Text

Forwards Addl Info Requested During 820921-22 & 1118-19 Instrumentation Working Meetings.Amended PSAR Pages Will Be Incorporated Into Future PSAR Revision
	ML20028B927
Person / Time
Site:	Clinch River
Issue date:	12/06/1982
From:	Longenecker J; ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To:	Check P; Office of Nuclear Reactor Regulation
References
	HQ:S:82:138, NUDOCS 8212070243
	Download: ML20028B927 (77)
	v • d • e

@

Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:138 DEC 0 01982 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Check:

INSTRUMENTATION (CHAPTER 7) WORKING MEETINGS - ADDITIONAL INFORMATION

Reference:

1) J. R. Longenecker to P. S. Check,

Subject:

Meeting Summary for Instrumentation (Chapter 7) Working Y Meeting, September 21 and 22,1982, dated September 24, 1982 4

2) J. R. Longenecker to P. S. Check,

Subject:

Meeting Summary for Instrumentation (Chapter 7) Working Meeting, November 18 and 19,1982, dated November 29, 1982 Enclosed is the additional information requested during the subject meetings for which a response date of December 1,1982, was projected. The amended Preliminary Safety Analysis Report (PSAR) pages will be incorporated into a future PSAR revision.

Any questions regarding the infonnation provided or further activities can be addressed to Mr. R. Rosecky (FTS 626-6149) or Mr. A. Meller (FTS 626-6355) of the Project Office Oak Ridge staff.

Sincerely, gDO L).hw nam 1

//37 J n R. Longene er Acting Director Office of Breeder Demonstration Projects Office of Nuclear Energy l

Enclosure cc: Service List Standard Distribution Licensing Distribution

8212070243 821206 i

PDR ADOCK 05000537 A PDR l ;

ENCLOSURE Instrumentation and Control (Chapter 7) September 21 and 22,1982, and November 18 and 19,1982, Working Meetings Action Items Due to Nuclear Regulatory Commission December 1,1982 September Item (November Item) 4 (11) ll(3,15) 52 (2)*

56 (5) 65 (17 N/A (20

The attached "CRBRP Remote Shutdown Design Compatibility with ISCB Statements of Guidance for Interpreting Criterion 19 of 10CFR50, Appendix A" will not become a part of the Preliminary Safety Analysis Report (PSAR). The amended Q/R 421.17 will become part of the PSAR.

' Item 4: l&C Design Criteria - Tech. Basis

(,

Comments (From Nov. t 8-19 meeting, Item 11) The plant wIlI comply with Regul atory Guide 1.75, incl uding wiring inside cabinets. A discussion.of Regul atory Guide 1.75 compilance wIlI be included In Chapter 8.

Chapter 7 will reference Chapter 8 for Regulatory Guide 1.75 compilance.

Resol ution: Amended response to ite;n 4 attached.

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Page 3 7.1.2.2 Indenant'eace of Reduadmat taf e+v tof a+ed ha+=ae

[s To assure that Independence of redundant saf ety related equipment Is preserved, the folIowing spectfIc physical separatton erIterIa are imposed for safety -

rolated Instrumentatton. l o All Interrack' PPS wiring shall be run in condults (or equivalent) with l wiring for redundant channels run in separate condults. Only PPS wiring shall be included in these cenduits. Primary RSS wiring shall not be run in the same condult as secondary RSS wiring. Wiring f or the Cl3 may be run in conduits crantaining either primary RSS viring or condults containing secondary shutdown system wiring, but never latermixed. Expanded criteria for physical separation of the CIS are given in Section 7.3.2.2.

o Wiring for other safety related systes may be run in conduits contaIning either primary RSS wiring or conduits containing secondary RSS wiring, but never Intermixed, provided that so degradation of the separation between primary and secondary RSS results.

o Wiring for redundant channels shall be brought through separate contaltunent penetrations with only PPS wiring brought through these penetrations. Primary RSS wiring shall not be brought through the same penetration as secondary RSS wiring. Wiring f or the CIS and other safety related systems will be brought through the same penetration as the RSS wiring with which it is routed.

7 Instrtsmentation equipment associated with redundant channels shall be

( o mounted in separate racks (or canpletely, metallically enclosed compartments). Only PPS channel Instrtanentation shall be mountec In these racks. Primary RSS equipment shall not be located in the same rack as Secondary RSS equipment.

pen rac 7 o Th nys i epa tio et n uit atl ,

l nt n ed car. ns ont an ss I pe led n

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,g This separation shall provide assurance that credible single events do not simultaneously degrade redundant channels or redundant shutdown systems.

o The wiring f rom a PPS buf fered output which is used f or a non-PPS purpose may be included in the same rack as PPS equipment. The PPS wiring shall be physically separated frcm the non-PPS wiring. The a:nount of separation shall meet the requirenents of IEEE 384-1974 o Electrical power for redundant PPS equipment shall be supplied frem separate sources such that f ailure of a single power source L

7.1-3 Anend. 62 Ncv. 1981

(Insert to 7.1.2.2)

The physical separation between conduits, penetrations, or rocks containing redundant Instriment channels shall meet the requirements of Regulatory Guide 1.75. Redundant Instrument channels in the primary RSS shall be physically separated from one another In accordance with the requirements of Regulatory Guide 1.75. Redundant Instrument channel s In the secondary RSS shalI be physically separated from one another In accordance wIth the requiranents of Regulatory Guide 1.75. Functional capabil ity is maintained in the event of single design basis events which might impact more than one sensor by alternate protective f unctions as described in Table 7.2-2. Requirements for separation del ineated in Section 8.3.1.2.14 shall al so apply.

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NRC CONCERN Item 32 6 35 Provide more information on ESP I&C functions and a description of Safety-Related Display (3 jg,) information.

Provide more detailed design (including diversity)

(BRI Items 32 and 35criteria dis-and inpot cussion of ESF IEC in the PSAR.

to LRM Item 62 from September 21, 1982 NRC Meeting.)

RESPONSE

A discussion of the ESF Atmosphere Clean-up Systems and the Steam Generator Building Aerosol Mitigation Release System is provided in attached revised PSAR Section,6.1, 7.3 and 7.6.4.

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TABl.E 6.1-1 IN CRRRP FNGINFFRFD CAFFTY FF ATURFK

_tIET OF PtAR Sectfan Cafety Featuras Fnelneer rt 6.2 Reactor Confinement / Containment 6.2.4 & 7.3.1 Reactor Containment isolation System 6.2.547.33 .

RCS Annulus Filtration System 6.2.6 4 'Il

Reactor Service Building Filtration System 6.2.7, 4s+ri , '] .3.4 9.13.2, 9.6

' Steam Generator Building

!AerosolReleaseMitigationSystem 6.3 4 7 3 3 HabItabIIIty Systems 5.2 Reactor Guard Vessel 5.3 Guard Vessels of PHTS Major Components 5.6, 7.4.1 & 7.6.3 Residual Heat Removal System 6.4, 3.6-B, & 3A.8 1 Cell Liner System 6.5, 3.8-C, 3 A.9, 9.13.2 j Catch Pan & Fire Suppression Deck System 4

. ~

6.1-2

7.3.3 ESF Atmosphere Clean-up Systems The ESF Atmosphere Clean-up Systems are as follows:

a) RCB Annulus Filtration System b) RSB Filtration System c) Control Habitability System These systems are described in the following sections.

7. 3. 3.1 Desion Criteria Esf A4.w.pke (h*Wf The following design criteria are applicable to the ., f:t; r:hted N Instrumentation and Control Systems:

A. Compliar.cc with CRBRP General Design Criterion 11 as listed in Section 3.1.3.

B. Class 1E power supply, backed up by Diesel Generators, provide power to al1 sais?y r:ht_d ::'#4 Sy:t& ccmponents.

C. No single failure of an instrument, interconnecting cable or panel will prevent a key process variable fron being ,

controlled or monitored in redundant divisions.

D. Physical and electrical separation of redundant portions of the F4% System is provided.

E.

Manual initiation of each protective action is provided at the systen level . E37 AbwespLrc Ow "('

F. Instrumentation used in the control ofy% Systems will function during and after an SSE.

EdF Arncrk d UO'* P G.

