ML18037A210

Forwards Info Re Containment Isolation Barriers in Response to NRC 790713 Ltr.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~F LL~ 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 1 1 02 NRC PDR 12 ILE- 2 2 14 TA/EDO i5 CORE PERF BR=- 1 i i'/ ENGR BR iS REAC 8FT7 SA 1 i9 PLANT SYS BR 20 EEB i 21 EFI.T TAT SYS 22 SRINKMAN i EPB" DOR OELD 1 0 EXTERNALS 03 LPDR 1 1 04 NSIC 23 ACRS 16 16

@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 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, 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,

'g~P~

NIAGARA MOHAWK POWER CORPORATION Donald P. Disc Vice President Engineering PEF: jk

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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 Shared Between S stem or Com onent Units Numbers N/A N/A

PLANT Nine Nile Point Unit 1 PLANT-SPECIFIC SYSTEM INFORMATION General Mater Sources Instrumentation and Control. Frequency of Safety Seismic Safety Seismic Safety Seismic System and

~Sstem Classification Ca~e<aCor Classification ~Cate or Classif. ~Cateoor Co.".,oonant Tes-s Emergency Condenser Safety Related I Safety Related Safety Rel. I Once each operating cycle 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 Safety Related Safety Related 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 Auto Depressurization System Safety Related N/A N/A Safety Rel.

I 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 General Mater -

Sources Instrumentation and Control Frequency o Safety Seismic Safety Seismic Safety Sei smic Syste.": and

~Ss tern C'lassification ~Cate or C'lassification ~Cate or Classif. ~Cateoor Cor:,oorert e.sts Safety Valves. 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 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 General Water Sources Ins trumen tat i on and Control Frequency of.

Safety Seismic Safety Seismic Safety Seismic System ard

~Sstem C'lassification ~Cate or Classification ~Cateoor Classif. ~Cateoor Coroonent Tests reactor Building Closed Loop Cooling Mater System Safety Related I Safety Related Safety Rel. I Normally in service Control Rod Drive Safety Related I Safety Related Safety Rel. I Automatic startup of each pump is demon-strated once per

• operating cycle Condensate Storage Tank Safety Related I Non Safety Related Non Non Safety Non N/A Seismic Related Seismic Hain Feedwater (pressure Safety Related I Safety Related Non Safety Non Normally in service boundary) Related Seismic Cooling Mater to Recirculation Pump/Hotor Safety Related I Safety Related Safety Rel. I Normally in .service

PLANT Nine e Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 1 of 17..

Iso'l a ti on Valves O O I

~ r S-CJ S-CJ O Positions O

r CJ N O S cC CJ VJ O

O QJ S-O O

~D S S I

C/) C/I S ~ ~Cn r O O r C/I C/l 0 I

C I O o

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CJ QJ CJ Ar O' O CJ QJ QJ D

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C CJ Q

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O UZ)

CIJ r O CCJ O O Srr 0

a U. J I O Q

CIJ O r O

C/l CIJ O O O O O *cX: OU CCJ Comments X-2A 24 Main Steam N 1 S 01-01 A GB NO A RMC 10 AC 0 0 C C AI X-2 24 Hain Steam N 1 S 01-03 A AO A X-28 24 Hain Steam 'N 1 S

- X-28 24 Hain Steam N 1 S 01-04 A A AO A RMC 10 A D C C S 39=Q9. MO A RMC 0 AI

-3A 10 Emer X-38 10 Emer en Co d X-38 10 Emer 9. enc Condense Y 1 S 39-08 8 GT MO A RMC 18 Feedwater 1 W 31-04 C GB NO RM A 6 0 A 18 Feedwater 31-02 N A CK A RF NANA N A N A NANA ee water N 1 W 31-03 C GB HO RMC N A 60 AC D 0 0 AI ee water N 1 W 31-01 N/A 0 CK N RF NANA N A NANA NANA X-5A 10 Emer enc Condense Y 1 W 39-04 N A I N/A X-5 10 Emer en'ondense Y 1 W 39-06 0 DCV A A X-58 10 Emer enc Condense Y 1 JW X-58 10 Emer enc Condenser Y 39-05 8 X-7 14 Shutdown Cool. Rtnj 40 AC. D. C. .0 X-7 14 Shutdown Cool. Rtn 1 W 38-12 N A X-8 14 Shutdown Cool. Su . 1 -W 38-01 0 X-8 Shutdown Cool. Su 38-02 0 React.Cleanu Su 1 1 W 33-03 R L X-9 6 React.Cleanu Su l 33-04 GT NO A X-154 6 React. Cl eanu Su 1 N 1 W 3 -0 X-154 6 React.Cle~anu Su 1 N 1 W 33-03 NLA Q NgA

