ML18037A210

Forwards Info Re Containment Isolation Barriers in Response to NRC .Fourteen Oversize Drawings,Available in Central Files Only

ML18037A210
Person / Time
Site:	Nine Mile Point
Issue date:	11/28/1979
From:	Dise D NIAGARA MOHAWK POWER CORP.
To:	Ippolito T Office of Nuclear Reactor Regulation
References
NUDOCS 7912040469
Download: ML18037A210 (58)

Text

REGULATORY INNATION DISTRIBUTION SYSTE(RIBS)

ACCESSION NBR g 7912040469 DOC ~ DATE ~ 79/11/26 NOTARIZED!

NO DOCKET F'ACID,$ 50~220 Nine Aile Point Nucteai Stationi Unit 1g Niagara Powe 0&H)M AOTH.NAME AUTHOR AFFILIATION gg-a~a DISRiDBP ~

Nfager a Mohawk Power Corp, REC IP, NAME RECIPIENT AFF ILIATIOIIl IPf'QL'ITOiT,A.

Operating Reactor's'"ranch 3

SUBJECT:

Forwards info re containment isolat)on barriers in response to NRC 790713 ltr,Four'teen oversize drawfn 8Eavailable in Centi'il P lien en I yiene 1, DISTRIBUTION CODE:

A001S COPIES RECEIVEDYI..TR ENCL' SIEE:2=

TITLE! General Df'stribution for after Issuance of Operating Ci NOTES:~<AYIACe~FLL~ MLkt$LLS~ECLQE LTL+

JAhg RECIPIENT COPIES RECIPIKNT COPIES ID-CODE/NAME CTTR"ENCL ID CODE/NAME LTTA"PCL.

ACTIONs 05 BC gQQ "7

'7" INTKRNALe 12 ILE-i5 CORE PERF BR=-

iS REAC 8FT7 SA 20 EEB 22 SRINKMAN OELD EXTERNALS 03 LPDR 23 ACRS 1

1 2

2 1

i 1

i i

1 0

1 1

16 16 02 NRC PDR 14 TA/EDO i'/ ENGR BR i9 PLANT SYS BR 21 EFI.T TAT SYS EPB" DOR 04 NSIC

@pa

~ Ja.um, Q~~~~ ~,

Ir et~~

1!cuuuana (PRV65 KAlax>~Q)0 6 )9~9 6 >spe TOTAL NUMBER OF COPIES REQUIRED:

LTTR 39 ENCL 38

~

g 4

p iEPt

@85

'~7 MIIASAIRA, 0 MQHAWK Donald P. Disc NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Vice President Engineering November 28, 1979 Director of Reactor Regulation.

Attn:

Mr. Thomas Ippolito, Chief Operating Reactors Branch iD U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Ippolito:

Re:

Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Your letter dated July 13, 1979 requested information regarding the containment isolation barriers.

The attached responds to your request.

Very truly yours, PEF: jk NIAGARA MOHAWK POWER CORPORATION

'g~P~

Donald P. Disc Vice President Engineering

, k

~

~

'1

~

'I I

V

PLANT Nine Nile Point Unit 1

BYPASS CAPACITY Plant Steam Bypass Capacity 40K rated steam flow

4. ~

(

l1 II r $,

Cj f4 v tf

PLANT Nine hKle Point Unit 1

SYSTEMS AND COMPONENTS SHARED BETWEEN UNITS Single-unit plant check here ~~

and do not complete S stem or Com onent Shared Between Units Numbers N/A N/A

PLANT Nine Nile Point Unit 1

PLANT-SPECIFIC SYSTEM INFORMATION

~Sstem Emergency Condenser General Mater Sources Safety Related I

Safety Related Safety Seismic Safety Seismic Classification Ca~e<aCor Classification

~Cate or Safety Rel.

I Once each operating cycle Instrumentation and Control.

Frequency of Safety Seismic System and Classif.

~Cateoor Co.".,oonant Tes-s High Pressure Coolant Injection Safety Related Safety Related Safety Rel.

I Pump operability is, demonstrated once per quarter.

Auto-matic startup of system is demon-strated once per operating cycle

- Low Pressure Core Spray Auto Depressurization System Safety Related Safety Related Safety Related N/A N/A Safety Rel.

I Safety Rel.

I Pumps and power op-erated valves are checked once per quarter.

Automati startup of one set of pumps is demon-strated once each operating cycle Automatic initiation is demo strated once per operating cycle Pressure Relief Valves Safety RElated N/A N/A N/A N/A Automatic initiatio is demonstrated once per operating cycle.

4

PLANT Nine Nile Point Unit 1

PLANT-SPECIFIC SYSTEf<

INFORi<ATIOiN

~Ss tern Safety Valves.

General Safety Related N/A N/A N/A N/A Eight of the 16 safety valves are

removed, tested for setpoint and partial 3ift once per operating cycle Mater Sources Instrumentation and Control Frequency o

Safety Seismic Safety Seismic Safety Sei smic Syste.": and C'lassification

~Cate or C'lassification

~Cate or Classif.

~Cateoor Cor:,oorert e.sts Shutdown Cooling System Safety Related Safety Related L

Safety Rel.

I Pump operability is checked

'once per quarter

.Containment Spray and Suppression Pool Cooling System Safety Related Safety Related-I Safety Rel.

I Pump operability is checked once per quarter.

Automatic startul of containment spray pumps is demonstrated onc per operating cycle Emergency Service Mater Safety Related Safety Related T..

Safety Rel.

T.

Pumps operability is checked once per quarter.