Instrumentation used in the control of/H6 Systems will function during normal environmental conditions .and during I

environmental conditions created by any design basis accident.

H. Capabilities for periodic testing and calibration of allg,p a , , W .ai

g4 g gd l

i instruments are provided. 55F. Mea 4emD$b C

I.

Capabilities for remoteAafCtdC.: are provided, should the Control Room become uninhabitable.

J. Capabilities are provided to monitor the bypass or inoperable status of components in accordance with NRC Regulatory Guide 1.47.

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S g 7.3.3.2 tionitoring Instrumentation Typically, process variables are mor.itored and indication is provided in the Control, Room and locally as follows( Ah M W h P( ED s ..-

. A.

wecAs t . 6.) :

1. All valve and damper positions.

2. All fan operation staitus.

3. Filter unit humidity.

4. Filter unit discharge air flow (also recorded in the Control Room).

5. Filter unit adsorbent filter entering air and leaving air temperature (local only).

6. Filter unit differential pressure across each filter bank and across entire unit (local only).

-fc Jfracspherf

7. Annulus 4 differential pressure.

lo a M p N.-f._

8. R5B confinement A differential pressure.

9. Control Room HVAC unit supoly air flow (also recorded in, the Control Room).

13. Control Roem HVAC unit discharge air, mixed air ar.d return air temperatures. ,

lat.17

11. Outside air temperature.

12. Control Room main and remote air intake radioactivity level for radioactive gases, iodines and particulates.

13. Control Room differential pressure.

B. Typically, process variables are monitored and alarm annunciation is provided in the Control Room and locally as follows:

1. Motor thermal overload, high vibration or air flow low for each fan.

I 2. Differential pressure high across each filter bank and across entire filter unit.

3.

Unit cooler or HVAC unit supply air temoerature high or air temperature entering cooling coil low.

Smoke, arrnonia, chlorine, cir'r or radiation presen t dWtitt#/AgdlK 4.

in Control Room main or remote air intake.

S.

Control switch in the local mode (Control Room only '

alarm only).

C. Typically, process variables are provided as inputs to the Plant Data Handling & Display System as follows:

1. Control Room and computer roon humidity.

2. Annulus differential pressure.

3. RSS confinement differential pressure (four different cells).

4. Control Room differential pressure.

5. Air temperature entering and leaving each filter unit.

6. Air temperatute entering and leaving each HVAC unit.

7. Inoperable or bypass status of components.

7.3.3.3 pesionAnalysis tion of Section 7.1 and the IEEE Standards System listed of alarm circuits and inputs to the Plant Data Handling and Displa (PDH&DS) which are non-Class 1E circuits.

7.3.3.4 RCB Annulus Filtration Svstem

7. 3. 3.4.1 Desian Basis g The RCB Annulus Filtgtion System is designed to ensure dd that a acceptable upper limit of a 4 of radioactive material is not exc under the site suitability source term c6nditions.

System Descriotion i 7. 3. 3. 4. 2 Initiation and control of the F!CB Annulus Filtration System represented by Figures 7.3-3 through 7.3-9.

and control operations.achil e e-be provided:

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ITp $4gt7 To OR75mf 4r=s4ws nulus space under (

1. tiaintain the containment / confinement uring normal \

1/4 inch water gauge negative pressur I plant operation and accident conditions.

2. Provide filtering of the annulus exhaust during nonnal operation.

3.

Provide filtering of the RCB ventilation exhaust air through the annulus filter system during P,CB/RSS open hatch refueling operations.

4. Initiate filtering and recirculating of the annulus air during accident conditions.

The RCB Annulus Filtration System is also described in Section 9 Reactor Service Building (RSB) Filtration Svstem 7.3.3.5 -

7.3.3.5.1 pesign Basis _

The RSB Filtration System is designed 9d +*mtotyfilter h c;.the

%.-RSB exhaus t order to mitigate the consequences of the Sit:hggg7g ggg

(-SSST}- event.

7.3.3.5.2 System Descriotion Initiation and control of the The RSB Filtration following System initiation and control is represente Figures 7.3-10 through 7.3-13.

operations shall be orovided:

1. Filter RSB exhaust during all plant conditions.

2. Initiate RSB confinement, recirculation and filtering ,

during accident conditions.

3. Maintain the RSB confinement at under 1/4 inch water gauge negative pressure The RSB Filtration System is also oescribed in sectionHi.l.1.

Control Room Habitability System _

7.3.3.6 _

i 7.3.3.6.1 Desian Basis d The design basis for the Control Room Habitability System in Section 6. 3.1.1.

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7.3.3.ti2. System Descriotion A detailed descriptiari of the Control Room Habitability System is presented in Section 6.3. - 1+

Figures 7.3-14 through 7.3-M represent initiation and control of the Control Room Habitability System.

by this system is as follows: ,

a) ^ Maintain the Control hem at' positive pressure at " ::

to minimize the infiltration of radioactive or( ,., e w ..ke chemical ,

centamination.

' Initiate Control Room isolationAwhen smoke or toxicorgases b) are present at either the remote or main air intakej c) Initiate Control Room recirculation / filtration mode when containment isolation is initiated, when Control Room isolation is initiated or by manut.1 initiation, i

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s Steam Generator Building Aerosol Mitigation Release 7.3.4 System ( arf 15 )

7.3.4.1 System Description Figures 7.3 (to' be provided later) represent in ARMS.

7.3.4.2 Design Criteria The following design criteria are applicable to the SGB ARMS:

A.

Compliance with CRBRP General Design Criterion 11 as listed Section 3.1.3.

B.

Class 1E power supply, backed up by Diesel Generators, provide power to all system components.

C. No single failure of an instrument, interconne or monitored in redundant divisions.

D.

Physical and electrical separation of redundant portions of the system is provided.

E.

Manual initiation of each protective action is provided at the system level.

F.

Instrumentation used in the control of ARMS system will functi during and after an SSE.

G.

Instrumentation used in the control of AMRS systems will func during normal environmental conditions and during environm conditions created by any design basis accident.

H.

Capabilities for periodic testing and calibration of all instruments are provided.

I. Capabilities are provided to monitor the byp Design Analysis

! 7.3.4.3 The SGB ARMS is designed to meet the requirements of Se the IEEE Etandards listed in Table 3 7.3-2'.

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JE TABLE 7.3 s2' (PPu d$ $(,,E rp LW W lEEF $mqba@b5 EsF 5phs Criteria for Protection Systers for Nuclear !

IEEE-279-1971 IEEE Standard:

Power Generating Stations !

Criteria for Class 1E Power Systems for Nuclear Power IEEE-308-1974 Generating Stations General Guide for Oualifying IEEE-323-1974 IEEE Trail-Use Standard:

Class 1E Electric Equipment for Nuclear Power Generating Stations Criteria for the Periodic Testing of Nuclear Power Generating IEEE-338-1977 Station Protection Systers IEEE Trial-Use Guide for the Application of the Single-Failure IEEE-379-1972 Criterion to Nuclear Power Generating Station Protection Systems IEEE-383-1974 IEEE Standard for Type Test of Class 1E Electr Stations IEEE Trial-Use Standard Criteria for Separation of Class 1E IEEE-384-1974 Equipment and Circuits l

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' T ABL E

],3 - 3 SYMBOLS h ALARM b INOPERABLE STATUS MONITORING h RED IND LITE ,

GREEN IND LITE h WHITE IND LITE h COMPUTER INPUT ED.IES:

1) Control switches are spring return to auto from start with a maintained stop unless otherwise stated.

ARRREVlATIONS

-)

SSPLS

- Solid State Programmable Logic System CR -

Control room (remote)

L Local (not control roon) ,

T.D. - Time deIay N. C.

- Normally closed F. C.