4 PLANT Ni 1ile Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 2 of 17..

I sol a ti on Va 1 ves CJ I V O

~ r 5

~ C 5 Vl Ql 5-eO C C Positions 0 O 5- 0 O~ E Ql QP 5- 0 5-we0 Vl O

0Ql 0D 5- 5 4-P QJ Vl CP Cl S- 4 I

~VP 0

I 0 I Vl

~

0I C I QP Cl S-

+J Ql 0 0I- ) 0r

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~ Ql Ql XXP~ 5- W 5 Ql fXP CJ M Ql M I- 5: QJ rd IX= I QJ 'r 5 4J CPI C

QP W I Vl C 05-r2 I O Vl.r 00 O

'I Sar 0 r g og 0 'r0 Vl 0&

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O 0

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M CL, M I

44 CL U 0 K U. 5- O Q CLU IXP Commen'ts 0

X-12B 8 Dr ell Co l r W 70-95 N A BCLC f 70-94 Ma OC 0 X-13 12 ore Spra Inlet Y 1 W 40-01 Manual Gj: 90 AC 0 C C AI X-13A 12 ore S ra Inlet Y 1 W 40-09 Manual AC 0 C X-13 12. ore S ra Inlet Y =

1 W gg-(Q Manua'l AI X-1 12 ore Spra Inlet Y 1 W 40-10 Manual GT M X-14 12 ore S ra Inlet Y . 1 W 40 11 anua GT MO A RMC AC 0 C C AI X-14 12 ore Syra~ Inlet W 40 12 Manual X-18 24 r well Vent 5 Pur e N 2 A 201-09 E X-18 24 A'r N 2 A 201-10 E B AO A RMC 6 X-19 20 Dr ell N V Fi1 N 201-31 E B MO A RMC 60 AC D C 0 AI X-19 20 Dr well N .VentslFill 2 N AO 201.2- E 03 X-19 4 Or el 1 N Ventj Fill N 2QlZ-32 Cont. Atmos. Oil 2 A 201.7- E DCV AO A RMC 0 0 0

~

ample Ret.

X-20: Cont. Atkins Oil 60 Sam le Ret.

X-25 Dr~well Floor Or. N 1 W 83.1- E Sum Outlet X-25 4 Or el 1 Floor Or N 1 W 83 1- E Sum Outl e t 12

PLANT N ne e Point Unit 1 PRIMARY CONTAINNENT ISOLATION SYSTEN DATA PAGE 3 of 17.

Isolation Valves I I QJ rd ~ ~

I VO

~ r S I Vl V CJ Positions

~ 0 le C oQJ V S

Q 0 ~cg r gI Ci: QJ Vl V A

CJ M QJ ~l 0 0 S-0 0 S- 0 QJ r EA 0 I=

~ J3 S S ch QJ ~ ~cg~ In 'I r I 00 CJ CJ S-V'r0 ) ClE tg 0

~ CJ S- S- W QJ QJ CJ CJ r I CC CJ lrt$ 0V r QJ CJ r S- a Vl K 0

I r V O OIQ tll r 0 0V V kr0 r

g'r 0 0'r th Q 0V Vl P.r V 0 lO IJ- I- O QJ rIJ 0 Cl SJ O M C/) 0 t/) O- ~ O.U Comments X-26,3 Dr ell E ui . Dr. N 1 W 83.- RM 60 AC Sum Outl e t 09 X-26 3 Dr ell E ui . Dr. N 1 W 83. 1- E 0 DCV AO A RM 60 0 C C Sump Outlet 10

-345 1 R ac W Inst.