PL+')T Nine Mile Point Unit 1

PLMT-SPECIF IC SYSTEM INFORllATIOil

~Sstem General Water Sources Ins trumen tat i on and Control Frequency of.

Safety Seismic Safety Seismic Safety Seismic System ard C'lassification

~Cate or Classification

~Cateoor Classif.

~Cateoor Coroonent Tests reactor Building Closed Loop Cooling Mater System Control Rod Drive Safety Related I

Safety Related I

Safety Related Safety Related Safety Rel.

I Safety Rel.

I Normally in service Automatic startup of each pump is demon-strated once per operating cycle Condensate Storage Tank Hain Feedwater (pressure boundary)

Cooling Mater to Recirculation Pump/Hotor Safety Related Safety Related Safety Related I

Safety Related I

Non Safety Related I

Safety Related Non Non Safety Non Seismic Related Seismic Non Safety Non Related Seismic N/A Normally in service Safety Rel.

I Normally in.service

PLANT Nine e Point Unit 1

PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 1 of 17..

Iso'l ation Valves Or S

S

~ ~

QJ CJ D C

CJ Q

CJN I

C/)

CJr Ar VJ C C/I CJ O O'0 D Sa U

S QJ QJD r

lCJ) R O~ ~Cn eCJ C QJ O UZ)

CIJ r O Or CCJ O

SO CCJ O

I cC CJ 0

Srr CJ S-VJ O O QJ r

C/I a

CJ r P I

U. J CJO S-O C/l S-O O O

~r S-O 0 C I

I

'r C

CIJ O O r Q

Oo C/l QJ CIJ O O O O *cX:

Positions CJ S-S O CCJ OU Comments X-2A X-2 X-28

- X-28

-3A X-38 24 Main Steam 24 Hain Steam 24 Hain Steam 24 Hain Steam 10 Emer 10 Emer en Co d N

1 S

N 1

S

'N 1

S N

1 S

S 01-01 A

01-03 A

01-04 A

39=Q9.

GB A

NO A

AO A

AO A

MO A

RMC 10 RMC 10 RMC AC 0

A D

0 C

C AI C

C 0

AI X-38 10 18 Emer enc Condense 9.

Feedwater Y

1 S

1 W

39-08 8

31-04 C

GT GB MO A

NO RM RMC A 6 0

A 18 Feedwater ee water ee water N

1 W

N 1

W 31-02 N A 31-03 C

31-01 N/A 0

CK GB CK A

RF HO RMC N

RF NANA N A 60 NANA AC D

N A N A 0

N A NANA NANA 0

AI NANA X-5A X-5 10 10 Emer enc Condense Emer en'ondense Y

1 W

Y 1

W 0

39-06 39-04 N A I

DCV N/A A

A X-58 10 Emer enc Condense Y

1 JW X-58 X-7 X-7 X-8 X-8 10 14 14 14 Emer enc Condenser Y

Shutdown Cool. Rtnj Shutdown Cool.

Rtn Shutdown Cool.

Su Shutdown Cool.

Su React.Cleanu Su 1

1 W

1

-W 1

W 39-05 8

38-12 N A 38-01 0

38-02 0

33-03 R

L 40 AC.

D.

C.

.0 X-9 X-154 X-154 6

React.Cleanu Su l 6

React. Cl eanu Su 1

6 React.Cle~anu Su 1

N 1

W N

1 W

33-04 3 -0 33-03 NLA Q

GT NO A

NgA

4

PLANT Ni 1ile Point Unit 1

PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 2 of 17..

Isol a tion Va 1 ves

~ C0 O~

5-5

~ +J Ql CJ M C

QP ~ W M CL, M Ql I

CJ 5

Vl E Ql QP 5-4-P QJ Vl CP MI-VlC Cl 5

I 44 Ql 0 0 I-0 2 5-r CL U S-Ql Ql

)

I 0 K 0

I 4

~VP fXP XXP~

5: QJ O ~

Vl.r 0 0

I rd00 5-0 O

I Owe0 IX=

'I 0 Sar Ql 5-Vl0 O Ql I

Vl I

QJ rg og U. 5-eO 5-D0 V O

~r 5

C C0 0 C

~I I

'r 5

Vl 0 0 'r O

Positions QP0 4J r V) &

0 O Q

Cl S-5-W CPI 0 IXP CLU Commen'ts X-1 12 X-14 12 X-14 12 X-18 24 X-12B 8

X-13 12 X-13A 12 X-13 12.

0 Dr ell Co l r BCLC f ore Spra Inlet ore S ra Inlet ore S ra Inlet ore Spra Inlet ore S ra Inlet ore Syra~ Inlet r well Vent 5 Pur e

Y 1

Y 1

Y

=

1 Y

1 Y

1 N

2 W

W gg-(Q Manua'l 40-10 Manual W

40 11 anua W

40 12 Manual A

201-09 E

W 70-95 N A 70-94 Ma W

40-01 Manual W

40-09 Manual Gj:

GT M

GT MO A

RMC 90 OC 0

AC 0

C C

AC 0

C AC 0

C C

AI AI AI X-18 24 A'r N

2 A

201-10 E

B AO A

RMC 6

X-19 20 X-19 20 X-19 4

Dr ell N

V Fi1 Dr well N

.VentslFill Or el 1 N

Ventj Fill N

N 201-31 E

2 N

201.2-E 03 2QlZ-32 B

MO AO A

RMC 60 AC D

C 0

AI X-20:

X-25 X-25 4

Cont. Atmos. Oil

~

ample Ret.