- Fall closed S.O.V. - Solenold operated valve A.O.V. - Air operated valve MOD - Motor operated damper ZS

- Position switch i

CIS - Containment 1 solation signal PPS

- Plant Protection System E/H - Eloctro-hydraul Ic

TABL E , (Continued) a 2

7. .> - 3 TE

- Temp element TT - Temp tranonitter Of/*

TIC - Temp Ind controller A

OAI - Outside air intake Npfd6 TMD - Temp modulatod damper A

RA

- Return air PDI

- Pressure differential Indicator PDC - Pressure dif f erential controller PMD - Pressure modulated damper PDISH - Pressure dif ferential Indicating switch high FR

- FIow recorder FIC - Flow Indicating controller FSL

- Flow switch low FT - ~ Flow transmitter FMD - Flow modulated damper FE

- Flow element M - Moisture l PB

- Pushbutton l

! MJX - MuttIplextng AHU

- Air handling unit i

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Rl~ FILTRATION RECIRCULATION DAMPERS s . /

CONTROL ACil0N REsULTAN8 nOMif0R ,

CONDITION

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g FIGURE 7.6-33^ FATcATic>l 5fstret

>- FUNCTIONAL CONTROL DI AGRAM RSB EEE4EtF-

" DISCHARGE, EXilAUST, RECIRCULATION &

CELL ISOLATION DAMPERS

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y A j OVERLOAD j CR t g O OE-ENERSIZE 3 7 NOT

+ SPACE t

C DEATER ST ARI DEMAND FRON m LOC I IESEL LDADINO' -

l PROCRANtERj FILTER CR DIESELLOADIN]C n ' AND 7- Fgg y g PRMRAMMER 1

> ONOT - SIARI ENERGilEO / CR OR SNITCH

+ DANPER CR (CONinSiART AND q 7 AND 4 OPEN -4 U LOC

(

l AUTO AND >q OR + ,

o-e-_ OR e II# - - Y" 0

+ +

LOC REM 0iE AND > ql >

R 30 SEC m f

A .

SICHALFROM} y - -

$$PLS j + _

A 4 . CR p -

m j A

<g ERNAUST AIR

} -

t.)

FLON Low

.~~~

/ '

IS RE(.940 ANT F AN f N AIR j ,.- LOC F'One LCW ']%,y - - - >J m

/

SOLAft ggca PRE *.i T jl r * '

~I R A 7

Q d

m IILIEE STOP CR RADIAT10N lN lll .

m "l ENEROS2E

<g,ii.k. .: /'3 > SET POINT r,s g.

1+ W ACE W iER

' u.J . T gq p

LOCAL , gggy,p A,;,3 w

'~*] O*NPtR CR S1CHALFRON)}

SsPts OMTR0,tSNiicNfOC

" - 41 'C run + ctOSE -<

AN > -

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~

AUTO y m;lr a \ /

\ aNO c,

( ,e Si0e y

-' FIGURE 7.d#$ T 32<;6 Flat >6ri ::: . -g i;ti g FUNCTIONAL CONTROL DIAGRAM TYF;eA4. FILTER UN&P SUPPLY FAN

l .

t I

r, C*

I I

I y________________________

l i l i I . t tv esc Mg -

i

1 I l '

t I ca l name crwoot V -

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TO

- I toc o' 7. 3- /3 o' n l

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g..

vi ,

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3

CL

, '1 3-12.

EJ ~ FIGURE 7.C f.St5 F it.TW. fad lwtCT VA6M M U N L C . Itctd FUNCTIONAL CONTROL DI AGRAM

.M, ha ll ATrn uru1Tr w rhaurit D 4 T"'"C'i T1.'"'

v w rv % r i,s m e.r y vai s w ri . - . . . .

~

RE981 TANT 3:088810R g, y F a= = .R TEDFERAT , Rgygg to FI 5 7.6 1 s.s.sr

%'f_ W Fiq 7 3-\ 2 M

CONTROLLER SICHAL

\

J LOC 1I FAN RtmMIMO

\ m m

IEleF'498 ZE CON?ROL MOOLLATE s sev=.s. A e CR

) ua o w En a

FAN

"*"' \

j =!aE&sE ,

'"" s Qc" s .

MD" f

b' l hI 7 3-l3 ESO IllIEE

~ I*

s FIGURE 7.5 ?,'

FUNCTIONAL CONTROL DIAGRAMAT77;C%. ICLiiT VA AJE MOM AT10AJ FRGCE55- PAR %; tie *-**NI nC "^T3 .

RESLLIANT te0N110R CDeclitoss CONiROt_ Acil0_N CR A

' LK

^ 4>-

i C OVERLOAD AL j g y HH st ART DENAse) - - Si Afti st A ,,

(F ON D OF+ENERCITE L

IhE Q *

[A7ER ENERCl2EO j Cm _

(CONTROLSNITCH,\'"s?Al'" * / a"o + zw,u

. > LOC I I

+ OPEN -4H R

\,OO m

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/

=

A,o l

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ca

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h}g

]"

CREMOTEstCHAL s'Es j

$ $P i

RE00rORN1 FRN\ -

HEAftR AIR ton MXM LOC OMTROt RH HAI + CLOsE 4>- C AIR INISKE > -

tc0

F C slCHAt PRES ID CR

" 5 sEC ONTROt RH RH IR lH19EE > tR siCHRt PRts D"

toca),5lc"ath a

t oc J , .__ i 55t 5 sNlvC a'e f IS

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suretv rnN stpRT

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pto -

( AUiO --> -

4>- A L- > p OR h-O

\

neo -> w stC -> _ Ca

\

> > R _, , . ,

( sfor l

r

' " 7. 3 - it nt uR rau g ,*

N

*e"t$ tnd'"

) l~ FIGURE-7.0 M FUNCTIONAL CONTROL DIAGRAM CONTROL ROOM HVAC UNIT SUPPLY FAN o O

C005Ii8004 CONTROL ACiION RESLEiANT MINelTOR LOC .

N010R ) *

(Ea%t J i ,g u

IESELLOA0lk O g

> NOT >

PROCRAposER)

ENERCllEO CS Q -

ON RF .? 91 _

nog _p lee URN LOC SiART AND q -

AND -> FApe H l-* _ -->& - _ s> ART CA

(

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~

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SSPLS

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OR

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->JI- - ENEmelFE

-3

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) g"gAfER y Sio"

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LOC A

!,T, -

siaar / _ _

\ =

( AviO

/ L,> __ L_* m D

\ AND >

( s>0r j

CR

'A 15-IT Occi,'m. Rec,%

FIGURE 7r6- H

<0 FUNCTIONAL CONTet0L DIAGRAM T-VILI4;AL- HVAC 4

UNIT RETURN FAN

O -

CONTRot AC11000 RESUtTAp87 pe0NITOR COMOITION

{

.. - LOC Notom TNERMAL

}

m A

ovtRtOAD j j m

O m DE-ENEROl2E NOT a

-> SPACE .

} st' ART DEMAND FftON m t0C DIEsEt LOADINC- " '

7 PtOCR7NME FITTER CA IEstt,toA0lN\C m U m ANO O FAM H F R0CR7 t'ME R - NOT - _ STMT c a ga.- ,=,

I(CONTROLSNITCH = =m 1 -~ -- "=

( ruemcita Auto r"z I on #

. H~~m" tC

( [.t\(.OYlT ,

g4 h'

CAA M80 stor

$ f 4 RENOTE SICes FROM \ >_ + '

- R g q CR 4

A

( Ex T

] 1 1 .

I FtDN TOW

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TM

4$u AtC 883 DkE ges .c9Le f'('

. , a_

d t W i" i. . .