X-34 1 Reactor R cir S s N HF Inst.

X-34 1 Reactor Recir. S s. N 5 W N A 0 Inst.

X-34 1 Reactor Recir. 'S s. N 5 W N A 0 FCV NA HFN Inst.

~X-35 5J 1 Reactor Recir. S s. N 5 W Inst.

X-35 Reactor Recir. Sys.

Inst.

N 5 W N /A 0 HF X-35 1 Reactor Recir. S s N nst.

X-35 1 Reactor Recir. S s. N N N/. NJ N/A NjA nst.

X-36%' React.Recir.S sInst N 5 W N A N 5 W HF

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

Iso1ation Valves I

CJ (s

e(S eO I

~

(J r

0S-C S Vl 0 CJ CJ Positions

~

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r~ 'r0 CI Q oQJ O C(: QJ Vl (3 S 0 IV

~VI I CJ 0 0 S- 0 CJVl 0 e(S e

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CJ ee 0 0- e 0 I-M S- S CJ

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CI Ci SJ 0 c QJ'/l (I I 0 CL ed: Comments X-37(5: 1 React.Recir.SysInst 5 W' N/A 0 GT H- N 0 0 0 N A X-37 1 React. Recir. S s Inst W MF X-37 1 React.Recir.S slnst 5 W N A HF W

X-43 1 React.Recir.S sInst W N A X-43 1 React.Recir.S sInst 5 W X-43 React.Recir.SysInst 5 W N A 0 FCV NAHF X-2875 React.R ir eact.Recur.SysInst 5 W N A 0 FCV N N A NANA N A

-28 NAM N N A X-28 React.Recir.S slnst 5. W 0 FCV NAHF N N A A N N A N A

<-32 5 React. Recir.~Ss Inst 5 W X-32 React. Retires inst 5 W N A X-32 React. Recir. S s Inst X-32 React.Recir' I st MF X-31 5 React. Recir.S s Inst 0 GT NAM N 0 X-31 React.Recir.S sInst. HF NANA N NANA X-31 React.Recir S I s HF 0 GT N H N 0 0 0 N A X-30 React.Recir.S sInst 5 W N A 0 FCV NAHF N N N A NANA N N NA=

X-30 React.Recur.S sInst 5 0 GT NAM N N H N 0 -0 0 NA React.Rec>r. yslnst N 5 W N/A 0 FCV NAHF N NANA N N NA

PLANT Nine e Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 5 of .17-Isolation Valves QP PJ r 44- I U O lg .r 5 5 XJJ QJ QJ 0 C Positions

~ C tXP u

5 5 aJ 0 o <<C cn 0 5

E QP QP O QJ 0 QP IIIP QP 5 M QP 0I 0r 5-0 I I/l 0 C QJ

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~ ~tg rCU~(/J tl 5-I t 0 QJ 5- W 5-QJ 5 QP ur r 4J

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5 QJ QJ-W CX. K CJ I

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0 cn.rOOPO 0O CLM 0 gr 0 U. I CX 0 0 Vl r 0 D

(/J 0 uu 0 4/l P r O <<5: CLU 4XP Comments X-29(5 1 React.Recir.S sInst N 5 0 GTNAM 0 0 0 N A

-29 1 R HF

-29 1 React.Recir X-29 1 React.Recir.S sInst N HF

-41 5 1 React.R ir W GT NAM X-41 1 React. Recir. S s Inst N 0 FCV N A HF N N A A X-41 1 React.Recir.S sInst N 5 X-44 4

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

React.Recir.S sInst N

N 5

5 N

N A A

0 GT ~N HF X-44 1 React.Recir.S sInst N HF X-44 1 React; Reci r .S s I ns t N 5 0 0 0 N A ANA NANANANA

'!I X-44 1 React. Recir. S s Inst N 5 N A 0 FCV NA'HF N N X~42 5 1 React. Recir .~Ss Inst N N A

-42 II . I 0 FCV N HF X-42 React.Recir.S.YsInst N 5 W React. Reci r. S s Inst 5 W HF React.Recir.S sInst N 55 0 GT NA 0 0 N A X-38 1 React.Recir.S sInst W 0 FCV NAHF N NA N A N A NA N N NA

