Text

Submits Revision 54 to Fsar,Constituting Amend 87 to Application
	ML19308A276
Person / Time
Site:	Zimmer
Issue date:	02/28/1979
From:	Borgamm E; CINCINNATI GAS & ELECTRIC CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 7903020326
	Download: ML19308A276 (30)
	v • d • e

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T I I I.: CI N C I N N ATI GAS & 1:I I+:CTi tI(' C( ).\l P.\ N Y .

E.A.90AGMANN

. c! .o r siot at - t%. tr a h a Docket No. 50-358 February 2E, 1975 Mr. Earold Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RE: WM. H. ZIMMER MUCLEAR FGWER STATION -

UNIT 1 - AMENEMENT 37 - SUBMITTAL OF REVISION 54 TO THE FSAR

Dear Mr. Denten:

The Cincinnati Gas & Zlectric Company on behalf of itself and as agent for Columbus and Southern Ohio Electric Company and The Dayton Power and Light Company hereby submits Revision 54 to the FSAR. The information submitted censists of FSAR change out pages. This revision constitutes Amendment 87 to the Application. It is documented in the FSAR as Revision 54. Sixty (60) copies of the information are trans-mitted.

Pursuant to 10 CFR 2.101, we will within ten days of this filing furnish to the NRC an affidavit reflecting that distribution of appropriate copies nas been made to John W.

Cashman, M.D., Mr. Gary Williams, Mr. Charles M. Hardin, Brock-haven National Laboratory, oak Ridge National Laborn Ory, and the Atcmic Industrial Forum.

A certificate confirming service of Amendnent 37 upon Mr. Harold B. Bissantz, President of the Board of County Commissioners of Clermont County, Ohio, Chief Executive of the County in which the facility is located, will be filed 79 0 3 02 0.3c26

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To: Mr. Harold Denton, Director February 28, 1979 Re: Wm. II . Zimmer Nuclear Power Station - Page #2 Unit 1 - Amendment 87 - Submittal of Revision 54 to the FSAR when acknowledgement of the receipt thereof has been obtained.

Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By E. A. BORGMANN

[*#

Vice President - Engineering Services and Electric Production EAB: dew cc: Charles Bechhoefer Glenn O. Bright Frank F. Hooper Troy B. Conner, Jr.

James P. Fenstermaker Peter H. Forster William J. Moran J. Robert Newlin William G. Porter, Jr.

James D. Flynn Thomas A. Luebbers Stephen Schumacher John D. Woliver State of Ohio )

County of Ilamilton)ss Sworn to and subscribed before me this ?? N of February, 1979.

day O ) ' n - a,v 7 [' Lh, [.v_,-

() Notary Public I"' T ' " ET L'. I-:USEa L * ;; u f'r C: ~ : 1 b , a A. 13, 1,4

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TIIE CINCINNATI GAS & ELECTRIC COhll'ANY T '

E. A. SORGM AN N viC f P.g StOg nt. g nee,s.g g es8e4 Docket No. 50-358 February 28, 1979 Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RE: WM. H. ZIMMER NUCLEAR POWER STATION -

UNIT 1 - AMENDMENT 87 - SUBMITTAL OF REVISION 54 TO THE FSAR

Dear Mr. Denton:

The Cincinnati Gas & Electric Company on behalf of itself and as agent for Columbus and Southern Ohio Electric Company and The Dayton Power and Light Company hereby submits Revision 54 to the FSAR. The information submitted consists of FSAR change out pages. This revision constitutes Amendment 87 to the Application. It is documented in the FSAR as Revision 54. Sixty (60) copies of the information are trans-mitted.

Pursuant to 10 CFR 2.101, we will within ten days of this filing furnish to the NRC an affidavit reflecting that distribution of appropriate copies has been made to John W.

Cashman, M.D., Mr. Gary Williams, Mr. Charles M. Hardin, Brock-haven National Laboratory, Oak Ridge National Laboratory, and the Atcmic Industrial Forum.

A certificate confirming service of Amendment 87 upon Mr. Harold B. Bissantz, President of the Board of County Commissioners of Clermont County, Ohio, Chief Executive of the County in which the facility is located, will be filed

To: Mr. Harold Denton, Director February 28, 1979 Re: Wm. H. Zimmer Nuclear Power Station - Page #2 Unit 1 - Amendment 87 - Submittal of Revision 54 to the FSAR when acknowledgement cf the receipt thereof has been obtained.

Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY

' ~

By E. A. BORGMANN Vice President - Engineering Services and Electric Production FAB: dew cc: Charler Bechhoefer Glenn O. Bright Frank F. Hooper Troy B. Conner, Jr.

James P. Fenstermaker Pater H. Forster William J. Moran J. Robert Newlin William G. Porter, Jr.

James D. Flynn Thomas A. Luebbers Stephen Schumacher John D. Woliver State of Ohio )

County of Hamilton)ss Sworn to and subscribed before me this 22' day of February, 1979.

% mmtNotary i

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n/.Public A J a/ v 7...-., ,,. ._3

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ZPS-1 REVISION 54 FEBRUARY 1979 WM. H. ZIMMER POWER STATION INSTRUCTIONS FOR UPDATING YOUR FSAR Changes to the FSAR are identified by a vertical line in the right margin of the page. To update your copy of the ZPS-1 FSAR, remove and destroy the following pages.and figures and insert pages and figures as indicated.