Cont.

Atkins Oil Sam le Ret.

Dr~well Floor Or.

Sum Outlet Or el 1 Floor Or Sum Outl e t 2

N 1

N 1

A 201.7-E W

83.1-E W

83 1-E 12 DCV AO A

RMC 60 0

0 0

PLANT N ne e Point Unit 1

PRIMARY CONTAINNENT ISOLATION SYSTEN DATA PAGE 3 of 17.

Isolation Valves

~ 0 r

0 ~

A cg S

S

~ ~

CJ QJ J3 S-QJ a 0

QJ I Vl le o g QJ CJ I M QJ ch QJ VlK QJ 0 V'r 0 V I r Cl SJ CJ CJ

) ClE rIJ 0

~l~ ~ In CC cg~

rI CJ O OIQ tll r 0 0

'I lrt$V0 S-0 tg V

I V

Ci: QJ0 r 0 kr O M Ird V

S-0V C/)

CJ S

Vl V 0 QJ r

EA r

QJ g'r IJ-I-S-

CJ 0

O I~

~

V O

~r S

C Q 0 I=

r I

th Q 0'r 0

00 t/)

CJ0 r

Vl V 0 V O- ~

Positions CJ S-S-W P.r 0 lO O.U Comments X-26,3 Dr ell E ui

. Dr.

N Sum Outl e t X-26 3

Dr ell E ui

. Dr.

N Sump Outlet

-345 1

R acInst.

X-34 1

Reactor R cir S

s N

1 W

1 W

W 83.-

09

83. 1-E 10 0

DCV RM 60 AO A

RM 60 HF AC 0

C C

X-34 1

Inst.

Reactor Recir.

S s.

N Inst.

5 W

N A 0

X-34 1

Reactor Recir. 'S s.

N Inst.

~X-35 5J 1

Reactor Recir.

S s.

N Inst.

5 W

5 W

N A 0

FCV NA HFN X-35 Reactor Recir.

Sys.

N 5

W N A 0

/

HF Inst.

X-35 1

Reactor Recir.

S s

N nst.

X-35 1

Reactor Recir.

S s.

N nst.

X-36%'

React.Recir.S sInst N

N 5

W 5

W N A HF N

N/.

NJ N/A NjA

PLANT Nin 1e Point Uni PRIMARY CONTAINMENT ISOLATION SYSTEM OATA PAGE 4 of 17.

Iso1ation Valves

~ C0 r~ 'r e(S S-S

~ M CJ QJ JD r

S-CJ m

CI CI IV e(/)

CJ e

CJ (s

e(S S

Vl e(J o Q QJ CJ I

~ CJ VI CJ NrU VlC CJ '0 Q'r 0 D S

e Ci SJ dJ dJ e-e($0 c 0

ee et/ e(j~

(: QJ O <<JZ)

Vl.rO 0

e(S00 S-0 O

I O

C(: QJ E

S='rO Sr-

eO

I 0

0-0(J QJ'/l CJ S-Vl (3 0 CJ e

Vl eQJ r P (I I CJO S

0 dJ 0

(J 0

~r S-C (:0 0

e e

~r

(

Vl Q Q 'r 0

00 I-QJ 4J 'r VI 0 O 0 CL ed:

Positions Comments X-37(5:

1 X-37 1

X-37 1

X-43 1

X-43 1

X-43 X-2875 React.Recir.SysInst React. Recir. S s Inst React.Recir.S slnst React.Recir.S sInst React.Recir.S sInst React.Recir.SysInst React.R ir 5

W' W

5 W

W W

5 W

5 W

N/A N A N A N A 0

GT 0

FCV MF HF NAHF H-N 0

0 0

N A eact.Recur.SysInst 5

W N A 0

FCV N

N A NANA N A

-28 X-28

<-32 5

X-32 X-32 X-32 X-31 5

X-31 X-31 X-30 X-30 React.Recir.S slnst React. Recir.~Ss Inst React. Retires inst React. Recir. S s Inst React.Recir' I st React. Recir.S s Inst React.Recir.S sInst.

React.Recir S

I s React.Recir.S sInst React.Recur.S sInst React.Rec>r.

yslnst N

5.

W 5

W 5

W 5

W 5

5 W

N A N A N/A 0

GT 0

GT 0

FCV 0

GT FCV 0

0 FCV NAM N

NAHF N

MF NAM N

HF HF NAHF N

NAM N

NAHF N

N H

N N A N

H N A N A A

N N A N A 0

NANA N

NANA N

0 0

0 N A NANA N

N NA=

N 0

-0 0

NA NANA N

N NA

PLANT Nine e Point Unit 1

PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 5 of.17-Isolation Valves

~ C aJ 0 n5 5

5-

~ ~

QJ QJ C3 5

QJ-W 5

CX. K QP IIIP I

4/P CJ I

6 QJ 4/l 4/J QP 44-lg 5

XJJ tXPo E QP QP 5 M QP XJJ QP 4/P r NC QP 5D I

U QP O u

r 0 D 5

r O U S-QJ QP E

lU) 0I

~ ~ r

(/J tg CU~

C QJ 0

OPO

, cn.rO 0r O0 5-0 I

u

<<C QP QC

'r 0 CLM QJ 5

cn 0 O QJ II/l tl r

QJ g r U. I QJ0 5

0 5-QP 0

PJ r U O

.r 5

C 5

0 C I

t

~r 5:

Vl 0 0 r CX 0

0 D

(/J QJ 4J ~r 4/l u 0 u O

<<5:

Positions QJ 5-5-W QPr P r 0 4XP CLU Comments X-29(5 1

React.Recir.S sInst N

5 0

GTNAM 0

0 0

N A

-29

-29 1

R 1

React.Recir HF X-29 1

React.Recir.S sInst N

-41 5

1 React.R ir X-41 1

React. Recir. S s Inst N

W HF GT NAM 0

FCV N A HF N

N A

A X-41 1

React.Recir.S sInst N

5 4

X-44 1

R~, R5J:i r.,5ys~

React.Recir.S sInst N

5 N

5 N A N A 0

GT

~N HF X-44 1

React.Recir.S sInst N

X-44 1

React; Reci r. S s Ins t N

5 HF 0

0 0

N A X-44 1

React. Recir. S s Inst N

5 N A 0

FCV NA'HF N

N ANA NANANANA X~42 5

1

-42 React. Recir.~Ss Inst N

II I '!I N A 0

FCV N

HF X-42 React.Recir.S sInst

.Y React. Reci r. S s Inst N

5 5

W W

HF X-38 1

React.Recir.S sInst N

React.Recir.S sInst 55 W

0 GT NA 0

FCV NAHF N

NA N A N A 0

0 N A NA N

N NA

-38 X-38 1

X-47 1

-47 R

r React.Recir.S sInst React.Recir.S sInst React.Recir.S sInst HF HF

/A. K N

N A N

R tR S

I st X-47 1

X-47 1

React.Recir.S sInst

~NA N A 0

GT NAM N

NA HF H

N 0

0 0

N A 1

PLANT Nine le Point Vnit 1 PRIHARY CONTAINMENT ISOLATION SYSTEH DATA PAGE 6 of 17.

Isolation Valves Or O~

<<P S

S

~ M QP CP ~

QP Cl A

QJM

~r C/l QJ QP ld lg0 Q QP QP S-

~ QP VPM QCM Ar VlC CP S

<<Jl U

CPM O r 0 D S

CL U S-QP QP rst K 0

~l

~

Mc cO cO~

S: QJ 0

<<PPO VP r0 0r JSJ 0

S-0 V

I 0

<<C QP M

0 Err

<<P M I

0 S-0 CP S

Vl0 O QPVl CD tl r

QJ

~E I

U. I QJO S

0ln CJ r U O

~r S

C C

~ 0 0 S:

r I

'r S

Vl 0 0'r Q

Positions QP0

~ ot Vl O 0

<<J

<

0 I 0 D J I Q Es CJ CJ J3 r stJ) 0~ ~ t77 IXJ SVJ~ M QJ 0 070 th 'I-0 0 Og IXJO $-0 stJ 0 cC I O ~=I: CJ QO r 0 I O 0 0 CJ S-sjs O O CJ sjs el ~CJ IQ EX. J CJO 5 0 Cll 0 SXJ r V 0 ~r D ~ C C 0 C I I C0 0 El 00 CJ0I XJl0 O CX. IC: Positions CJ CJr I 0 stJ O Xs Comments X-53 Reactor Vessel Inst N N A 0 GB N A H N X-53 Reactor Vessel Inst N ~ 0 FCV QNA HF N A '-'54 N A X-54 EC Elbow Flow Meter N -64 X-64 CAD S CAD S stem Sam le A 201.7-E 01 A 201.7-E 0 DCV 0 DCV AO AO 60 A D X-71A X-71A X-71B X-718 X-71C X-71C X-71D X-71D X-71E X-71E F -71F -72A X-72A Reactor Vessel Inst Y Reactor Vessel Inst Y Reactor Vessel Inst Y'eactor Vessel Inst Y EC Elbow Fl i r EC Elbow Flow Meter Reactor Vessel Inst( Reactor Vessel Inst Reactor Vessel Inst Reactor Vessel Inst actor Reactor Vessel Inst React r Ve 1'nst Reactor Vessel Inst 3 3 W N A N A N/A 0 GB 0 FCV 0 GB HF HF HF HF HF N A N/A N A H N A N A N A A N Q 0 N/A N/A N/A 0 0 NA AN A PLANT Nineoie Point Unit 7 PRIMARY-, CONTAINMENT ISOLATION SYSTEM DATA PAGE 8 of 17.. Isolation Valves sJ 0 itS S S ~ ~ Q7 QJ ~ C S Q7 X CL~~ QJ QJ E ) 0~r V7 ttS itS~ CQJ O VZl Vt 'r O 0 00 S-0 O 1 O cC Q7 EC '~0 Err CLM 0 Q7 S-Vt 0 0 Q7 I Vl ~ Q7 r2 r LL.~ Q70 S-0 S 0 O 0 ~r S 0 0 C I I ~r C Vl 0 0 r CL M 00 QP0 4J V) 0 O D O Positions Ql S-S Qir w'I 0 cQ CLLt Comments X-72B -72C X-72C X-720 X-72D X-72E X-72E X-72F -72F X-74 1 Reactor Vessel Inst 1 Reactor Vessel Inst EC Elb 1 EC Elbow Flow Meter 1 React r Reactor Vessel Inst 1 . Reactor Vessel Inst 1 Reactor Vessel Inst Reactor Vessel Inst 1 Reactor s 1 Inst 3 4 ILRT Sam le Pt. 3 4 ILRT Sample Pt. Y 5 W W 5 W 2 A 2 A 20.2-41 201. 2-N/A N A N A N A FCV GB FCV GB GB N/A N A N A N A N~A HF HF HF HF HF N/ N/ N A N N N N N N H N 0 N 0 N'ANA N 0 0 0 0 0 NANA 0 0 C C N/A N A N A X-80 X-80 1 2 1 2 ILRT Sam le Pt. ILRT Sam le Pt. N 'N 2. A 2 A BlB.. N A C C C C X-80 X-82T5 '-82 -82 -82 -98 1 2 ILRT Sam le Pt. 1 Reactor Vessel Inst 1 Reactor Vessel Inst 1 R actor Inst 1 Reactor Inst 1 CAD S s~m le 2 I 01.6-A I2 03 3 W 4NA N A GT FCV AO N N RM 60 N 0 N/P, NJg 0 0 0 0 0 C N A -98 1 CAD S stem Sam le 2 A 201.7-04 DCV AO RM 60 D 0 0 C X-75 X-75 X-75 Main Steam Flow Im N Main Steam Fl owIm i N Ma>n S Im N Main SteamFlowImp / N 10 S 10 S 10 N A N/A 0 GT. FCV GT FCV NgA N/A Hlk. N/A HF JNA NQA N N/A ~N ~N N/ N 0 N 0 N/ 0 0 0 NJA N/A 0 PLANT. Nine Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 9 of 17. Isolation Valves ~ C0 ~f sXJ 5-5 ~ W Ql QJ D C E Ql CL Z X-122 X-122 ~s Ql M f 4/3 QJ s 3/4 Service Water 3 4 for Dr Ql s4-sXJ 5 Vl sXJ 0 E Cl Ql 5- ~ Ql VJ QJ Ql 0 0'f-0 D 5-s CL SX 8 W 8 W 5 Ql Ql ) DE ' 0 ~ sM sS/J s(5 sxl~ sC Ql 0 OXO VJ r 0 0f 4XJ 0 I GT 5-0 O I O <<5: QJ EC ~r Q 4r Ci ~ 5-0 4/J Ql ill0 O Cl ~ Vl s QJ sE XJ. I QlO 5-0 4/) 5-Ql 0 r V O ~r 5-Q O ~r s ~r Vl Q Q 'r O LC 0 4/3 CJ +'r VJ 0 O U 0 <<4 0 l:C Positions Ql 5-5-W Qh ~'s0 sXJ O LJ Comments X-122 X-131 2 Li uid Poison 1 B 42 01 M q. N A H N H D 0 C 0 0 A X-131 Li uid Poison B