-38 R . r /A. K N X-38 1 React.Recir.S sInst HF X-47 1 React.Recir.S sInst

-47 React.Recir.S sInst HF N A N X-47 1 R tR S I st ~NA 0 GT NAM N NA H N 0 0 0 N A X-47 1 React.Recir.S sInst N A HF 1

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

Isolation Valves QP I

I CJ U O r

ld ~ r S lg 0 CP QJ O C C Positions S

~0 O~<<Pr O A 0 0 S QJ Q QP <<C QP Vl 0 0 S S

~ r M

C/l

~VPM QP S-QP CP S-0

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QPr QP Cl Vl C

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st K VP r0

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<<P M U.

I I Q 0'r0 Vl Vl O 0

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Comments X-40 3/4 Drywell 0 Samp.Ret N 2 A 201.2- N/A 0 GB N/A N/ N/A H 0 0 0 N/A X-40 3/4 Dr well 0 Sam .Ret N 2 A 201.2- N A 0 CK NQA N A NA NANA 67 0 Sam .Ret N 2 A 201.2- N A 0 CK NA RF A N A 68 X-48 1/2 Dr well 0 S m GT SO RH 60 DC D' Supply 25 X-48 Dr well 0 Sam le N A 201.2- E GT SO RH 60 DC Su 1 26 X-49 Dr Hell 0 201. 2- E GT SO RH 60 DC Su 1 29 X-49 Drywell 0 Sample N 2 A 201.2- E GT SO RH 60 DC 0 0 C Supp y 30 X-50 Dr well 0 2...Sam le N 2 A 201. 2- E G Q 0 0 Su 1 27 X-50 1 2 Dr well 0 Sam le N 2 I A 201. 2- E GT SO RM 6 DC 0 0 C Suppl 28 X-51 1 EC Elbow Fl t r Y H N. 0 n N/A X-51 1 EC Elbow Flow Heter Y 4 N A N N A N A

/

PLANT Nine e Point Vnit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 7 of 17 Isolation Valves I

CJ SXJ r C VJ I

O CJ CJ D~

~ r 0-V Positions

~ C stJ S- O C C 0I 0 O 5 Q CJ ~ =I: CJ sjs O CJ3 C 0 $ - O CJ 0 0 stJ S- S-M CJ IJJ CJ CJ, $ - ~ ~SVJ~ 0 Og 0 QO 0 sjs Cll I

C I 0 CJ CJ t77 $

T M CJ QCN CJ 'Z> el 0 0 AI- 5 0I CJ CJ IXJ stJ

~c2 0 0 CJ JD J3 M QJ CJ C I CJr 0 I 0th 'I-0 IXJ ~

Q

) 070 0 0 D r O r I XJl I 3- CL CJ K SJJ C I J stJ 0 EX. J 0 0 O 0 stJ

~ -IEXJIe- Q Es cC El CX. IC: 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 CAD S A 201.7- E 0 DCV AO 01 X-64 CAD S stem Sam le A 201.7- E 0 DCV AO 60 A D X-71A Reactor Vessel Inst Y N A 0 GB X-71A Reactor Vessel Inst Y X-71B Reactor Vessel Inst 3 X-718 Vessel Inst Y Y'eactor 3 HF X-71C EC Elbow Fl i r 0 GB X-71C EC Elbow Flow Meter HF N A N A N A A N X-71D Reactor Vessel Inst( N/A H Q 0 X-71D Reactor Vessel Inst W HF X-71E Reactor Vessel Inst N A X-71E Reactor Vessel Inst F actor 0 0

-71F Reactor Vessel Inst HF N A NA AN A

-72A React r Ve 1'nst X-72A Reactor Vessel Inst N/A 0 FCV HF N A N/A N/A N/A

PLANT Nineoie Point Unit 7 PRIMARY-, CONTAINMENT ISOLATION SYSTEM DATA PAGE 8 of 17..