REMOVE INSERT VOLUME 3 Chapter 6.0 Pages 6.2-82 through 6.2-93 Pages 6.2-82 through 6.2-93 Pages 6.2-95 through 6.2-95c Pages 6.2-95 through 6.2-95c VOLUME 4 Chapter 6.0 Cont'd Pages 6.4-2 and 6.4-2a Pages 6.4-2 and 6.4-2a Chapter 7.0 Pages 7.3-22 through 7.3-26 Pages 7.3-22 through 7.3-26 Pages 7.3-29 and 7.3-30 Pages 7.3-29 and 7.3-30 1

ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-7 SIGNALS TO INITIATE VALVE CLOSURE SICNAL DESCRIPTION A Reactor Vessel Low-(Level 3) Water Level B Reactor Vessel Low-(Level 2) Water Level C Main Steamline liigh Radiation D Main Steamline liigh Flow E Main Steamline Low Pressure 54 F Main Steamline Tunnel Leak Detection (High Temperature or 45 High A Temperature)

G Shutdown Cooling Reactor Prcssure liigh 11 54 J* Condenser Vacuum Low K Reactor Water Clean liigh Dif ferential Flow 45 L Drywell Pressure liigh M Plant Exhaust Plenum liigh Radiation 45 N RWCU Leak Detection (High Temperature or High A Temperature)

P liigh Steamline Pressure 14 Q Low Dilution Flow or High Leakage Flow R RIIR/RCIC Combined Steamline High Dif ferential Pressure (High Flow) I 54 S RilR Equipment Area Leak Detection (111gh Temperature or fligh t2 Temperature) 45 T RHR Shutdown Cooling Flow liigh U Reactor Vessel Low (Level 1) Water Level

Bypassed when turbine stop and bypass valves shut, reactor pressure less than 1050 psia, and bypass switch in the " Bypass" position, and 54 the mode switch is in Startup/ilot Standby, Shutdown, or Refuel positions.

45 1

6.2-82

ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-7 (Cont'd)

SIGNAL DESCRIPTION V RCIC System 45 (1) Steam Tunnel Leak Detection (High Temperature or High ATemperature) ,,

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(2) RCIC Equipment Area Le k Detection (High Temperature or High a Temperature)

(3) High Steam Flow 54 (4) Low Steamline Pressure (5) High Turbine Exhaust Pressure l W High Tamperature at Outlet of Cleanup Non-Regenerative Heat Exchanger or Standby Liquid Control System Actuated 45 X (1,se Through Electrical Interlocks with Other Valves or Pt.mp Motors 45 Z Refueling Floor Exhaust Radiation - High RM Remote Manual From Conirol Room 6.2-82a

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SUPP FtW. SPRA Y "B M-45 c.c. 56 GA TE AUTO RM shui SH01 RUR "C" HIN FwW BYPASS M-4t, o.c. SG GATE RM MAN CHUT SHOT RM2"B"MID Flow By/MCs N-4C o.c. 56 GATC LM MAD SHOT SMOT RHR. Hy "B" cenDVDSATE H-44 0-c. && G476 A oTo RM SHUT GNUT RME "B" FULL Flow f flosH H-44 o c. GG GloBC Avro PH S60T $807 RMX "C"Fulb R.CW f Flush M44 c .c . SC, GLCBS AUTD RJ1 GHOT SHOT HPcs rest u uE M-W o.c . S(, CrosE Avro RM SHOT Sfh/T HPCS M!N FLO W M 47 0.c . 54 Q4TE RM MAN 3 HUT CHUT l

caTeol xco news mTwr lM.qg - - - - - - -

l l

DEYWE2L GGoir sont 02. I H- At9 0.c. 54 GLcBG AUTO RH CPSV 8PEU DeYWCtl EQUIP. $ UMP DR. iM-49 C.c. S4 G LOBE AUTO RH l DPEN CPEN I

VKYwrLL flock SvMP OR. lM-50 o.C. SC GLOBis 4070 RM CPEN CPED ORYWttL PLDog $dMP DR. lM-50 0.C. SG Gle8 6 4UTb RM DPEN CPED 6

CYCLEO CCCCED GATG M- 51 1.C . SC GATE MAD. -

L.3 RUT L. shur

. CYCLED CODDGDGATE M-Si 0 C. El G4 TE M42- ~

L. SHOT L. SHUT 12S TR AIR - Cour "B" M-52 D.C. 57 GLOBG RM M40. OPED CAM l

spArg H.5 5 - - - - -

NYD206fA G4S CCDTReL M-5y D.C. SG GATE RH MAN dHOT SHUT HYP20680 Gas cont 204 lM-54 0. C. SC GATE EM MAN SHOT GHUT

~ ~ ~

s SPARG M-55 ; ~ ~ ~ ~

l

.I

. I (Cont'd) ZPS-1 REVISION 54 3 FEBRUARY 1979

'AI A' !- ' I T I O*: [ c, p .4 4 &

ff CONT /.INMENT A h g c' t G N A

/s ,$ I SOL /sT 10N 'E_ A 0 pD

.C 6'y- [G6

., g ,0 REMARKS

.- e

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JJ q0' y n-S I G':AL vy 4% so' [ 4' .5

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3 g q4

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b 4 x c,f G O &

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. . g .,

38 7

l sHor l char B, L 2 Y2 s7p no e i Y stE acres it, t 8 -

>4 GHur SHUT B, L 2 Ye srp. l Mo 8 i Y seg 9075 fi l

SHOT l SHUT Bi L 2 Y1 STV Ho B 1 Y sEs NOTss it,1 s SHUT l sHor B, L 2'z / sTo. No 8 i Y see po Te it ik sHvT l.3 HUT -

t Yz ~

90 8 1 Y S//07 L.3H07

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2 YL ~

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L STO YES B L Y yy,g .., n yyS7

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2 GTD. Yes 8 1 Y Z vatves tu m u itEt itM-3/f0T AS /5 ~

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t

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TABLE 6.2-8 gg f [ ACTUATIM [

G: : . .,

4 // g gq$.T /,

<F + v lit 1C ISOLATED q" 9 Qg4 4 f7 jj /I ' f7 syfk' y$ +h% 5

= f? g.0 ' :

~

Q SBLC M-54 f.c . 55 cyscx RGy. flow -

SUvT SRUT GBLC M-54 d.c. SS cycck Rgy. FLGN -

CHui S Hv7_

SBL C "A " Disc. M-5& 0.c. SS EX PLce:/vr* CPEN EM ~

31/0 7 SHUT 38L c "B ~ DISC M-54 o.c . 55 GX PLosiv6 CPEN RM ~

CHUT SHUT SBLc BYPMS$ M-56 o.c. 55 Gl08G HA M.