42. 1-02 N/A I

CK N/A RF t'l/ N/A N/A N/A /A N/A /A -131 X-129 X-129 X-133 X-133 X-134 X-134 Littuid Poison 2 Reactor Head S ra 2 Reactor Head S ra 1 Reactor Vessel Inst 1 Reactor Vessel Inst Dr ell Airborne. Monitor 1 Dr ell Airborne Monitor Y N 1 B 42 1-1 W 34 02 1 W 34-01 2 A 2 .7-08 2 A 201.7-09 N A N A N/A E 0 CK I CK N 0 GT MO 0 GB N 0 FCV N 0 DCV AO RF A RF A A MC M ( A HF A A MC N A tl A 30 N/A 60 NANA NANA AC 0 N N/A N/A A D N A N/A A N A iV A 0 0 N/A /A =N/ N/ C C 0 C C A N 0 C AI X-137 X-137 X-3 X-13 12 12 Cont. S ra Inlet Cont. S ra Inlet ecsrculation S s. Reactor Water Samnl R 1 W 80-18 1 W 80-16 N A anual 0 CK N 0 GT AO RF NA N A N A N A N A 0 H N N A NANA 0 0 N A X-13 X-81 1 Recirculation S s. N Main S 1 MainSteam FlowIm 5 N 1 MainSteam Fl owIm 5 N ann earn ow m 6 W 10 S 10 S 1 S N A 3QA N A N A CV N A gA PLANT Nine le Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 10 of 17 Isolation Valves O I S-S. ~ ~ QP QJ D C 2 Q QP PvP IVl QP rtP C V) IXP O EQJ QP S 4-P QJ VJ QJ Ae VP C QJ D 0 r-0 D S-r O SJ S-QP QPD rtp c 0 il rtP ttP~ C QP 0 UZI VP'r 0 0 I ltPO0 S-0 rtPD O I O eQ. QP'0 EC ~r Q Srr Q ~ 0 0 t/P QJ S-V) O 0 QJ VP Ol r QJ r I ta-I-QP0 S-0 S-0 0 0 ~r S+J C C ~ 0 C0 C ~r r ~r C VP Q 0 'r O 0 QP0 M'r Vl 0 O U CL <<Q: Posi tions QP S-S- & QPr 7 r 0 iXP O SX Comments X-139 1 X-139 1 X-140 12 Reactor Water Sampl Recir ula Cont. S ra Inlet 6 W 1 W 80-17 N/A 0 FF N/ GB N HF /A N/A N/A N/A N/A /A N/A N/A X-140 12 -149 12 X-1 9 12 X-150 12 Cont. S ra Inlet Cont. S r Cont. S ra Inlet Cont. Sra I 1 t 1 W 8- .89=38 80-36 Manual 0 CK Gl N A AO RF RMC ANANA 60 A N A N A A 0 0 N A X-150 12 X-156 4 X-156 4 X-1~7 Cont. Spray Inlet Recirc. Pum Coolin Water Return ec>rculation Pue Cool>ng Rater Sup 1 W 80-35 1 W 1 W 70-92 1 W 1 W 70-93 Manual N~A Manual Manual N A T A I GB N 0 GB MO I GT SO 0 CK N RMC RF N 30 DC JANA DC <ANANA N A 0 0 0 0 N A A AI N A N A X-168 X-174 3 4 3 Or Level Imp. Line Control Rod Drive to Reactor 2 A 1 W 301-114 Manual N A I GT N >Ar X-174 3 X-174 3 X-. 230 3/4 X-23D 3/4 X-0 34 Control Rod Drive to Reactor Control Rod Drive to Reactor N Pur e to TIP N Pur e to TIP N Pur e to TIP reathing A or rywe 113 1 W 30-1 N 201. 2-65 1 N 201.2-39 1 N " 201.2-40 8 A 8 A N A N A ~NA N6 N/A 0 GT N 0 CK N I GT N/ 0 GT N/ 0 GT gN RF NgA N/A H A N~A H A N.A H ANANA N A N A N A N A NANA C 0 N A N A N A PLANT Nine Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 11 of 17 Isolation Valves ~ 0 I 4 /Cl S-S-. T ~ Ql QJ M S-Ql O 3-Ct Z QJ t C/rl QP CCS C C/l 0 F Ql QJ S M QJ C/l Ql QC C/rl.r Vl C Vl Vl QJ 0 Q ~ 0 D S-n Cn U S-Q) QJ E CCS 0 I /Cl~ r CQP O USQ C/l 'r Q C0 ~ y nclO0 a. 0 nCSO Cl I O eQ: Ql0 EC r 0 ~r O M I O tJ QJ Vl tJ 0 Ql Vl ~ Ql r U I V 0 ~r S C CQ 0 C I I ~rVl Q 0 'r O Positions Ql W 'r Vl CJ 0 O Ct. nQ; QJ S-S (De 0 /Cl O U Comments XS-316 S-316 XS-316 3/4 3 4 D/P Points for ILRT N DPPoi t fr T D P Points for ILRT N A N A 0 GT NAH N NA GB N 0 0 XS-321 XS-321 XS-321 3 4 Upp. tmos. 1 Sam le tm Sample Su Am Sam le Su r. 0 Sam . Ret .N A Kl2= 23 201. 2-E 24 N A ~RF N NA DC N A D C N AN A N A N A XS-321 XS-321 XS-328 Su