Isolation Valves 1

~

O r

0 S

Q7 S-Q7 0 Positions sJ 0 O S- 0 cC Q7 Vt 0 0 0 S- 0 Vl Q7 0 0 itS

~ritS~ 0 I C 0 Ql

~ ~~

S S Q7 QJ QJ ttS V7 S

I I 0

QP 0 S S-QJ CQJ EC 0

'~0 Q7 ~ r C 4J Qir 00

~

C O 'rVZl 0 0 0w'IcQ S Q7 X CL~~ ) E Vt O O Err CLM r

2 LL.

r

~ 0 CL 0Vl Mr V)

O D O CLLt Comments X-72B 1 Reactor Vessel Inst 5 W N/A N/A N/ N/ N 0 0 0 N/A 1 Reactor Vessel Inst N A FCV N A HF N A

-72C EC Elb N 0 0 0 N A X-72C 1 EC Elbow Flow Meter HF X-720 1 React r W N A X-72D Reactor Vessel Inst Y HF X-72E 1 . Reactor Vessel Inst N A GB N A N N N A N'ANA X-72E 1 Reactor Vessel Inst 5 W FCV HF NANA X-72F Reactor Vessel Inst GB N~A N N N 0 0 0

-72F 1 Reactor s 1 Inst HF X-74 3 4 ILRT Sam le Pt. 2 A 20 .2- N A 41 3 4 ILRT Sample Pt. 2 A 201. 2- GB N N H C C X-80 1 2 ILRT Sam le Pt. N 2. A BlB.. C C X-80 1 2 ILRT Sam le Pt. 'N 2 A N A C C X-80 1 2 ILRT Sam le Pt. 2 I A I2 01.6- 4NA X-82T5 1 Reactor Vessel Inst N A GT N N N 0 0 0 N A

'-82 1 Reactor Vessel Inst 3 W FCV N/P, NJg

-82 1 R actor Inst

-82 1 Reactor Inst

-98 1 CAD S s~m le AO RM 60 0 0 0 C 03

-98 1 CAD S stem Sam le 2 A 201.7- DCV AO RM 60 D 0 0 C 04 X-75 Main Steam Flow Im N GT. Hlk. JNA N 0 0 0 NJA X-75 Main Steam Fl owIm i N 10 S N A FCV N/A NQA ~N N/A Ma>n S Im N 10 S GT NgA N ~N N 0 0 X-75 Main SteamFlowImp / N 10 N/A 0 FCV N/A HF N/A N/ N/

0 PLANT . Nine Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 9 of 17.

Isolation Valves Ql r s4- I VO sXJ ~ r 5-

~ C 5

sXJ Vl Ql Ql O Positions 0f ~s 0 O 5- Q

~ Ql E Cl <<5: QJ ill 0 M

~Ql 5-Ql 0 0 5- 5- O Cl 0 sXJ f ~s S/J 0 ~ Vl 4/) O Ql C ~

5-W Ql 5 4/3 VJ QJ 0

5 M s f ~ r s 0 CJ 5-

~

QJ D C E QJ Ql 0'f-0 D

) DE Ql Ql s

s(5 0

sxl OXO Ql 4XJ

~

EC 0 r Q s

QJE 5-Ql ~ r Vl Q

+'r VJ 0 5- W Qh

~'s 4r Q 'r s

Ql CL Z s 5-s VJ r 0 0 O Ci ~ XJ. I 0 O U 0 <<4 0 LJsXJ CL SX 4/J O 4/3 O Comments X-122 3/4 Service Water 8 W I GT LC 0 l:C X-122 3 4 for Dr 8 W X-122 X-131 2 Li uid Poison 1 B 42 M q. N A H H D N 0 0 0 C

A 01 X-131 Li uid Poison B 42. 1- N/A I CK N/A RF t'l/ N/A N/A N/A /A N/A /A 02

-131 Littuid Poison 1 B 42 1- 0 CK RF A N A NANA N A A N A iV A X-129 2 Reactor Head S ra 1 W 34 02 N A I CK N RF A tl A NANA A N X-129 2 Reactor Head S ra 1 W 34-01 0 GT MO A MC 30 AC 0 0 C AI X-133 1 Reactor Vessel Inst N A 0 GB N M ( A N 0 0 N/A X-133 1 Reactor Vessel Inst . Y N/A 0 FCV N HF A N/A N/A N/A N/A /A =N/ N/