~

lnSH07 L . SHU T SPARE M-57 ~ ~ ~ ~ ~ ~ -

SPARE H-59 - - - - - - -

spAge M-59 - - - - - - -

8PA2C H-60 - - - - - - -

l 3PRRE H-6L - - - - - - -

I spsee l u-42 - - - -

-l - -

sM26 M-G S - - - - - - -

spsge p - 4 <,t - - - - - - --

DW PNEVMArif PURGB M- &S l0)_g, S4 GL og & Ai,'ro gm oppy opgg SPARE M-4C - - - - - - -

SA4RC H-67 - - - - - - -

RR A CY&loDER LID E H-48 Oc- 57 GLc8E AC To RM CPEN OPED _

KR A ORA /M L/DE H-48 0.C. 67 GLDBE AUTO KM OPtD OPEP RR A SHo 771.E L/DE H-4f 0 c. 57 GLc8E Auto EM orry oPCD R2 A CYLIMPER LIME M -49 I o.c. 57 Gloss AUTO RM cPep oPEN I

I

,I

1 1

1 (Cont'd) ZPS-1 REVISION 54 FEBRUARY 1979 VALVE IOSITIO!!

.4 p* A 4 A a % n y'.m 4

. f- CONTAINMENT Q

pm 6 f> 'T&a cQ *C 0" 6 l[ .f ff [ ISOLATION Dh ,[ y. p ,y 0 .b REMARKS h

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L V2 -

YES _Q_ i Y M i. SHUT -

1 NO _A_._ L_ Y.'-

t TYM 4" fEST TYPE "A " T2'ST q

H ___

l__ ___ - - - - -

_ __ _ _ TYPE " A TEST TYPE 'A" TEST l 38

- - - - - - - - - Type .A. Test l - - - - - - - -

7ygg. .y n 7,g7 l

TYrs "A" Tes7 TYPE **A ' [EST l Sk S H u 1* Shur C, L, M, z. 11s s ro. Ato B 1 L see Nors y 43

~ - - - -

__ TYPE "A* TEST 7YPf '*4" Thi[

SHOT -

L,6

% STO. No 8 i y SEE NOTE 28 _

_5_gu[__ -

L ,, 8 sit sro. No _B_ i at sec NorE 28 43 K -

4,O t{t STD. No B L,_y_ _ SEE NOTE 28 45 M -

Lr 0 l4 STD. Alo 8 1 L Sff W076 28 6.2-88

6 I

l TABLE 6.2-8 (Co V

gg ;f AC T U RI' 10?. [

J . sT 6 . .

LINE ISOLATED [ $#h g, ; ,

[ g6 D.' $ ,.5 4 q- .h

$5 Y

c

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g. > 4.- ,5 4:

...R L j W uNDER LING H-41 0.C. 57 GLcBS A UTo RH OPED OPEN Q 6 92410 L/D G N-69 0.C. 57 G LDBE A UTO RH CPCA) CPED i

, b SH UTTL E LIME M-41 0. c . 57 GLaB G AU TO RM OPEN OPEP rch 8 CY'l IMOE'R t ING H-49 D.C. 57 GLOBc AUTO RM GPEN OPED

,St CNECW REY. FLOW t;'fEU OPEU PkYWEll IUGTEUMGDT Ss ?- _ -70 _ C' 9%Y WVlt IUSTEUMGNT SufW of-70 0. :'

Q( Glo8O A UTO KM DPEN OPEN SER we4 ktR M-71 1C SG Gle6G MAN.

L. SHUT L. SHUT l SERVICE A/K 5&

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SHUT SHOT RHR RELIGF VENT lH-72 GC SC EELICf ttTR PEEss -

GHur shur I i I

L A* S REllEF VEMT I N-73 0.C. 54 RSLIE'F DVER PRf53 -

5 SHOT SHUT RHR RettrF VGWT l M - 73 0.C. ML RELIEF evac P/2FS N ~

lGNUT 3 HUT LHK RELIEF VENT I M- 73 0.C. .S G 25Lle'P GVF2 PE233 ~

l3 HUT 3llof RNR VENT HX-A lM-73 0 c. SC globe RM MAW SHUT SHCT RHR VtHT HX-B M-73 c. c . 66 RELIEF On~R CeE55 -

SHOT SMOT LPCS EElltf vtHT H-73 0 C. SG REL/6F D J ER. P'2 E SS SHUT St/UT OtYtJEM cH/f4ED WTR."6" l M-7'l 0.c. 54 GATG AUTD RH Cffp CPEV ORYWFlL CH/U Eb NTA."B' M - 74/ T. c . 54 cHEu<. Rev. FLo w -

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l I I f

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FEBRUARY 1979 a.vc : osITIe:: / p' s yj/g g- lcoNTnItmenT h' sfh j h h! ~/

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L/1 s7p no B f a SE2 NOTE 28 4 3j5h or - -

t/2 ,sTD. no 8 i u SEE AICTE 25 _

y HUT -

~

3/4 STD. No 8 l 4 SEE //CTE .2 2 tur 5 -

no a i Y ser vere e s 07 45IS 8, L, M r Z. 3 57o. 20 6 i Y su vore es 5'a Hui AS IS -

2N -

No B l Y 3H01 ASIS -

'2 l2 -

No 6 / Y set hut - -

1 -

90 8 i Y SET 9 fod PS/G poM L8 ser Hur - -

2 -

No 6 1 'f ser & Soo m>c pere IR l

Roi - - 3 -

Uo 8 L Y SET 4 . coo Ps/G NtB as u HVT -

l #l2 -

Mo 8 i Y SET @ 220 P616 $$to H it T l -

~

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No e i Y s e T9 Seo P3/ C c$e 18 Hur AS /S

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Afo E 1 Y GE79 75rsta sEs-207E 18 UUT

~ ~

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No 8 1 Y SVT @ tw esis , ces pere fB HvT as IS B> L 8 870 20 B J Y "8 ofed wysy "4" spor 54 Hur 6 -

no 6 i Y "B ~opgv wys v ",9 *syur Hur asis 6, L 9 S TO. Do B 1 Y B' cPex? whew "A "suor 5L 90T as is

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4 TABLE 6.2-8 (

cJ g s 4, N

.s A .