r. 0 Sam Ret 2.

S~ur. Saniale Ret. Su r. 0 Sam . Ret N 01.2-7 N A Ol. 2-7 AO RF N N JUL ANANA A N A XS-328 S-328 3/4 3 4 Su r. Sam le Ret. S r. m $09 201.2-112 'E 0 AO XS-328 XS-324 XS-325 XS-326 3 4 12 Su r.. Sam l Su 1 N Cont. S ra Suction Y Cont. S ra Suction Y Torus S ra 80-N 70 AC D 0 0 0 AI XS-326 Torus S ra~ 80-39 CK. L'3~ 3/ PLANT Nine e Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 12 of 17 Isolation Va'ives I rXJ S-S- T M CJ CJ M S CJ0 K CJ I S-D OJ r U QJ M V'r 0 D S-r D U S QJ QJ rXJ) S0 'I~ ~ v) rXJ~ C CJ 0 UZI VJ 'r 0 0 I 0 S-0 rXJ V I V rC: QJ0 EC r 0 Err CX.M I rXJ V 0V QJ S XXJ V 0 QJ r rIJ r CJ U. J-QJV S 0t/l S QJ 0 Q V O ~ r S O I I ~rv) 0 0 ~ r Q 0 CA ~ rl V) V O V O Positions CJ S-S QJr I 0 rXJ O U Comments XS-327 20 Suppr. Vent&Purge N XS-3 7 20 Su