X-134 Dr ell Airborne. 2 A 2 .7- E C C Monitor 08 X-134 1 Dr ell Airborne N 2 A 201.7- 0 DCV AO A MC 60 A D 0 C C Monitor 09 X-137 12 Cont. S ra Inlet 1 W 80-18 N A 0 CK N RF NA N A N N A NANA X-137 12 Cont. S ra Inlet 1 W 80-16 anual 0 GT AO A 0 X- 3 Reactor Water Samnl X-13 R ecsrculation S s. N A N A H N 0 0 N A X-13 1 Recirculation S s. N 6 W Main S 10 S N A N A X-81 1 MainSteam FlowIm 5 N 3QA CV gA 1 MainSteam Fl owIm 5 N 10 S N A ann earn ow m 1 S N A

PLANT Nine le Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 10 of 17 Isolation Valves QP I

~

0 r

0 rtP S C V) QJ QP 0S- C C

+J Posi tions O

IXP O O S-V) O

~0 I QP EQJ eQ. QP

'0 PvP QP S il0 S- 0 QJVP 0 C 0

S- S.

I Vl 4-P QJ S-0I 0 0 rC r QP QP S-

~D

~

VJ QJ 0

0D

~ QP QJ QP QP rtP ttP~ rtP Ol S-M 'r S- &

Ae r- D C QP D rEC 0 r QJ r C QPr

~

QJ ltP C 2 0S-r D 0 UZI O ~

Q r VP Q Vl 0 7 r VP C rtp VP'r 0 0 O Srr

~ I- 0 O0 I 'r 0 O U 0 iXP Comments Q O SJ c Q t/P ta- CL <<Q: O SX X-139 1 Reactor Water Sampl 6 W N/A 0 FF N/ HF /A N/A N/A N/A N/A /A N/A N/A X-139 1 Recir ula GB N X-140 12 Cont. S ra Inlet 1 W 80-17 X-140 12 Cont. S ra Inlet 1 W 8-

-149 12 Cont. S r .89=38 0 CK N A RF ANANA N A N A A N A X-1 9 12 Cont. S ra Inlet 80-36 Manual Gl AO RMC 60 A 0 0 X-150 12 Cont. Sra I 1 t X-150 12 Cont. Spray Inlet 1 W 80-35 Manual T A X-156 4 Recirc. Pum Coolin 1 W N~A I GB N X-156 4 Water Return 1 W 70-92 Manual 0 GB MO RMC N 30 DC 0 0 AI X-1 ec>rculation Pue Manual I JANA DC 0 0 A

~7 X-168 Cool>ng Rater Sup 1

1 W

W 70-93 N A 0 GT CK SO N RF <ANANA N A N A A N

N A 3 4 Or Level Imp. Line 2 A Manual X-174 3 Control Rod Drive 1 W 301- N A I GT N >Ar to Reactor 114 X-174 3 Control Rod Drive N A N A N A N A to Reactor 113 X-174 3 Control Rod Drive 1 W 30-to Reactor X-. 230 3/4 N Pur e to TIP 1 N 201. 2- N A 0 GT N 65 X-23D 3/4 N Pur e to TIP 1 N 201.2- N A 39 X- 0 34 N Pur e to TIP 1 N 201.2- ~NA 0 CK N RF ANANA N A NANA N A N A 40 reathing A 8 A N6 I GT N/ NgA N/A H or rywe 8 A N/A 0 GT N/ A N~A H 0 GT gN A N.A H C 0

PLANT Nine Point Unit 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 11 of 17 Isolation Valves I

QP CCS I O

~

V r

0 S

C C/l tJ QJ Positions

~ 0 $ C C 0Ql O Q I QJ F eQ: Ql Vl tJ 4 t QJ S 0 0C 0 0 Ql

/Cl S- S-. C/rl M QJ Vl Vl I 0 Vl I0 C QJ T ~ MQl C/l Ql QC QJ 0 Q)

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I 0 'rQ Vl 0 CJO 0 /Cl Ct Cn U O U O Ct. nQ; O U Comments XS-316 3/4 D/P Points for ILRT N N A 0 GT NAH N NA 0 0 S-316 3 4 XS-316 DPPoi D P t