ACT L idi d;

[

k %T S

. C;.; y r* s e

Ll. ISOLATED v -

J -

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<* F f* = *% ^

f (?c. =

ORYWBL CHILJFD W72. % M-71 0& 5? G4re Avro KM SHUT c//ur 92YWELL CH/Us'D WTR. "A" M-77 /. C . 54 check. xEV. FLCW ~

SHDT CHOT THEdddd DZYWBEL F&oeR M-78 - - - - - - -

THlodGH peYWELL FL ooR H-79 - - - - - - -

THEDUGH DRYWEZL Flo0R M-80 - - - - - - -

TH200G H LtaYWELL FlD0R H-8[ - - - - - - -

THROUGH DRYWGLG Floor M-82 - - - - - - -

TH2006& DEYWELL Floor ' H-83 - - - - - - -

I THRovGN CRYWELL ' F600/2 l H-84/ - - - - -

l - -

l Tx20ma ozYwrit ricon M-es - - - - - - -

7HRDuGH DRYWELL floor M-84 - - - - - - -

THE0adH PRY WELL FLcoR. H-8 7 - - - - - - -

TH2cuqH PRYWELL Flocit H-88 - - - - - - -

THMaDI DKYWELL N00R M-89 - - - - - - -

TunwGH DRYWEZL Flook H-90 - - - - - - -

7H200GH MYWELL FLC0% M-91 - - - - - - -

THEDaGH DEYWFLL R002 I H-91 l - - - - - - -

1 I

9 I

nt'd) ZPS-1 REVISION 54 ;

FEBRJARY 1979 VALVI: i)S I T IO"

[ s/ g4 ,q e4 s,

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. x CONTAINMENT p\ [ gT

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SIGNAL

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shur Sh Na G Y "A *ctY J weral A* SNor" Gilvi -

i

_ _ _ m _

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_ _ _ _ _ . _ o 38 6.2-90

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TABLE 6.2-8 (

i

g. .,

y [ iiT L' AT I R. [

C' q-08 W.S T N, ^,

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Y Qk4 p., jT Q gg S 5'j c

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m

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H- 95 oc. 57 Glo BG RM MAN. oPFN OPEN sq4eg g Sg, - - - - - -

RHR RELIEF VENTS H-47 d.C. SC ReUG7- CVEAP2ess SMUT SHUT KHz RCLIEF VEN T5 M-97 0.c. SC CEuGF cv5R. Pff5S -

SMUT Shur RHC REUEF Vex / Ts M- 97 o c. SC RELIEP CJeX PR(sS

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I l Run Tng unE us ~ lM-9V o.c. sc aLose suro an I.seo7 seuT

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DRYidElb ft/242 GtHA0sr M-LOf 0-c . SC GLcBE RM MhN. SMoT SHOT P2YWEu. POPM BtHAvsT M-tOf 0 c- SC GLOBE Rth M h t). SHUT s#UT I

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f.

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CONTAINMENT h k

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l - - - - - - -

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2 6TD. 90 8 1 Y 3EE NeTE li 6.2-91

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s9 3 s .

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SotP. cM4MBER R1246 cxWAvs7 N-103 0 c. SC BUTTER fly AUTO EM SMUT OPEA) 4)PP c@HAR2 RJP17 ' E2NAUGT H -103 0.c- SC BUT7EeFLY AUTO RH 8H07 OPrv CMfBuSTIGtE 4A9 Ch0720L M-103 0 C. Sir GLOB E KM HAN. SNGT SMU7 _

(bNBV.srtBin Q46 con.7720L H-/03 0. C . 6h GLC6G RJf MAD. SHOT SHOT 3dPP. C/MMGUR h/R46 IULET N-idd p.c- SC BUTTER FLY AUTC RH SMUT OPEAI SMPP CwH952 hiedt IntET M-104 0.c. 54 bes77bRfl.Y AU TO RH SHOT OF1?N su PP CH4MM72 POSGC IDLET N-104 0. c . 5C GLOB E RM CW N* aMul snot SAPP CHAMBER PVR4E WLET H-$0V 0.c. SC 460BG RM_ M htl* det/T SHUT Ret e $7 TAM VAcupa exg. M-iO4 0.c. SC GLOBE AUTO RM opgp opgp KJfR REUO" vat.ves Dis. M-105 0.c. 5F REUEF DVER PCEss -

SHUT SHUT _

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SHUT 3 HOT l

VAcuun BREAKEPs ciDfx M.iD7 -

- ~ ~ - - -

VAcoVM BEG 4KEPA LIUST H-109 - - - - - - -

VA c00M 82EALE2S LIAJET H-fo9 ~

~

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,l

nt'd) ZPS-1 REVISION 54 FEBRUARY 177E VAINI: I'OS I T ION [ [ .q g ,

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g-gM CONTAINMENT f th h 'y f o o ISOLATION [ O ,0 REMARKS h q0G SIGNAL

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GHOT SHUT Bo l Mr Z.

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2 STD. YS B 1 Y t M4LV 6 IM P494L M't.

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8 -

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Mo 8 i 't &c7 e 42o Ps/G l7Ygg CHOT SHUT - 0 -

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~

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l - - - - -

rHeousa sevtam fuee

~ - - - - -

~ ~ -

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- - ~ ~ ~ ' - ~

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T4P4 UGH ORYk)EZL PL.002 6.2-92

1

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.T-l/104 ins TRuHent unes - - - - - ~

cM Ecc. $MVT REC /Rd. It!HP seat R!e4E I-so l.C/oc rs acoge Mast -

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REcJRC. R/MP$24L PURGC I- 21 C 1.C/.o.c. 55 co ces y AN FLCW ~

0%U GPE SUPP CMHBER AIR 3 AMPLE ! T-7,7A l0C. 3G GLD86 ACTO RH SHUT 6 HUT surf.cHAMBEtt niz 54HrLE l1-29A, o */o.c. SC stoAG A vro RM SHu7 Sito Are GIMPLU-REACTOR HEAO lE-SDA,6 #lo.c. SG Giose HAN -

l SHUT SMUT Dw. Arnos. 34MPLE lI-G SA #l04. SG GLOB 6 AU Tb KM I OYUW8 PEU-s ut.u sAmrY/2ELicF VALVES Cr O* E *l0-C- 54 GLD6E

hay -

l5 HUT S HV1 AIK $4M PL 6 N.S. l Z'-6 & A I.l0.c. $4 GLOB G MAN -

l Wl? SH LTV AIR SAHrL G EECJEC. PUMP IB, e,05 */o.c. SC GLeR>6 man -

! WJ' S bel 412 CAMPLE REclec. PunP lr-674 2lo. c. 54 GcoBE MAN '

l 95? bH.V ^

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1-104 - -

l I

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LE 6. 2-8 (Cont'd ) ZPS-1 REVISIO!I 54 FEBRUARY 1979 ;

VAINI; l'USITIO :

/ /- p ,q e &

y CONTAINMENT ci /0 f.gTM c-f,6s 0 Dpp [6

?'