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-> Ad _l m

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-Y5Y bE-(GMC;TE Afil 884fAEc' O >

- - - - - - - - K'tils 81 L- h -

FITTER CR s;ceat r og & FAN HH C l'RE!.tN T l g V - $10P j j / k ml RADfA12kN0lN j is a i i 1 o t r

/ e gngpoggg 9fp,,j,i t i t <

i if <nn ge,qe, sich2E* IRON \ > oa eER ssets j t RNo _

-> Ctost H MCR oNvRotsNitCN\oC FAN >

siARr / _

Q TOC ANo -

\ >

=>

( AUTO

<+ -

aNo

- a stoe

\ * - CR e-. 7 , /\

'A\

M FIGURE h &* M ei CCoM FUNCTIONAL CONTROL DIAGRAM 4 T * *,VgFILTER UNIT SUPPLY FAN

eorrisson conipot actim nasusnn noneten L0c 7"' A (s0tI'iis PIEsENT ,

"I \

cm Sw Tcu f ,

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"QRMAL / :

Oh n . _

" 8880 ! p

,.(CISsc.uAt BYPA%

,_ y a r

(e@ Nits/ AT toMt'o" \'" q =

INIT8 ATE c/g CECantCoLArnost /

Og #

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m

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~ r IR INIR E ADIAtl0t4tilCjs AD" AIR INip E mi j seert ents / *

, =

en p

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\ l

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/ --

y~

r - ry r-

,,sr, j, _p V2 ,

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~

w 5 t1C

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m .

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m WN p toc < , 3 i

/ < - >-

aaa - ,

, o ~ #

. t stCNAt ssrtsFRgpg) ,

7 3 - 37 FIGURE ' ' "

FUNCTIONALCONTP0EDIhhRAMCONTROLROOM l MAIN AIR INTAKE ISOLATION VALVES .

CON 081 ION CONTROL ACTION M SUL T ANT MOM 110R LOC *

>, A TROL Rn m4h . . w gglgTlAfg C/kg ' CR AIR IMIME ADIATION Hlel Q' y g

. ggg,ggcuLg9sg s] _

FrLTRATeod W ,

cm S- A

, TROLRMRMk AIR INTAKE

-t ens j

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No.F 0 .

CHLORINEPRES) '

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4 '"

al"';n.j m&

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tci 11 > a ii 'q

[%fJ54_Mh .] ?_ ..---.. y -.- _ .m. _ . . . . .._ , , _ _ ,__ ., .

l._,.. I., l_,. ce

,(sudtMmay '

~ J kg / PUSHOUTTON _

CLOSE F AND >

c5 '

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> ^"" O

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AUTO D

m

< H>

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f

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Ssets j( con:ROL SMITCH CLOSE

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/

f 4 Hk _g

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l t0C= T( / <r$- aa0 -

m

- A en SICHAL FROM 5$rL5 j

\ - 1.3 - 18 o.

FIGURE 7.f,-23 FUNCTIONAL' CONTROL DIAGRAM CONTROL ROOM

~ . REMOTE AIR INTAKE ISOLATION VALVES O

o -

CODOIT10N CMTR WIM E CGCIN ~~

m ONTROL RIA INTREE 4e>M RM mal Y. - 0 O ,

10NAL PRESENji -

7 NOT M LOC

+ R U -

M

~> " EpEpeln T OPEN q E"

RGClK -_

sov vRLvf OMT.R RM RM m BG.FC SI L ESE

+ E8ERSIN I H

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= -

CA a < R CR CR CONTROL k >

( SWITCH CLOSE [ >"

'/,

. ( =a ) ,JR 2 9 @ > is

^

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C580NAL FROM) ( h

~

REMOTE

+

SSPLS j e

40C CONTROL k -

( SWITCH CLOSE [ h'--

l

\ >

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e LOCRL

( OPEN

/ <+

~

R CR CSICHALFROM)

SSetS .

, 4 n ;

e

- 2 3 - 19 .

FIGURE 7.040 :

g- FUNCTIONAL CONTROL DIAGRAM CONTROL ROOM -

N FILTER UtilT AIR INTAKE VALVES

?

C C R

O

,

O L M O

L " a C

@qs T

I M

O r 7

H m"

,= =

N E S

E O P L O EC C VF L.

T AO N T VM A IA N T

L U

MI OA A

T.

E V

S E

E R 2 l

n i

e V G R O S D E

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E.E m" m-m"

,p

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=_-

O = o TT NI ON CU S

2 MCE i AAV RVL

'd 5 GHA '

T V H O N

32 A I &

l 0

i C

A

? d3 ,5 7 7LSA .D TKE OUT L l ERAN l O RTiI R

T N

O C 0 -

7 0

_A

+

Q i UNX GOER I C F

LI AA RA I

< N OE I D TI

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> > UU l FO ii I

= " - " "

=*- E :

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C, g E a Ma O S g

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i lM

'f se i f sP i A L A C

OM T

T R IR L

N ssi k

'5 a s~ e R0 s n g I

A S I

1

( -

1

e S '@

. u o 7 @

E s %

O y 8

b gg O g al g* < g4

% E 3 > J T o

a be1 u

3 a

y a gg e 2 fh gg s,

- ae

( - N .3 g I o co E *w l o u o a N3v2 A e

a f r

' b,a4. U ot i

)2<

Ebb 9

D 22 O Qn t- -

g t.

Eg*h J =2 ~

i 756 I d W fhk h i

. e,

-wM 2 2 _e EE h '045 U V W '

, , )

t 8 9 3

.Q O

T o Ob D 3 h

$i h 2 h

.- - - - -e as

[!

3 o/ d es $ ., ,

a3 y

BE !

8h l . E5 i

. 3s Oo I d I 9

3 d I O () ~l l %>

i i ,

J O

---q . U- K d O g ---.~-

y *

- 5 4

\ ,

I. CapabIIIties for remote shutdown ero pravided, shout d the Controf Room

become uninhabitabis.

J. Capabilities are provided to monitor the bypass or inoperable status of components in accordance with NRC Regulatcry Guide 1.47.

K. Capabilities are provided to assess plant and environs conditions ,

during and following an accident. '

7.6.4.2 DenIgn Da erIetIen Instrumentation and controls are provided for the safety-related HVAC Systems as described in this section. For a complete description, including process and InstrtaentatIon dIagrans, refer to Section 9.6. Functional Controf Diagrass for Heating, Ventilating and Air Conditioning instrumentation and Control System are Identifled in Figures 7.6-12 through 7.6-34.

7.6.4.2.1 control system A. .Enns .

1. All f ans in safety-related HVAC Systems are provided with remote manual controls in the Contrcl Room.

2. ' " "- ----a+ ' - ^* * = Aaa"'"-

A l l f an . N ac a;nt:! r::^ C' == ; !r tit:r F:::, : d '.'n' ^ Cr' r F=a*. ::r"'t; I. F:::

,~

u.

y _ -- m .+ . v o i .,. * --- 4-a , are provided with local manual .

controls on Local Panels.

3. Automatic control of f ans is illustrated in the Functional Control Diagrans. Typically, f ans will start autanatically under any of the following conditions:

I. Start demand from the Diesel Generator Loed Sequencer will ,

start fans;

11. Low air flow sensed in the discharge of a fan will start the redundant fan; s

III. Starting of supply fans will start return f ans;

.. Oe..:. e:

^

~.. ! :.; er. .:....;

....; 0...

..; ~ ~..l"#.0

.: 7t;.- 7:=:;

O. . . . . l . ... .. . ; ;

, j e t .;. . ' s. .. {

. e. t.!;t ;;;;' : ;d ! : ^ '" ' 9/

lY

% Unit cooler f ans will start when the safety equipment in the cell starts or when the temperature of the cell exceeds the setpoint; V. .

M, Diesel Generator emergency supply fans will start when the 'j respective Diesel Generator starts.

'~

7.6-5 Amend. 71 Sept. 1982

B. Valves

i. Aii ..;... i.. .... ."!AC 7. .E . r .,'J.J .lth . ;. . n.;l re...e r r v. +6 e c e +.e o---

2. ; !;;; ;! ^h: :::::;t!:n :1 :: t:! nz:-' ; - 0, 'cr-' , -*';;! y , -

4 : .c h e ,. .a d b, pe;; ; pc ; .- ! d:d '" ' ;;; - :::: = *r:l: ^3

'.:::' ":n: ' t.

4 V nm...,____i 7- -- --- ._. . . . _ _ _ __; .__. .....

c .. 2_..1.<.

er,et :;/d:::b!: :uitch '- ^5: ": ^ :' ":: .

,/. Containment supply and discharge valves will automatically close on a Containment Isolation Signal from the Plant Protection System.

