot4 \\/ALs/ cows 9 gog_ggy:g i

4

e i

l TABLE 3.2-bContinued) bOOWsE.O M RESA:>mfe# To 2."70.\\ o.) REN\\

Principal component (IY h #

Yd Con 525Lh7 sod to EQRL

,F s

i XXVIII. Instrument

~

and Service Air Systemy Pt5%,PS'2 3PS'h/O.M 1.

Vessels, acc ulators, supporting safety related systems 3

46T 54CluDG_D-PA%WE. McCumCA.L 2.

Piping and valves in lines between i,

re a ed s s

3 INCN 3

3.

Other equipment and piping NSC 1404-SA5:E'T4 XXIX. Diesel Cenerator Systems [,R43,R4 RAS 3

1.

Day tanks and f I st e

k 6doTIMCLuD Q - M n M EN h,

2.

Piping and valves, fuel oil system and diesel cooling water system 3

1 3.

Pumps, fuel oil system and diesel lMCLVDES \\l ALMEs sp era Acts 9E. ca IE. Ft.w Tioed service water system 3

14CLubE.D 1

4.

Pump motors, fuel oil system and j

diesel service water systems 3

Ind C L O D E D 5.

Diesel generators

{

6.

Diesel generators starting air g uctu o q_.C) 3 system 3

]

7.

Lube oil system Mo"Y sMC.L.uD E.D - PAbbt9 E utc.a Au s c.a s_ __

3 8.

Electrict modules with safety g get99g,9 functions 2

t wCL.COE.O g

9.

Cable, with safety functions 3

10.

Diesel generator coahustion air gicTEtt.s m S OF COQm94CTion L.C j

intake, exhaust systec, intake and e-.

j exhaust systems intake air filter, and valves.

ym g uttu or.O - PA%\\VE ME.CAMsCA-A -- -

N 3

b 11.

Exhaust silencer

[

and crankcase vent piping NSC co Q - q, AGE. T9 3

12.

Jacket water cooling 3

mgooge

.m i

TABLE 3.2-IkContinued)

(MootFito SCCt. REsmse To T10.5 Q q,_q )

/ m gqb Safety (2) 1 Principal Componentil(1stsMM 59E /AnucTM Class C43t252EL.a:t god 70 DE 3.

Piping and valves, other NSC N CAFE T9 4.

Pressure Vessels NSC 5.

Condensate & Feedvater Pumps NSC 4

6.

All Other Pumps NSC 7.

Tanks NSC l

l 8.

Other Components NSC g

j XXXI. Condensate Storege and Transfer System (fil klogE.

ts k

1.

Condensate storage tank NSC N-W E~TQ m

l 2.

Piping and valves NSC

]y 3.

Other components NSC If XXXII. Auxiliary a-c Power Systea

[o.,b,C,,d,g,,h

)

1.

4160 V switch gear with safety (pp L) 2 functsons nactooE.D i

l 2.

480 V load centers with safety @ N 2 func'tions j

3.

460 V HCC'S with safety functions (,qg,Q 2 3(

4.

All cables with safety function l

(including underground cables, (RSl[2.37) i M A1ER W) O F N M O G O O U S"T k

cable splices, connections and j

terminal blocks) 2 y

'4 l

5.

Conduit, cable tray and supports

]

O containing Class IE cables cabletrayandsupp(ortsr233) 2 MOT ttOCLooE O c.5TRoc'tona.t ONL.9 i

,L 6.

Conduit, i

y containing non-1E cables in safety class structures where failure may damage other safety related items.

NSC Mohl-G AF C7T

{

TABLE 3.2-IkContinued)

(MOOtBIED 009.RES9onSE "To 7M IO-R E.V I

/gs: m % sfaty(2)

Principal ComponentII h M N 61)/90elCTed Class i

i coq.CtE.LAT, \\C 4 70 E_Q9 L t

7.

4160/480 transformer with safety functions

(.t? ?_"b) 2 8.

Protective relays and control 14CLOOE.O WrTR LOA,0 CE.bfTE.9.S AeoJEL l

panels with safety functions M7-)

2 g uttoop_O 9.

a-c control power inverters with 2

safety functions

(.p,g}

INCLODE.D 10.

Containment electrical penetrations (SQ2. 2 3

i 11.

Fire stops inttuoq_ o MSC 12.

gog wp pg All components with safety functions 2

seatsODE O XXXIII.125 Volt d-c Power Systee(R$[o,,b,c,dg.,(

I M

1.

125 V batteries, racks, chargers, i

distribution equipment with I

h safety functions 2

INCLuoE O t

2.

Cables with safety functions 2

MrCTER.\\M S 05: C04S~TV.OC~T tOA LE~T 3.

Conduit and cable tray and supports containing Class IE cables 2

4.

Conduit and cable tray and supports eacST s uCLMOC.D - %TR.OC70Q.A.L._ OML.9 containing non-lE cables in safety class structures where i

i failure may damage other safety

)

Response

(a)(1) Using the methods outlined in NRC Memorandum from Vollmer and Mattson to Eisenhut, dated April 8, 1983, " Guidance for Licensees and License

~ Applicants to demonstrate compliance with 10 CFR 50.49 ' Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants'" and Appendix A, " Typical Equipment or Systems Important to Safety,"

and Appendix B, " Typical Examples of Non-Safety-Related Equipment" and Regulatory Position Cl of proposed Revision 1 (May 1983) to Regulatory Guide 1.89, all electrical equipment located in a harsh environment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions is classified as safety-related.

Compliance with IEEE Standard 384-1974 as modified by Regulatory Guide 1.75 with the design alternatives noted in Table 8.1-2 assures both electrical and physical separation between redundant safety-related systems and non-safety-related systems so that failure of the non-safety-related equipment will not prevent satisfactory accomplishment of safety functions by the safety-related equipment. Non-safety-related (non-lE) devices in associated circuits as defined in Regulatory Guide 1.75 have either been qualified for the postul ted environmental conditions or a failure modes and effects analysis (FMEA) has been done to demonstrate that all possible failure modes of the device will not prevent satisfactory accomplishment of safety functions by safety-related equipment. To further assure that failure of a non-safety-related control system will not result in consequences more severe than those analyzed in Chapter 15 a study was done to answer NRC questions on control systems failure (see letter PY-CEI/NRR-0022L, dated March 14, 1983).

l (a)(2) All safety-related electrical equipment in a harsh environment, as defined in the scope of 10 CFR 50.49 is included in the EQRL report entitled

" Safety-Related Equipment Identification and Environmental Qualification Summary" provided with the response to Question 270.1(a).

(See l

Sections 3.11.1.1 and 3.11 3.1 for the commitment to provide the ab'ove scope

{

of safety-related equipment in the referenced EQRL report.)

l l

i e.

.270.8 (Cont'd) s 4

(a)(3) The.EQRL report entitled " Safety-Related Equipment Identification and Environmental Qualification Summary" provided with the response to Question 270.l(a) includes the post-accident monitoring equipment required in Categories 1 and 2 of Revision 2 of Regulatory Guide 1.97 as listed in Table 7.1-4.

(b) Since as noted in the responses to (a)(1) through (3) above, the subject equipment is already included in the equipment qualification program, no additional information or justification is required.

l

\\

l.

i 4

l

.,... -. _ ~

ML20083J815

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ML20083J815

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