O' ,P /f 8 e o ISOLATION

2) .G 4' 0 o~ 4_

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<o 4' G

4 45.5 :3 q Q' G O M a u pores 21,z2,21(2 V l

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B 1 Wo excerr Fea uces s,sreo seww l 45 43 c$ ~

3V4 No 8 1 165 SEE NDIE 17 I 45 i enw-wor suoT B. L, M , Z. s/q Sro Me 8 i Yes ses pores U,it h r em>-3Ho) Shur 6, L, M, Z % STD NO B i Ye5 $EB" M TE5 lir$$

3 H Li 1~ L/1 l 45 Ho B SCE NOTf5 fir !9

- - ~

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\ a p r G et E L P w v n u ne u D c e r r A i E n r cueM n r n. M ve n a T n n As M A n u se e.e er A. s Ma nu s s r . s x R e eu c c a O e e e o e 1 e zu sr ur en tL -w /tw e se en er S n e u s n & e s I s . u e t E N r sr s E e a s s v e aes I L u r a w P 4 .m Mr.+ o r e A 4 o n M r un^ p - e . cm on u a M" A n e x n e r r ws scs r e a s A uuu nn r .*l r c n 5 w t a cu wt Awo m x e r x a e i e n tr s o A r a aw M l r e mA i A s e i / - r% ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-8 (Cont'd)

8. a. Containment spray valves are interlocked to prevent both from being open at the same time unless the isolation signals shown are present. This allows containment spray for high drywell pressure conditions. When the automatic signals are not present, these valves may be opened for test or operating convenience.

54

b. Suppression cooling valves have interlocks to allow them to be opened after automatic closure. This allows for suppression pool cooling. When the automatic signals are not present these valves may be opened for test or operating convenience.

9. Criterion 55 concerns those lines of the reactor coolant pres-sure boundary penetrating the primary reactor containment. The control rod drive (CRD) insert and withdraw lines are not part of the reactor coolant pressure boundary. The basis to which the CRD lines are designed is commensurate with the safety importance of isolating these lines. Since these lines are vital to the scram function, their operability is of utmost concern.

In the design of this system, it has been accepted practice to omit automatic valves for isolation purposes, as this intro-duces a possible failure mechanism. As a means of providing positive actuation, manual shutof f valves (IC11D001-101 and -102) are used. The charging water, drive water and cooling water headers are provided with a check valve (ICllD001-115, -138 and -137) within the hydraulic control unit (HCU), a Seismic Category I 44 module, and the normally closed solenoid valves (IC11D001-120, -121, -122 and -123). These valves will prevent any direct flow away from containment. These valves are shown in Figure 4.2-19 (Sheet 2). If an insert line fails, a ball check valve provided in each 43 drive is designed to seal off the broken line by using reactor pressure to shift the ball check valve to the upper seat. This feature also prevents any direct flow away from the primary containment. A piping integrity test is accomplished for leaks of the HCU's during daily inspection (HCU operating pressure above 1000 psi). In addition, several indicators in the control room, such as temperature and pressure of CRD cooling water or drywell sump pump operation, would indicate if leakage is excessive. The maxi-cum leakage expected at this penetration is 3 gpm when the RPV is still pressurized (about 1000 psi). This leakage also assumes a single active failure of a check valve inside the HCU. After the reactor vessel is depressurized, the CRD leakage will de-crease to about 0.5 gom. It may also be said that leakage moni-toring of the CRD ins.ct and withdraw lines is provided by the overall type A leakage rate test. Since the RPV and non- 44 seismic portions of the CRD system are vented during the per-formance of the type A test, any leakage from these lines would be included in the total type A test leakage. 6.2-95 ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-8 (Cont'd) The flowout of the CRD is restricted through the HCU by perfor-mance test requirements to ensure that HCU leakage does not exceed 0.2 gpm. The maximum leakage expected for these pene-trations is 0.2 gpm per HCU. If a single failure is assumed, the maximum leakage would be 3 gpm. Seismic tests have demon-strated the seal integrity of the CRD system. Maximum leakage following these tests did not exceed 3 gpm. The system design criteria are as follows: Quality Seismic Quality Group Assurance Component Category Classification Classification Valves; return line within containment boundary 1 A I ,. 43 Valves; insert and withdraw I B I Return line piping within isolation valves I A I Insert and withdraw line piping I B I The CRD insert and withdraw lines are compatible with the criteria intended by 10 CFR 50, Apper. dix J, for Type C testing, since the accept-ance criterion for Type C testing allows demonstration of fluid leakage rates by associated bases. The maximum leakage m:pected has been factored in with the total allowable containment )enetration leakage and determined to be acceptable.

10. Rain steamline isolation valves to be type "C" tested in accordance with Subsection 5.5.4. Leakage is exempt from Appendix J total 31 measured leakage criteria.

11. Test pressure will be applied between the valves. The total leakage recorded will be assigned to each penetration.

12. Penetration paths for M-18 and M-24 will be tested simultaneously. 14 The total leakage recorded will be assigned to each penetration.