5. C:n^r;: "::: i::!:t' n ;;d .;;!r:_!:t!:n w!!' 5: ' :t:d by :ny em vi the ie::e. as cend:t'en;:

'. C rt.?n :n* ';;::t':n;

. ? :A: p ::: ^ et '-+-Ee;

. TX7: ^:: :t '-tCh:;

7 ,_ .. l sh . d:etlen pre;;nt -t '-t;h:;

..

v. rie..i u i .' .. l . l w i l .n Ir a... OT *r :l "22-C. Damners

1. Dampers used to ' control a system parameter (i.e., temperature, pressure or flow) are energized by starting of the supply fan.

Control of the damper is accomplished by measurement of the system paraneter, comparison of the measurement to a required setpoint and transmission of a control signal by a controller, and modulation of the damper to maintain the required setpoint.

. w i o w. onu . .w . . w w . . ..w. a.. w .y. . wi . . . . n.... v. . . . . .

tem are provided with remote manual controls in the Control Roan local manual controls on I.ocal Panels. These d s will aut Ically assume the recirculation mode (i.e exhaust dampers close d recirculation dampers open) u either of the

~~

following conditio -

1. Containment isolation nel ent; i

. 11. Airborne radiati.on d ted in ulus, RSB Operating Area or the Fuel Handil ll.

3. RSB cleanup ter and isolation dampers will aut !cally assume the RSB nfinement mode upon airborne radiation det in the RS erating Area or the Fuel Handling Cell.

7.6-6 Amend. 71 Sept. 1982

. o 7 . X. Dampers serving supply or exhaust f ans are interlocknd with the operation of the fans they serve and will open when f an starts and close when fan stops.

7.6.4.2.2 Monitorino insten ntation A. Typically, process variables are monitored and Indication is provided

, in tne Control Roca and locally as follows:

1. All valve and damper positions.

2. AlI fan operation status.

I T ._,A L . __ , 2 , r .

I ar . e. r. ., .A. _. ..i. _ . ..-...1 y.

m ____ _, _z,m e.1..._ J .. eka f'ame.W

,1

- _ 2, __t f. __ __.__J

w. . .. w... w..=.. g. 1 - -- --.-- - -'

2 e' A__ .._,A .2_m,k .e an+ ,tnn .te anA I a t s.

.r . . . . . . . . _ - _ - . _ _

4 9 t 4.,.

, - - --- - .o1.n, _-

1 _ ____1. __ r ___, m.,og

..7,...... .___. -. .,..

s e..

i w.., .

.. a .,

.w.

_ _ __ _ __ _ _ _ _ _ _ _ ___t ze,A__ L__L ..A

. . ,,___,r..=,..........

av. .......,.

. __ _.1 w... . , , = . . .__,. . ,. ..s.

. _ 2. ,,____1,_, _ _ _ _ _ . . _ _

+

,, ,...w., w w..... ... . . 7 . . . . . .

t . ~, *_ 2,,,____1, _, _ _ _ _ _ . . _ .

.. . . . . __....._____1

m. . ,__ ,_,

m___ ,n,,,, .._ ,m r_,__

2 .-- ..... - _ _ . __.

_____s.2 ,.

u.. -

a __ e a_ _ s m....,. . , - , .

, , , ,__1_ _. e___ , , , , , , . _ _ , 2, _ _< ____ _,_ _..._2 _,_ __2 __2..__ ,_

.w. .w.... w. . iw .i . . v sw w.1 w . w . . w. p .. , .n.u n.. .i . . . . . -

:e etu ee.

s7. +'r: Outside air temperature.

l ' ?. C0-' :! "er ::! : ' r:t: :! '-t:E: :'!:::t' j ?:: ! fe-i ._s,__..... _____ ,_2,___ .2 .... ......__

.---. . - ,__- , . - - . - . - _ ' ' ' r ' ' ' ' - - - '

., n____ . __ _ __ . . _ _ . . . . _,

,A , ..r. ww i . u i . ww . .

w.ww..

wy .y. .

3i..... ....n u..w .w.

www.. , . ... w.-

..,. . . _ _ _ _r--

r . . . _ _, _____ __

2, ____1,

,_1 _ , _ _ _ . . _ 2, _ _ < _ _ _ , , _

i f..._.,____. ..w,..

y,, - - --- . . - _ . . - - - , - _ .

7 , , . , , , , . . g.

B. Typically, process variables are monitored and alarm annunciation is provided in the Control Roan and locally as tollows:

1. Motor thermal overload, high vibration or air flow low for each fan.

, _e 2,,4 e.

- m,.11.._._._._.1.

. . w.

_ _ _ _ _ . _ _ L

,. . . . . . ,_L.

.f w-. . . ~ . - .

___L _ k . .L

. -_ . n. A

..pAeg an+ tem 411+ e .nf+ ,

M 7.6-7 Amend. 71 Sept. 1982

7

,- , ;.? . .

e. ,

- = f .

[s

, j 7, I. Unit cooler or hVAC unit supply air temperature high or air temperature entering cooling coil low. ;

.: . _-:';, r : ':, o': '- . - '- = r:d!:t!:n ; ::: t ' " n'r:l n--s-- e:r. ; r z t; :! '-t er. ,.

. /1 I. Control switch in the local mode (Control Roan only alarm only).

C. Typically, process variables are provided as inputs to the Plant Data Handling & Display System as follows:

t

1. Control Room and computer room humidity.

2. Coniainment -dlf f wential pressure. , ,s -

i

3. Annulus dif f arential pressare,'_'

i ,,- .

4. .1SB confineme.it dIf ferontIsi . prossure (four dIf feront ceiIs).

7

5. Motrol Room dif forential pressure.

- t

6. Air temperature entering and leaving each,filt'er unit'./

~

j' 7. Air temperature entering and leaving each HVAC unit.

[ ,- .. 8. Cell temperature of each area being serviced by a unit cooler or ,

t i HVAC unit.

R. ,

9. Inoperabie or bypass status of components.

/ ,

1 D. The follow!ng process variables are classified as ' Accident Monitoring variables and are used to assess plant and environs conditions during and following an accident:

/ 1. Annulus to atmosphere dif f erential pressure. I r.

l 2. RSB confinement to atmosphere differential pressure.

3. HVAC units discharge air temperature.

4. FIIter units adsorbent. fIltg ie, wing air temperature.

5. HVAC and filter units air f' low )ow.'

6. Damper and valve pott'tlon '19dication.

t .-

i. 7. Fan operation status Indication. ,

./ 7.6.4.3 Desle_n Analysis j The HVAC Instrumentation and Control System is, designed to perform the functions described in Section 7.6.4 while meeting the criteria !!sted in Section 7.6.4.1. All HVAC l&C circuits shall meet the requirements of Section 7.1 with the exception of alarm circuits (sed inputs to the PDH&DS which are 7.6-8 Amend. 71 Sept. 1982

, e' _.a.- -

_* ___________A_

l i

5 8 5 5

NW I 5 '

3% 2

{ . 5 r5 n g- 8l=" 'I' i5 i, ; l!!

\

n n T n e:

h 5

?!g Tn (a a n n n =%

i!$ g 85g C"o 3

"i l g 8 %] -

(

O/ S Y '

j ( [a 2

5 gsm-% e-v\s e.

g!

E I 5

h t;

$sE E dia 1*

!g"I W r;*s vv v n

Bf!

i try "O

g V

Amend. 71 Sept. 1982 .,

7.6 33

C- C C .

. * ** g g enw. teONS TW COND111ON CONTROL ACTION cm A

C o'v T.N Yao ) x + ((h,'

c, - / .

] y gy FAN H

('*scausua1n;I*" \ cu T'

{wounoaaf T

(-( sioe j

gex fj_I-

&n

+

$ oikES !U" $"

f

y g r"nN a scnusu a T / =

CalR F N L O -

/m see -

7

' , g ,

Ay EE uo t'R' FIGURE 7.6-16 FUNCTIONAL CONTROL DIAGRM CONTA!WENT gd CLEANUP SCRUBBER EXHAUST FAN

.e

~ .

cournot acri. asma.vant nouston ca.estion -

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COOLER FAN SERVING CELL CONTAINING CONTAINMENT CLEANUP EQUIPMENT

NOTES RESUL T ANI NON110R I, KET OPERATOR SMlfCHES

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(_ ' .-

E Amend. 71 Sept. 1982 1

7.6-54 l

i l

item 52: Discuss Remote Shutdown W

Comment s: ProvIdo item by item response to NRC positions on RMS. Revise QR 421.17.