r. Vent&Pur e N

XS-327 3 N Hakeu & Bleed N XS-327 3 N Makeu 8 Bleed N 1 N 1 N 1 N 1 N2 201-16 201-17 201.2-33 201.2-06 0 It AO A RH 60 A D C C X 0 XS-330 4 Torus Makeu Torus Makeu 1 W 58.1-01 58. 02 Manual 0 DCV RMC N RF 60 XS-332 12 Core S ra Suction Y XS-334 6 Core S ra Test Ret Y 1 W 81-01 40-05 Manual 0 GT RM XS-335 XX3M 12 XS-337 XS-333 12 Core S ra Suction Core S ra Suction 6 Core S ra Test Ret Core pray Suction Y 1 W 1.W 1 W 81-22 8l.23. 81-02 Manual 0. .anna.) W Ha GT RMC N 90 AC 0 C C AI AI X - 1 Cont. S rag Suet>on. XS-342 12 Cont. S ray Suction on . pray est > ne XS-352 4 Cont.S ra .Te t Line to Wa Dis osal X - 0 20 Torus Air Vent&Fill N XS-340 20 Torus Air Vent&Fill: N lJA 1' 201-08 201-07 80-02 80-01 80-43 Manual 0 Manual 0 N A 0 GT GT GT N A RHC N 70. kC 0 7 AC N H I 9. 0 LC 0 ~ 0 LC LC PLANT Nine e Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM OATA PAGE 13 of 17 0 Isolation Valves ~ C0r 0 ~ 4 e S. 5 ~ M Ql QP M C QJ 3- 0 QPN I Cl) QJ I QJ rp-r(5 5 Vl rrJ'0 QJ CP 5- ~ QP +CAN Nr VlC Vl QP O Q'r 0 0 5-r 0 U 5-CJ QJ E rC) K 0 rr rK QP O UPO Vl r 0 0 I u0 50 O I l55 u <<6 QJ ~0 ES0 Sr r O ~ I O 5-0u QP V7 QP5-Vl0 O QP r Vl ~1 ~ QJ U. I 5-CJ 0 U O ~r 5 5= 5:0 0 ~r 'r ~r 5 VP0 O Positions QP0 4J r Vl 0 0 O A 'J S-5 Clr P,r O% O U Comments XS-354 3 Torus Spray XS-354 3 Torus S ra XS-354 3 Torus S ra XS-365 20 eactor Water Cleanu N W 80-65 N/A 0 W 80-68 W 63. N/A RF R F RF N NANA NA N A XS-365 20 Relief to Torus N O.P. 63 ~ 1-01 N A 0 CK NApg PRIMARY CONTAINMENT ISOLATION SYSTEM WATER Page 14 of 17 Footnotes for Isolation Valve Table 1. The valves in the emergency condenser steam supply line remain open during an accident unless there is a break in the emergency condenser line, indicated by high steam flow in the emergency condenser line or high radiation in the emergency condenser vents. These signals automatically close the valves. 2. The air operated valve in the emergency condenser remains closed during accident conditions. They are opened by high reactor pressure or low-low water level signals. The air operated valves. will then remain opened unless a break in an emergency condenser line is indicated as discussed in (1) above. 3. The Core Spray System is considered to be an extension of. containment, therefore core spray valves 40-01, 40-09, 40-10 and 40-11 do not automatically isolate. These valves open on a low reactor pressure signal in conjunction with a high drywell pressure or low-low reactor water level. If the Core Spray System is not needed to maintain reactor vessel water level, these valves can be isolated manually. 4. The drywell vent and fill line consists of a 20-inch line which penetrates primary containment. Once outside primary containment, it branches into a 24-inch vent line and a 4-inch nitrogen supply line with each line containing two isolation valves. 5. There are two lines per penetration for the reactor recirculation system instrumentation. Each line has a manual gate valve and a flow check valve outside containment. 6. The Containment Spray System is considered to be an extension of containment, therefore, the containment spray valves do not automatically isolate. If the Containment Spray System is not required to mitigate the consequences of an accident, it can be manually isolated from the control room. En ineered Safet Function NINE MILE P T UNIT 1 PRIMARY CONTAINMENT I OLATION SYSTEM DATA Page 15 of.17 ABBREVIATIONS Isolation Valve T e Isolation Si nal Codes N=NO Y=YES Pos ition Indicati on in Control Room D =. Direct I = Indirect N = None Others stated in Table Fluid A = Air B = Sodium Pentaborate S = Steam W = Water N = Nitrogen 2 Isolation Valve Location I = Inside Containment 0 = Outside Containment Others stated in Table Isolation Valve Actuation Mode A = Angle B = Butterfly BCK = Ball Check BL = Ball CK = Check DCV = Diaphragm Control Valve FCV = Flow Check Valve FF = Flow Fuse GB = Globe GT = Gate RV = Relief SCV = Stop Check SV = Solenoid VB = Vacuum Breaker Isolation Valve Power Source A = Air AC = AC DC = DC H = Hand Isolation Valve Actuator Code Parameter(s) Sensed ~or Grou for Isolation A High Steam Flow-Main Steam Line High Radiation-Main Steam Line Set Point units < 105 psid < 5 times normal background. Low Low Low Condenser Vacuum High Temperature-Main Steam Line Tunnel Low Low Reactor Water Level High Steam Flow Emergency Cooling System 7 inches mercury vacuum < 200F > 5 inches Indicator Scale < 19 psid Low Reactor Pressure > 850 psig A = Automatic HF = High Flow H = Manual OP = Overpressure RF = Reverse Flow RMC = Remote Manual Control Room RM = Remote Manual (Local) Isolation Valve Positions AI = As Is C = Closed 0 = Open AO = Air HO = Motor SO = Solenoid-High Radi ation-Emergency Cooling System Vent < 25 mr/hr NINE MILE POINT UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA Page 16 of 17 ABBREVIATIONS (Continued) Isolation Si nal Codes Continued Code 'or Grou Parameter(s) Sensed for Isolation Set Point uni ts Manual Low-Low Reactor Water Level High Area Temperature Low-Low Reactor Water Level High Drywell Pressure N/A > 5 inches 71ndicator Scale) < 190F for Cleanup System < 170F for Shutdown - Cooling System > 5 inches YIndicator Scale) < 3.5 psig NINE MILE POINT UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM OATA Page 17 of 17 Fi ure Codes 1 = C-18006-C 2 = C-18014-C 3 = C-18015-C 4 = C-18017-C 5 = C-18020-C 6 = C-18041-C 7 = C-18022-C 8 = C-18578-C 9 = C-18012-C 10 = C-18002-C PLANT Nine Mile Point Unit 1 DESIGN REQUIREMENTS FOR CONTAIN11ENT ISOLATION BARRIERS question: Discuss the extent to which the quality standards and'eismic design classification of the containment isolation provisions follow the recommendations of Regulatory Guides 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Water-Containing Components of Nuclear Power Plants", and 1.29, "Seismic Design Classification". R~es onse: The codes used in the design of Nine Mile Point Unit 1 Class I systems at the time of construction were ASME Section I ANSI-B31.1-1955 and ANSI B16.5-1955 with requirements of ASME Section III for non-destructive testing. For subsequent modifications which involve the addition of a complete new

system, Niagara Mohawk is committed to follow the recommen-dations of Regulatory Guide 1.26, Revision 3.