13. Deleted 43

14. Deleted.

38

15. Deleted.

6.2-95a ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-8 (Cont'd)

16. The Zimmer 1 TIP system design specifications require that the maxi-mum leakage rate of the ball and shear valves shall be in accordance 26 with the Manufactureres Standardization Society (Hyorostatic Testing of Valves). The ball valves are 100% leak tested to the following criteria by the manufacturer:

Pressure 0 - 62 psig Temperature 340 F Leak Rate 3 3 10 cm /s 17 A statistically chosen sample of the shear valves is tested by the manufacturer to the following criteria: Pressure 0 - 125 psig Temperature 340* F 3 Leak Rate 10 cm /see STP The shear valves have explosive squibs and require testing to destruc-tion. They cannot therefore be 100% tested.

17. Deleted.

l37 18. Test pressure is not in tue same direction as the pressure existing when the valve is required to perform the safety function as required 16 by Appendix "J" to 10 CFR 50.

19. Since the traversing incore probe (TIP) system lines do not com-municate freely with the containment atmosphere or the reactor coolant General Design Criteria 55 and 56 are not directly applicable to this specific class of lines.

The basis to which these lines are designed is more closely described by General Design Criterion 54, which states in effect that isolation capability of a system should be commensurate with the safety importance of that isolation. Further-more, even tho.agh the failure of the TIP system lines presents no safety consideration, the TIP system has redundant isolation capa-bilities. The safety features have been reviewed by the NRC for BWR/4 (Duane Arnold), BWR/5 (Nine Mile Point) and BWR/6 (CESSAR), and it was concluded that the design of the containment isolation system meets the objectives and intent of the General Design Crtieria. 43 Isolation is accomplished by a seismically qualified solenoid-operated ball valve, which is normally closed. To ensure isolation capability, an explosive shear valve is installed in each line. Upon receipt of a signal (manually initiated by the operator), this explosive valve will shear the TIP cable and seal the guide tube. When the TIP system cable is inserted, the ball valve of the selected tube opens automatically so that the probe and cable may advance. l A maximum of four valves may be opened at any one time to conduct calibration, and any one guide tube is used, at most, a few hours per year. 6.2-95b ZPS-1 REVISION 54 FEBRUARY 1979 TABLE 6.2-8 (Cont'd) If closure of the line is required during calibration, a signal l causes the cable to be retracted and the ball valve to close auto- I matica11y after completion of cable withdrawal. If a TIP cable fails to withdraw or a ball valve fails to close, the explosive shear valve is actuated. The ball valve position is indicated in the control room. As stated above, the penetration is normally closed (oggn ag average cm /sec. ~ of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> per month), and the design leak rate is 10 If a failure occurred, such as not being able to withdraw the TIP cable, netration, and the resultingtheshearvalvewouldisolatetgepg/sec maximum leakage would be 10_ cm . The shear valves are shop tested by statistical sampling methods to ensure that the -3 legkage limits conform to the design specification limits of 10 43 cm /sec. Testing of the ball valve is not recommended, since a very small amount of leakage is expected, and any testing would need to be performed from inside the drywell, exposing the operator to radiation dose estimated to be about 50 mR. These lines should therefore be exempted from the 10 CFR 50 Appendix J Type C tests.

20. Closed system outside the containment. The inlet isolation valves l38 will always be pressurized to a higher pressure than the containment pressure. The system is seismic Category I and single-failure-proof. 31 A Seismic Category I water supply for makeup is available for 30 days. 54 The makeup rate into the RBCCW surge tank is established at 300 gpm and therefore provides sufficient fluid inventory to assure the sealing function for at least 30 days at a pressure greater 38 than 1.10 P .

a The RBCCW Class C piping will be subject to the ASME Section XI, 45 Inservice Inspection Program.

21. These lines satisfy the requireuents of General Design Criterion

54. They are Seismic Category 1 and terminate in instruments that are Seismic Category 1. They are provided with manual isolation valves.

38 These lines are connected to the essential ADS accumulators. On loss of the drywell pneumatic system, they are pressurized by the ni-trogen subsystem. These lines will always be pressurized to 165 psig. They terminate in a pressure switch that alarms at 145 psig. 6.2-95c ZPS-1 REVISION 54 FEBRUARY 1979 is sized to filter radioactive particulates and iodine for at least 30 days' operation after the accident, based on inlet concentrations de-scribed in the previous paragraph. The temperature and pressure inside the control room are ensured at 73*F + 1*F temperature and 0.125 inch H2O positive pressure (Note: The control room is maintained at a positive pressure because the carbine building ventilation system maintains areas adjacent to the control room at -0.125 to -0.25 in, water gauge. Even if control room air intakes are isolated, the control room pressure will gradually drop to a level slightly above the turbine building pressure. This is accept-able to Regulatory Guides 1.95 and 1.78 since pressurizing air would contain ammonia or chlorine which would produce higher room concentra-tions than if only infiltration was the transport mechanism.) with respect to surroundings during and after all the postulated conditions, as discussed below,

a. The control room and other areas served by the control room HVAC system are completely isolated from the high-energy pipelines to preclude any effect of steam pipe ruptare of the control room temperature and pressure,

b. To further ensure that the control room atmosphere is not affected by the surrounding conditions, the control room is isolated on annunciation of any abnormal station operating condition, on the main control board. Strict administrative procedures are laid out for ingress and egress to the control room following isolation.

c. The control room temperature and pressure cannot rise due to loss of control room HVAC system component failure, because two, 100%-capacity, redundant HVAC systems are available for the control room, as discussed in Subsections 3.11.4 and 9.4.1.