Resol ution: The itemized responses to NRC positions on RMS are attached. The amended QR 421.17 is attached.

i nWSSE1D

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\

1 CRBRP REMOTE SHUTDOWN DESIGN C0W ATIBILITY WITH 15C8 STATEMENTS OF GUIDANCE FOR INTERPRETING CRITERION 19 of 10CFR50, APPENDIX A !

1. statement:

The design should provide redundant safety grade capability to achieve and maintain hot shutdown from a location or locations remote from the contml room, assuming no fire damage to any required systems and equipment and assuming no accident has occurred. The remote shutdown station equipment should be capable of maintaining functional operability under all service conditions postulated to occur (including abnormal environments such as loss of ventilation), but need not be environmentally qualified for accident conditions unless environmental qualification is required for reasons other than remote shutdown. The remote shutdown station equipment, including indicators, should be seismically qualified.

Reply:

Safety grade controls are provided for each of the SGAHRS loops A. B and C. These redundant sets of controls are located in separate cells on the 836 foot level of the SGB-IB. Fire or other damage in one cell will not affect the equipment in the other cells, thus redundancy for heat

. removal is provided.

The redundant SGAHRS instrumentation, the RSMP equipment and other I&C equipment involved in remote shutdown will be designed to operate con-tinuotsly ir, an ambient temperature of 120'F. The instrumentation and control cabinets do not require forced ventilation. So long as the ambient temperature of the equipment cell does not exceed 120*F loss of ventilation to the cell will not affect the operation of the equipment.

The SGAHRS I&C cabinets, controls.and . indicators will be qualified to 1E requirements. Other.. control equipment wi,11 be IE or non-1E in accordance

. . . .. with the requirements -of their normal plant function. - -

. The remote shutdown' monitoring panel will be seismically qualified'.

~.

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2. Statement:

Redundant instrumentation (indicators) should be provided to display {

to the operator (s) at the remote shutdown location (s) those parameters I which are relied upon to achieve and verify that a safe shutdown con- l dition has been attained.

I Regly:

Redundancy is provided by separating the A. 8 and C loop SGAHRS I&C electrically and physically such that failures in the equipment for one loop will not affect the other loops or the capability to remove heat from the plant. Parameters displayed on the SGAHRS panels that are relied upon to achieve and verify a safe shutdown condition are listed in PSAR Section 7.4.$1.4. Similarly, the RSMP will provide separate indications for the A. 8 and C loops for the PHTS. INTS and superheated steam parameters.

Separate indications will also be provided on the RSMP for the electrical parameters of the Division 1, 2 and 3 diesel generators. Parameters dis-playedontheRSMParealsoprovidedinSection7.4.Y.1.4.

3. Statement:

Credit may be taken for manual actions (exclusive of continuous control) of systems from locations that are reasonably accessible from the Ramote

(

Shutdown Stations. Credit may not be taken for manual actions involving jumpering, rewiring, or disconnecting circuits.

Reg.iz:

i Remote shutdown operations on CRBRP do not rely on jumpering. rewiring or disconnecting the wiring of circuits. All of the I&C equipment used for remote shutdown operation can be switched between the normal mode and the local mode of operation by built-in transfer switching capability.

Operations to achieve remote shutdown are centered in cells 272A 2728 and 272C and nearby in cell 271 on the 836 foot level of the SCB-IB. ,

Local surveillance of control rod drive, mechanism (CRDM) controls, position

/8

~ *

'; ~ -

.'. - w . .: .: ... . . .

. ..:. ... ;_ . .. :. . i .. . . e > .

4- .n A. .r .

indicatsrs cnd scram break 2rs can be perfomed on th2 765 feat icval .

cfth2c:ntrolbuilding(CB). 5urv3111anco of other plent systems, when required, will be accomplished at their local I&C panels.

4. Statement _:,

The design should provide redundant safety grade capability for attain-ing subsequent cold shutdown through the use of suitable procedures.

R.eply:

The SGAHRS is a safety grade system designed to remove decay heat from the reactor plant. The SGAHRS will be used to achieve and maintain hot shutdown conditions or, if desired, to cool the plant to the refueling conditions and maintain those conditions. Operating procedures for the SGAHRS will permit achieving and maintaining the desired plant conditions during remote shutdown operations.

5. Statement:

~

1.oss of offsite power should not negate shutdown capability from the remote shutdown stations. The design and procedures should be such that following activation of control from the remote shutdown 16 cation, a loss of offsite power will not result in subsequent overicading of essen-

~

tial buses or the diesel generator. Manual restoration of power to shut.

down loads is acceptable provided that sufficient information is available such that it can be performed in a safe manner.

Reply:

The CRBRP design for remote shutdown will permit achieving and main-taining plant shutdown conditions if loss of offsite power occurs coin-I cident with remote shutdown operations. This is accomplished by remote shutdown employing the use of normal plant safety related equipment which is designed totally for all design base events including loss of off-site power. ,

i

6. Statement:

The design should be such that if manual transfer of control to the remote location (s) disables any automatic actuation of ESF equipment, this equipment can be manually placed in service from the remote shut-downstation(s). Transfer to the remote location (s) should not change the operating status of equipment.

Reply:

daarn*a3N The SGAHRS ie the principal engineered safety system usedA remote shutdowg e system is designed to be operated in the local mode (e.g., remote shutdown) or the remote mode (from the control room).

The system design for SGAHRS instrumentation and control system should be consulted for detailed information concerning operating in the local mode (PSAM.ej.1).

Transfer of control from remote to local operation for Nuclear Island HVAC, recirculating gas cooling, emergency plant service water and emergency chilled water systems will.not change the operating status of the equipment nor disable automatic operation of ESF.

Transfer is accomplished by operation of a switch in the Solid State Programmable Logic System local cabinets. This transfer isolates the control room and transfers to local control.

7. Statement:

Where either access to the remote shutdown station (s) or the operation of equipment at the station (s) is dependent upon the use of keys (e.g.,

key lock switches), access to these keys shall be administratively controlled and shall not be precluded by the event necessitating evacuation of the control room.

Reply:

The industrial security system will provide facilities and procedures to permit operating personnel to move within the plant to perform re-mote shutdown operations. The industrial security system should be consulted if details are required by NRC.

+ . 8. Statement:

The design should comply with the requirements of Appendix R to 10CFR50.

Reply:

1 The design for remote shutdown in CRBRP is such that a single fire will not prevent operations to achieve and maintain hot or cold shutdown conditions.

i

--w---- -- - - -- - - - , - - - - -.- .- , - - - , - , , . - - - - -,-,----------m -

y , , . ..:.g .

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} Questfon c1421.17 The Information supplied for remote shutdown (PSAR Section 7.d.8 from outside *

e control roam is Insuf ficient. Therefore, provide further dracussion to describe the capability of achieving hot or enid shutdown from outside the confrol reas. As a alnimum, provide the following Informations

.;g. . .. .

e) ' A table listing the controls and display instrumentation required for hot and cold shutdown from outside the control room. Identify the train essignments for %e safety-related equipment. -

b) Design basis for selection of instrumentation and control equipment on to hot shutdown panel.

c) Lacetion of transfer switches and the remote control station.

d) Description of transfer switches and the remote control station.

e) Description of isolation, separation and transfer / override provisicas.

This should include the design basis f or preventing electrical interaction between the control room and remote shutdown equipment. -

f) Description of control room annunciation of remote control or overridden status of devices under local control.

g) Description of compilance with the staf f's Remote Shutdown Panel position.

Resnons, The response to this question is provided in the amended text for Section 7.4 .(.

('

3 -

QCS421.17 1 . .