For example, the Containment Atmospheric Dilution System, including portions of the Vent a'nd Purge and Containment Radiation Monitoring Systems, was added subsequent to commercial operation and followed the quality standards recommended in Regulatory Guide 1.26. The containment isolation valves are all part of Class I systems. The classi'fications used at the time of their design were equivalent to the seismic.design classifications of Regulatory Guide 1.29. PLANT Nine Nile Point Unit 1 PROVISIONS FOR TESTING Question: Discuss the design provisions for testing the operability of the isolation valves. R~es oese: All power-operated reactor coolant system isolation valves and containment isolation valves which are normally opened can be tested for operability during power operating conditions. The Nine 11ile Point Unit 1 Technical Specifications requires all normally open power-opera'ted isolation valves (except the feedwater and main steam line power-operated isolation valves which are exercised by partial closure and subsequent re-opening at least twice a week) to be fully closed and re-opened at least once per quarter. All power operated isolation valves which are normally closed can be tested for operability once per operating cycle. This is considered sufficient for these valves since they are only opened during infrequent intervals. 0'1 PLANT Nine Hile Point Unit 1 CODES) STANDARDS, AND GUIDES Question: Identify the codes, standards, and guides applied in'the design of the containment isolation system and system components. R~es ense: The ASHE Section I and ANSI-B16.5-1955 codes were applied to the design of isolation valves. In addition to these code requirements, ultrasonic and radiographic examinations of isolation valves were performed, as well as seismic and thermal analyses. An independent third party review of calculations was performed and found acceptable. The Containment Isolation System electrical equipment was designed to withstand the accident environmental conditions appropriate to its location. "For the drywell, these conditions were short term accident conditions of saturated steam at 62 psig and 310 F. The Reactor Building environmental accident conditions for which the Contain'ment Isolation System el'ectrical equipment was designed are 100 percent humidity, 150 F and a 3125 psig ~ All electrical specifications for Class I electrical equipment called for seismic design analyses of either of the following: 1. The maximum ground motion acceleration is 11 percent of gravity and the maximum resulting response acceleration is 45 percent of gravity for oscillators in the period range of 0.2 to 0.3 seconds'r 2. A minimum factor of 0.20g horizontal and 0 '0g vertical should be used unless a specific dynamic analysis is, made in which case it should be referred to the Purchaser for his approval. PLANT Nine Mile Point Unit l NORMAL OPERATING MODES AND ISOLATION MODES Question: Discuss the normal operating modes and containment isolation provision andprocedures for lines that transfer potentially radioactive fluids out of the containment. R~es ense All systems which could transfer potentially radioactive fluids out of primary containment would automatically isolate on a primary containment and/or reactor vessel isolation signals. The only isolation sy'stems which do not automatically isolate on these signals are the Emergency Condenser, Containment Spray and Core Spray Systems. These systems are considered essential systems to mitigate an accident and; therefore, are not isolated. The Emergency Condenser System will isolate on system high flow or high radiation of the Emergency Condenser vents. There are six potential pathways for radioactive gases or liquids to be transferred out of the primary containment. a. N vent and purge system. b. CkD System. c. Drywell floor and equipment drains. d. , Recirculation sample line to reactor building sample sink. e. Suppression chamber transfer to waste disposal system. All of the above except items d and e would isolate on a contain-ment isolation signal. Overrides are provided for items a and b such that they can be manually re-opened for controlled venting and monitoring purposes. Venting would take place through the Reactor Building Emergency Ventilation System. This system would not isolate on high radiation.. By procedure, venting is allowed only after containment atmosphere has been sampled and analyzed'he drywell floor and equipment drains transfer liquid under normal operation. These lines isolate on high drywell pressure or reactor low-low water level. Since water level below the top of the fuel is required to produce significant fuel failures, highly radioactive liquid would not be automaticaly transferred to the waste building. Activity in these lines is not normally monitored, however, positive valve position indication is provided in the control room. The drywell high pressure 'signal which initiates containment isolation has a seal-in feature so that both Reactor Protection System channels must be cleared and manual resetting accomplished before any isolation valves not provided with overrides can be re-opened. The isolation valves may then be manually opened from the control room.

Thus, the pumping of drywell drains cannot be performed, inadvertently.

R~es oese Normal Operating Hodes and Isolation Hodes (Continued) The recirculation sample line contains three (3) one (1) inch manual valves in a line connected to a reactor recirculation line. These valves are normally closed except during a sampling procedu re. >e discharge of these 1 inch valves reduces to 1/4 inch tubing which runs around 50 feet to a sample sink. A flow fuse is in-stalled outside of primary containment to limit flow through the duline. Niagara Hohawk will install two automatic isolation valves uring the next scheduled refueling outage scheduled for'early 1981. These valves will close on high drywell pressure or low-low reactor water level. The isolation valves will be provided with manual overrides to permit sampling during an isolated condition. In the interim, operating procedures will be modified to en that o i sure a positive administrative control assure that the sample line is not inadvertently left open after use. During sampling', a member of the Operating Staff will continously monitor sampling activities and verify that at least two valves are closed when sampling is complete. The suppression chamber transfer to waste disposal system line requires a locked closed valve to be open to pump water out of the suppression chamber. The valve is normally locked closed except when pumping water out of the suppression chamber to maintain level. Ualves capable of automatic isolation on either low-low water level or high drywell pressure will be installed by the next refueling outage. In the interim, whenever the suppression chamber is being pumped

down, a member of the operating staff will be stationed to close the valve should an isolation signal be received.

i