d. The control room operator doses for LOCA, assuming 99%

iodine removal efficiency and 10 ft 3/ min unfiltered infil-tration rate are tabled below. Dose (rem) Using Dose (rem) Using Conservative Assumptions Realistic Assumptions -4 Skin (Beta) 11.2 1.3 x 10 Whole Body 2.08 3.0 x 10~ (Gamma) Thyroid 22.7 2.7 x 10~ The ionization detection subsystem is used to provide early warning of the presence of combustion products in the control room, auxiliary electric equipment r oo.a . computer room, or cable spreading room. On annunciation of any ionization products inside the control room, the mixture of outside air and recirculated air for the control room HVAC 6.4-2 ZPS-1 REVISION 54 FEBRUARY 1979 system can be routed through normally bypassed, absorber filters for odor and smoke removal. A capability to purge control room air by 100% outside air is provided. The cables, instruments, and equipment used in the control room are made of flame-retardant material for the preven-tion of fire. Fire fighting apparatus is available inside the control room. Chlorine is detected in the two outside air intakes by four detectors, two located in each outside air intake. The power supplies for the detectors are divisionally separated such that primary intake detectors are powered from Division 1 and alternate intake detectors are powered 28 33 from Division 2. This design satisfies the redundancy requirements of Regulatory Guide 1.95. On detection of chlorine gas (at approximately 1 ppm) in an outside air intake, the affected intake mode is isolated l1 and the system placed in recirculation mode. 12 Ammonia is detected in the two minimum outside air intakes by four de-tectors, two located in each intake. The power supplies for the detec-tors are divisionally separated such that primary intake detectors are powered from Division 1 and alternate intake detectors are powered from Division 2. This design satisfies the redundancy requirements of Regu-latory Guide 1.95. 33 The ducts connected to the primary and alternate outside air intakes are sized to provide a delay time which exceeds the response time of the detectors plus the closure time of the isolation dampers. Thus upon detection of ammonia gas (>25 ppm) in an intake, the outside in-take is isolated and system placed in recirculation mede before tha ammonia reaches the isolation dampers. In addition, breathing apparotus 12 and bottled air supply is provided near the operators. 51 6.4-2 a ZPS-1 REVISION 54 FEBRUARY 1979 in the reactor coolant pressure boundary and that the core is in danger of becoming overheated as the reactor coolant inventory diminishes. Reactor vessel low water level initiates closure of various valves. The closure of these valves is intended to isolate a breach in any of the pipelines in which the valves are contained, conserve reactor coolant by closing off process lines, or prevcat the escape of radioactive materials from the primary containment through process lines that communi- 2 cate with the primary containment interior. Two reactor vessel low water level isolation trip settings are used to complete the isolation of the primary containment l2 and the reactor vessel. The first (and higher) reactor vessel low water level isolation trip setting initiates closure of all valves in major process pipelines except the main steam-lines. The main steamlines are left open to allow the reuoval of heat from the reactor core. The second (and lower) reactor vessel low water level isolation trip setting com-pletes the isolation of the primary containment and reactor 2 vessel by initiating closure of the main steam isolation valves and any other valves that must be closed to isolate minor process lines. The first low water level setting (which is the RPS low water level scram setting) was selected to initiate isola-tion at the earliest indication of a possible breach in the reactor coolant pressure boundary, yet far enough below normal operational levels to avoid spurious isolation. Iso-lation of the following pipelines is initiated when reactor vessel low water level falls to this first setting:

1. RHR reactor shutdown cooling supply,

2. RHR reactor head spray,

3. RHR shutdown cooling discharge to radwaste, and 54

4. RER process sampling.

The second (and lower) of the reactor vessel low water level isolation settings (the same water level setting at which the RCIC system is placed in operation) was selected low enough to allow the removal of heat from the reactor for a 7.3-22 ZPS-1 REVISION 54 FEBRUARY 1979 predetermined time following the scram and high enough to complete isolation in time for the operation of emergency core cooling systems in the event of a large break in the reactor coolant pressure boundary. Isolation of the follow-Ing pipelines is initiated when the reactor vessel water level falls to this second setting:

1. all four main steamlines,

2. main steamline drain,

3. reactor water sample line,

4. reactor water cleanup,

5. drywell drain discharge to radwaste, 54

6. primary containment low purge exhaust, and

7. primary containment high purge exhaust.

b. Main Steamline High Radiation High radiation in the vicinity of the main steamlines could indicate a gross release of fission products from the fuel.

High radiation near the main steamlines initiates isolation of the following pipelines:

1. all main steam 11nes,

2. main steamline drain, and

3. reactor water sample line.

The high radiation trip setting is selected high enough above background radiation levels to avoid spurious isolation, yet low enough to promptly detect a gross release of fission products from t.2 fuel. (For more information on the high radiation setpoint, see Subsection 7.6.1.3).

c. Main Steamline Space High Temperature and Differential Temperature High temperature in the space in which the main steamlines are located outside of the primary containment could indicate 2 a breach in a main steamline. Also, such a breach may be in-dicated by high differential temperature between the outlet and inlet ventilation air for this steamline space. The automatic closure of various valves prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive material from the reactor coolant pressure boundary. When high temperatures occur in the main steam-line space, the following pipelines are isolated:

7.3-23 ZPS-1 REVISION 54 FEBRUARY 1979

1. all four main steamlines, and

2. main steamlina drain.

The main steamline space high temperature trip is set for enough above the temperawre expected during operations at 7.3-23a ZPS-1 REVISION 54 FEBRUARY 1979 rated power to avoid spurious isolation, yet low enough to provide early indication of a steamline break.

d. Main Steamline High Flow Main steamline high flow could indicate a break in a main steamline. Automatic closure of various valves prevents excessive loss of reactor coolant and release of signifi-cant amounts of radioactive material from the reactor cool-ant pressure boundary. On detection of main steamline high flow, the following pipelines are isolated:

1. all four main steamlines, and

2. main steamline drain.

The main steamline high flow trip setting was selected high enough to permit isolation of one main steamline for test at rated power without causing an automatic isolation of the other steamlines, yet low enough to permit early detection of a steamline break. '54 7.3-24 ZPS-1 REVISION 34 FEBRUARY 1979

e. Drywell High Pressure l54 High pressure in the drywell could indicate a breach of the reactor coolant pressure boundary inside the drywell. The automatic closure of various valves prevents the release of significant amounts of radioactive material from the contain-ment. On detection of high drywell pressure, the following pipelines are isolated:

1. drywell drains discharge to radwaste,

2. primary containment low purge exhaust,

3. primary containment high purge exhaust, and 54

4. RHR shutdown cooling discharge to radwaste and RHR pro-cess sampling.

The drywell high pressure isolation setting was selected to be as low as possible without inducing spurious isolation trips.

f. Reactor Water Cleanup System High Differential Flow 54 High differential flow in the reactor water cleanup system could indicate a breach of the nuclear system process barrier in the cleanup system. The cleanup system flow at the in-let to the heat exchanger is compared with the flow at the outlet of the filter /demineralizer. Higher flow from the vessel initiates isolation of the cleanup system.

g. Reactor Water Cleanup System Area High Temperature and 2 54 Differential Temperature High temperature in the area of the reactor water cleanup system could indicate a breach in the reactor coolant pres-sure boundary in the cleanup system. High area temperature and high differential temperature in the area ventilation system initiates isolation of the reactor water cleanup system.