Amend. M

..s. .. '.. .'. . July 1982 v

. 3 , . . ... 9, , itsv. :se; . ...

.dk .c.,a. 5: . . Wa6MWv SV. - _ . . _

W '

l 7.4.4 Remote Shutdown System l 7.4.4.1 Deslan Descriotion l 7.4.4.1.1 Function The Remote Shutdown System provides the means by which (1) safe shutdown conditions of the reactor plant can be established and maintained frcm locations outside of the Control Room in the event that the Control Room must be vacated; (2) hot shutdown conditions can be achieved and maintained; and, (3) If desired, the plant can be cooled to and maintained at the ref ueling iemperature. ,

l 7.4.4.1.2 Deslan Basis The Remote Shutdown system is designed to use equipment located outside of the Control Room to place the reactor and plant into a. safe shutdown condition under the folIowing conditions:

(a) The evacuation of the Control Room is not colecident with any other abnormal plant condition with the one exception that loss of of fsjte power may cccur.

(b) No severe natural phenomena such as __

f , tornadoes, hurricanes /

floods, tsunami and sejches from 10CFR50, Appendix A, Criterion 2)doccur coincidently with the d!?;j(% :t of the Control Room, g (c) The plant remains in an orderly shutdown status f ra the initiation of the evacuation of the Control Room to the time that command of the shutdown is re-estabiIshed outside of the Control Roczn.

(d) The remote shutdown operations will be commanded f rom one location and wilI use plant systems operated in their iocal mode to ef feet the shutdown and decay heat removal.

(e) Plant instrurnentation and control systems required for remote shutdown operations will have transfer switches located at the local panels to permit the plant operating personnel to select to operate f rom the local panels while isolating the remote controls or, conversely, to operate f rom the controf room while isolating the Iocal controf s. The transf er of control of a plant system f rom the rerrote to the local mode is annunciated in the control room.

(f) Communications between the Remote Shutdown Monitoring Panel (RSMP), the command location f or rerrote shutdown operations, and the SGAHPS panels and other local panels durirg remote shutdown operations will be by the Malntenance CcunmunIcation Jackirg (MCJ) system utilizing a sound-powered teI ephone. Nui delq&..t , p.y w , j,, _

ha daf.Q ,

9 7.4-8b Amend. 72 Oct. 1982

. l 7 4.4.1.3 R = te Shutdown Doeratlana E m.tB g The RSMP will be located in Cell an of the 836'-0" level of the SGB. The l l RSMP will have Indications (see Section 7.4.4.1.4) from which an operator can assess the progress of the shutdown, and it will be the location from which that operator will command the operation of the plant systems being operated in their local mode to of fact shutdown.

The Division 1,11 and III SGMRS (Sectlon 7.4.1) Iocal panels wIlI be iocated in Cells 272A, B and C respectively, in close proximity to the R$r, on the 836'-0" l evel of the SG8-1B. The SGMRS, operated in its local mode, will be used to control the removal of heat from the reactor plant to achieve and G stabilize the plant at the desired plant temperature (hot shutdown or -T ref uel Ing temperature). The local SGMRS panels will have all of the controls _j l

and Indications necessary to completely control theTstem. All signai s f rom the Control Rom to the SGMRS panels are buf fered to prevent f aults occurir.g in the Control Rom from propogating back to the SGhiRS panels. All SGMRS component controls can be transferred to local at the local SGMRS panels.

Placing the transf er switches in " local" overrides all control functi,ons in the Control Room.

The Division 1,11 and 111 OSIS local panels are located in SGB Cells 272A, B i

and C with the SGMRS panels, and will be operated in the local mode when required to control heat removal from the plant in conjunction with the operation of SGMRS. Isolation of 03iS paneI controf s f rom the Controf Room l

is incorporated in the design. Steam drum drain and superheater outlet isolation valve controls can be transferred to local at the local OSIS panels.

Whenever any SGMRS component control transf er switch is placed in the " local" position an alarm is initiated in the Control Room to alert the Control Room operator. The same statement is true f or the steam drum drain controls and superheat outiet isolation valve controf s on the 05IS paneis.

oubaht4 hetMont.1t.s.h if of f site power is lost coincident wi having to achieve a saf e shutdown condition in th reactor plant f rom o side of the Control Room, the diesel generators will start and f unction I accordance with the design provided :.

by the Building Electrical Power System. Anu 7- :t.- _d ::- 7: 7..

Cnn'" ;t'; with nnaratino and f eedinn +ha df=--' ;; ; " g ,, ,, ; , , o O; ';

l na n --e 7 --- i e ,

na e 73 um .+ tan w* .+ 4'7

. e .- Ye.<t.%v.\

4

% tu hvacated, reactor scram and in the event t the C8ntrol Room m[The operating personnel will moveI to

operation will be Initiated manually.

the 836'-0" level of the SGB where the SGMRS in the local mode 6---+'

will ef" fect I heat removal and stabil Ization of the pl ant temperatures. ..

rmy u z u .; g y e ... 44.,4 u.+___. --; n:. 3f 7 g ,.

l l p x* L,r:tcx. The plant shutdown wilI be directed by the operator at 4he RSMP who will also assign operating personnel not continuously occupied in perating SGMRS to oversee or operate o{Igrg4 ems as required. g Movement of personnel within the plant and access to building cells and local panels wIlI be controlled by the f acilitles and procedures of the industrf el Security System.

%4 mt.h h ios:, of Ara =>Ce swrMaes w lI be, J %, A L % l.al D % d hem 5% cw also loc. cq eked f 7.4-8c Amend. 72 Oct. 1982

(Insertto7.4.f.1.3)

Primary sodium outlet temperature indication can k used for confirmation of reactor shutdown c.coling, ,

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7.4.4.1.4 Eautoment Deslan ,

The RSMP is the only piece of equipment provided by the Remote Shutdown Sy stem. It will be a vertical sided, non-Class IE cabinet assembly containing meters and a phone Jack panel. The meters will receive buf fered signals f ran the infilating systems and, thus, do not require transfer sultches to isolate them f rom the Control Room. The phone Jack panel will permit the operator at the RSW to communicate with the five NSSS or Nuclear Island buildings by means of any of the three E,J circuits provided in each of the buildings. In addition, communications among the bulldings can be estabt Ished through the phone Jack panel on the RSMP.

The Indications provided on the RSMP are as f ollows: ,

o For each primary heat transport system loop, .

1 - Pep outlet sodim tMnperature indicaton (3 total) 1 - Reactor inlet sodlum temperature Indicatiott (3 totel) 1 - Sodim pump shaf t speed Indication (3 total) o For each Intermediate heat transpori systam Iocp, ,

1 - lHX outlet sodium temperature indication (3 totel) 1 - IHX Inlet sodium temperature indication (3 totel) 1 - Sodlun pep shaf t speed Indication (3 total) o For each superheated steam locp, 1 - Temperature Indication (3 total) 1 - Steam flow Indication (3 total) t o One reactor vessel sodium level meter (long probe) o For each Diesel Generator (3 total) 1 - Wattmeter 1 - Frequency meter l 1 - Varmster l

1 - Voi tweter w Ith ph ase sel ector sw itch 1 - Ammeter with phase selector switch in addition to the f oregoing Indications, other indications used during remote shutdown operations that are not on the RSMP will be available as f ollows:

o SGAHRS Controls and Indicators used for the operation of each SGMRS division are

located on the three seperate SGMRS panel s In cells 272A, B, and C. Each

- SGMRS division is separate and redundant f rom the other divisions. See the response to Question CS421.04 for additional Inf ormation about SGMRS division assignments.

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. G 7.4-8d Amend 72 Oct. 1982

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The fof IowIng controf s, Indicators and alarms are on each SGMRS panel."

ControfIars Auxillary Feedwater Flow '

AFW Steam Turbirs Steen inlet Pressure s P/CC Inlet Louver Position PACC Fen Blade Position Steen Drum Level Steam Drum Vent Superheater Vent ' !

Analoo indicotors <

Protected Water Storage Tank Level Protected Water Storage Tank TemperLture '

Auxil iary Feedwater Flow Auxillery Feedwater Pump Discharge Pressure .

Steam Driven Turbine Steam inlet Pressure '

Steam Driven Tubrine Speed ,

PACC Outlet Air Temperature :

~

PACC Outlet Water Flow and Temperature PACC Inlet Louver Position PACC Fan Blade Pitch Position Steam Drte Pressure and Water Level -

t Annunciato1s ' s 1 Protected Water Storage Tank Level

' FWST Temperature AFW Supply Temperature

! i Steam Driven Turbire Speed

,/ , Driven Turbine Steam inlet Prewure Steam Driven Turbire Dearing anc Lube Oil Teperature t

e High Motor Bearing Temperaturer, 1

SGMRS Initiation Diesel speed and f uel oil Indications will be available at the diesel o

generator local control panel s in the Diesel Generator Buil ding,Ge .

f

Each Indicator, alarm and controller is repeated on each of the SGMRS panel s except for those associated with the AFW pumps. Penels A and B have the control s, alarms and Indicators f or motor dr iven AFW pumps A and B; Panel B -

has those associated wIth the steam driven AFW pump.

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7.4-8c Amend. 72 Oct. 1982 i

7.4.4.2 Design Analvsts l

The Ramote Shutdown System provides the R$r fr:n which an operator can assess the progress of the plant shutdown and command the local operation of the plant systems (prir.ortly SGMRS) to ef fect the shutdown. It should be noted that the PACC subsystem of SGMRS is automatically Initiated by all reacter :

trips, and It remains in operation for the duration of the plant shutdown or as.long as the reactor generates significant decay heat. i I

The Remote Shutdown System imposes no special requirements on the plant j systems, but takes advantage of the fcilowing system design features:

o The ability to operate in both local and renote modes wl'th isolation fran and annunciation in the Control Room when operating in the local mode.

o The redundancy diversity, separatloa, Isolation and rollabilIty of the sef ety grade systoms. .

o The design and location of saf ety grade systems equipment that minimize the probabil ity and ef fect of fires and explosions on the abil ity of the systems to perf orm their saf ety function.

o The redundant safety grade SM:~tS provides the, capabil Ity to achieve and maintain hot shutdown and, if desired, to cool the plant to and maintain the pl ant at ref uel ing conditions, o Wtb transf rri ~ GMRS t iocal the for anualI rts SC S. On e . art MRS a cally i s those .eters sed tc ove de y heat.

Tip RSMP i a non-Cl 1E Seismic s 111 as and there is not si bj d to the se rati requir ents IEEE -19 or t the Isml qi al i [I, cati r u t rarnents

E 344-19 to any other i Si dms l is ed in Table 7.1-3.

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7.d-8f knend. 72 Oct. 1982

attacnment to LEM-u2-094

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/ ITEM Sbt PACCs Instrumentation and Control Action: Update response to Question CS 421.26 in order to

/

identify which instrumentation and control is

/ safety-related and which is important to safety.

Resolution: The amended response to Q421.26 is attached, l

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- Attachmsnt to LEM-82-093

/ Page 2

/ Ouestion CS 421.26

/

In the PSAR, Section 7.4.1.1.2 discusses the Protected Air-Cooled Condenser (PACC) and how air flows through it is controlled by a combination of fan blade pitch and inlet louver position. The staff requires a detailed discussion of this instrumentation and in particular the method used for fan blade pitch indications.

Response

The outlet louvers have discrete open and closed position sensors. These provide indication at both the local control panel and main control panel in the control room.

The inlet louvers have both discrete open and closed position sensors and a continuous position sensor. The continuous position sensor provides feedback to the louver control. Both types provide indication at the local control panel and at the main control panel in the control room.

The fan blade pitch is sensed by continuous position sensors for both control and indication. The indication is provided at the local control panel and at the main control panel in the control room.

Both the discrete and continuous sensors are integral to the actuator. The discrete sensors are roller switches activated by a cam and the continuous is a potentiometer.

This instrumentation discussed above is Class 1E with the exception of the indicating lights.

All instrumentation and controls necessary for the PACCs to carry out their intended safety function is safety-related.

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- Item 65- Re9. Guide 1.97 i Comments: Chapter 7 should refer to QR 760.6 for Reg. Guide 1.97 response (Nov.18-19 meeting notes, item 17).

Resolution: Reference to QR 760.6 is included Ira amended Chapter 7 attached.

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7.5.10 containment Atmosnhere Temnerature

, , The objective of the Containment Ahnosphere Tamperature Monitoring System is to provide Indication in the Control Room of the ahnosphere temperature inside the containment building.

7.5.10.1 Design Descriotion The temperature instrumentation consists of two f ully redundant and independent channels. Each channel consists of two thermocouples mounted on the Rm dome, '

with each thermocouple providing a signal to conditioning Instrumentation in the SGB. The Instrumentation sends a signal to the Control Room where Individual readout is provided. This instrument is also required to perf orm functions for events which lie beyond the design basis for the plant. This Instrument is f urther discussed in this capacity In Section 2.1 and 2.2 of Ref erence 10b of PSAR Section 1.6.

7.5.11 Accident Monitoring instrumentation The Accident Monitoring Instrumentation is an Integrated set of inctruments made available to assess plant end envirots conditions during and following accidents.

(

7.5.11.1 Hascristiqc lWSERT ) m.

J.

Accident Monitoring parameters are monitored to perform

the f ollowing f unctions:

i o Provico primary information to permit manual Verlable Type A actua1 Ion of saf ety systems.

Type A variables monitor the primary information required to permit the control room operator to take spect fIc nanually controlIed actlons f or which no automatic control Is provided and that are required f cr saf ety systems to accomplish thelr safety i

functions f or Design Basis Accident events. Primary information is that which is essential for the direct ,

l accen;,1!s'.mont of the spect fled saf ety functlons; it l

does not include those variables that are associated i wIth contingency actions that may also be identified in written procedures.

o Indicate that saf ety f unctions.are being accom- Variable Type B l ;

plished (i.e., reactor shutdown, core cooling, f contain6nent Integrity).

i Type B verlables provide Information necessary to ,

Indicate whether plant saf ety functions are being l

accomptished. , .; ;

i 7.5-33c Amend. 71 i

Sept. 1982

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l (3nsert to 7.5.11) i A discussion of the f unctional requirements and general design l requirements is provided below. Additional prel iminary description of the appl Icaton of Reg. Guide 1.97 is provided in Question Response CS760.06.

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Attachment to LEl:-82-093 Paga 3

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, ., ITEM (,20) Local Control of Auxiliary Feedwater System (AFWS)

?

Action: Provide update response to Question CS421.18 in order to describe the capability to turn off the AFWS manually at the local SGAHRS panels.

-Resolution: The revised response to Q421.18 is attached.

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Attachment to LEM-82-093 Paga 4

/

, Ouestion CS421.18 Provide documentation that verifies that control provided for safe shutdown from outside the control room will include the capability for reset of any engineered safety features equipment having a high likelihood of being automatically initiated during the normal transient occurring following a manual reactor trip.

For example, the auxiliary feedwater system may be in this category.

Response

The Auxiliary Feedwater (APW) and Protected Air-Cooled Condenser (PACC) are subsystems of the Steam Generator Auxiliary Heat Removal System (SGAHRS). The AFW subsystem is not initiated during the normal transient occurring following a manual reactor trip. However, all AFW subsystem component control capability can be transferred from the main control panel to local panels by transfer switches located on the local panels as described in Therefore, the AFW PSAR Sections 7.4.1.1.6 and 7.4.3.1.3.

subsystem can be reset from the local panels when steam venting ceases and decay heat is being removed in a closed-loop mode by the PACCs alone. Throughout the decay heat removal mission, the operator can manually start and stop the AFW subsystem at the local panels as necessary to maintain steam drum level.

The PACC subsystem is automatically initiated by all reactor trips, and it remains in operation for the duration of the plant shutdown or as long as the reactor generates significant decay heat. The PACC has the capability of being reset at the local panels. Then, the operator can manually start and stop the PACC units. Once started the PACC units will automatically control steam drum pressure the same as in the main control room.

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ML20028B927

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