7.3-25 ZPS-1 REVISION 54 FEBRUARY 1979

h. RHR System Area High Temperature and Differential Temperature l54 High temperature in the area of the RHR system pumps could indicate a breach in the nuclear process barrier in the RHR shutdown cooling system. High area temperature and high differential temperature in the area ventilation system initiates isolation of the RHR shutdown cooling system and steam supply to the RCIC turbines.

54

1. Turbine Condenser Low Vacuum In addition to the present turbine stop valve trip on low condenser vacuum instrumentation, which is a standard com-ponent of the turbine system, a main steamline isolation valve trip in the low condenser vacuum instrumentation system is provided and meets the safety design basis of the l2 nuclear steam supply shutoff and primary containment isola-tion systems.

The main turbine condenser low vacuum would indicate a leak in the condenser. Initiation of the automatic closure of various Class A valves will prevent excessive loss of reactor coolant and the release of significant amounts of radio-active material from the nuclear system process barrier. Upon detection of turbine condenser low vacuum the following lines will be isolated:

1. all four main steamlines, and 54

2. main steamline drain.

The turbine condenser low vacuum trip setting was selected far enough above the normal operating vacuum to avoid spurious isolation, yet low enough to provide an isolation signal prior to the rupture of the condenser and subsequent less of reactor coolant and release <f radioactive material. Instrumentation Sensors providing inputs to the primary containment and reactor vessel l2 1 solation control system are not used for the automatic control of the process system, thereby achieving separation of the protection and process systems. Channels are physically and electrically separated 7.3-26 ZPS-1 REVISION 54 FEBRUARY 1979

f. mode switch in STARTUP mode, and l 54

g. main condenser low vacuum.

The logic actuator outputs used to control the main steamline drain valves and reactor water sample valves could be termed two-out-of-two, applied to each valve. The logic strings for this control are shown in Figure 7.3-14. Other isolation valves are controlled by drywell high pressure and re-actor low water level signals. In this arrangement, two drywell pressere sensors are combined with two water level sensors to form a " hybrid" one-out-of-two twice network. This logic is shown in Figure 7.3-12. These same drywell pressure and water level logics are used with process radia-tion monitor upscale and inoperative signals to produce other isolation actions, including initiation of the standby gas treatment system. The reactor water cleanup isolation valves are controlled by two logics, using high flow, high area temperature, high area differential tempera-ture, and low water level signals. Bypasses and Interlocks An automatic bypass of the main steamline low-pressure signal is effected in the startup mode of operation (see isolation functions and settings). Interlocks are provided frou position switches on the drywell drain sumps to the radwaste system to turn of f the drywell drain sump pumps if the isolation valves close. Redundancv/ Diversity The variables which initiate isolation are listed in the circuit descrip-tion. Also listed there are the number of initiating sensors and chan-nels for the isolation valves. Actuated Devices Table 6.2-8 itemizes the type of closing device provided for each isola-tion valve. To prevent the reactor vessel water level from falling below the top of the active fuel as a result of a pipeline break, the valve closing mechanisms are designed to meet the minimum closing rates specified in Table 6.2-8. The main steamline isolation valves are spring-closing, pneumatic, piston-operated valves. They close on loss of pneumatic pressure to the valve operator. The control arrangement is shown in Figure 7.3-15. Closure time for the valves is adjustable between 3 and 10 seconds. Each valve is piloted by two three-way, packless, direct-acting, 7.3-29 ZPS-1 REVISION 54 FEBRUARY 1979 solenoid operated pilot valves both powered by ac. An accumulator lo-cated close to each isolation valve provides pneumatic pressure for valve closing in the event of failure of the normal air supply system. The sensor trip channel and trip logic relays for the instrumentation used in the systems described are high reliability relays. The relays are selected so that the continuous load will not exceed 50% of the con-tinuous duty rating. Table 7.3-6 lists the minimum numbers of trip channels needed to ensure that the isolation control system retains its functional capabilities. Separation Sensor devices are separated physically such that no single failure (open, closure, or short) can prevent the safety action. By the use of conduit and separated cable trays the same criterion is met from the sensors to the logic cabinets in the control room. The logic cabinets are so arranged that redundant equipment and wiring are not present in the same bay of a cabinet. Redundant equipment and wiring may be present in con-trol room bench boards, for separation is achieved by surrounding re-dundant wire and equipment in metal encasements. (A bay is defined by adequate fire barriers.) From the logic cabinets to the isolation valves separated cable trays or conduit are employed to complete adherence to the single failure criterion. Testability The main steamline isolation valve instrumentation is capable of complete testing during power operation. The isolation signals include low re-actor water level, high steamline radiation, high main steamline flow, high main steamline tunnel temperature, and low condenser vacuum. The water level and steamline flow sensors are pressure or differential 54 pressure type sensors which may be valved out of service one at a time and functionally tested using a test pressure source. The radiation measuring amplifier is provided with a test switch and internal test source by which trip availability may be verified. Functional operability of the temperature switches may be verified by applying a heat source to the locally mounted temperature sensing ele-ments. Control room indications include annunciation, panel lights and computer printout. The condition of each sensor is indicated by at least one of tr.cse methods in addition to annunciators common to sensors of one variable. In addition, the functional availability of each isolation valve may be confirmed by completely or partially closing each valve ind-ividually at reduced power using test switches located in the control room. The cleanup system isolation signals include low reactor water level, high equipment area ambient temperature and differential temperature, high differential flow, high temperature downstream of the nonregenera-tive heat exchanger, and standby liquid control system actuation. The water level sensor is of the differential pressure type and can be periodically tested by valving each sensor out of service and applying 7.3-30

ML19308A276

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