Points for fr ILRT T

. N A GB N

XS-321 Upp. tmos. 1 A Kl2= DC D C Sam le 23 tm 201. 2- E Sample 24 XS-321 3 4 Su Am ~RF N NA N A N AN A N A N A Sam le XS-321 Su r. 0 Sam . Ret .N N A XS-321 Su r. 0 Sam . Ret N 01.2-7 N A JUL XS-321 Su r. 0 2. Sam Ret Ol. 2-7 RF N N ANANA N A XS-328 S~ur. Saniale Ret. AO A

$ 09 XS-328 3/4 Su r. Sam le Ret. 201.2- 'E AO 112 S-328 3 4 S r. m 0 XS-328 3 4 Su r.. Sam l Su 1 N XS-324 Cont. S ra Suction Y N 70 AC D 0 0 0 AI XS-325 12 Cont. S ra Suction Y XS-326 Torus S ra 80-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 I

~r V O S

V QJ QJ Positions S V V S I rC: QJ V S

0 0 S- 0 XXJ 0 rIJ QJ 0 rXJ S- S-

'I

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CA O O U rXJ Comments XS-327 20 Suppr. Vent&Purge N 1 N 201-16 AO A RH 60 A D C C XS-3 7 20 Su r. Vent&Pur e N 1 N 201-17 XS-327 3 N Hakeu & Bleed N 1 N 201.2- 0 It 33 XS-327 3 N Makeu 8 Bleed N 1 N2 201.2-06 X 0 Torus Makeu 1 W 58.1- Manual 0 DCV RMC N 60 01 XS-330 4 Torus Makeu 58. RF 02 XS-332 12 Core S ra Suction Y 1 W 81-01 Manual 0 GT RM XS-334 6 Core S ra Test Ret Y 40-05 XS-335 6 Core S ra Test Ret C C AI XX3M Core pray Suction 1 W 81-22 Manual 0. GT RMC N 90 AC 0 AI XS-337 12 Core S ra Suction Y 1.W 8l.23. .anna.) W XS-333 12 Core S ra Suction 1 W 81-02 Ha X - 0 20 Torus Air Vent&Fill N lJA 201-08 XS-340 20 Torus Air Vent&Fill: N 1' 201-07 X -

XS-342 1

12 Cont.

Cont.

S S

rag Suet>on.

ray Suction 80-02 80-01 Manual Manual 0

0 GT GT RHC N

70. kC 7 AC 0 9.

0 0

0

~

on . pray est > ne 80-43 N A 0 GT N A N H I LC LC LC XS-352 4 Cont.S ra .Te t Line to Wa Dis osal

PLANT Nine e Point Unit PRIMARY CONTAINMENT ISOLATION SYSTEM OATA 1 0 PAGE 13 of 17 Isolation Valves I

QJ 5

rp-r(5 Vl I

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Positions

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O U Comments XS-354 3 Torus Spray W 80-65 N/A 0 N/A RF N NANA NA N A XS-354 3 Torus S ra R XS-354 3 Torus S ra W 80-68 F XS-365 20 eactor Water Cleanu N W 63. RF O.P.

XS-365 20 Relief to Torus N 63 1-~ N A 0 CK NApg 01

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.

, NINE MILE PRIMARY CONTAINMENT P

I T UNIT 1 OLATION SYSTEM DATA Page 15 of.17 ABBREVIATIONS En ineered Safet Function Isolation Valve T e Isolation Si nal Codes N=NO A = Angle Code . Parameter(s) Sensed Set Y=YES B = Butterfly ~or Grou for Isolation Point units BCK = Ball Check Pos i ti on Indi cati on in Control Room BL = Ball A High Steam Flow- < 105 psid CK = Check Main Steam Line D =. Direct DCV = Diaphragm I = Indirect Control Valve High Radiation- < 5 times FCV = Flow Check Valve Main Steam Line normal background.

N = None Others stated in Table FF = Flow Fuse GB = Globe Low Reactor Pressure > 850 psig Fluid GT = Gate Low Low Low > 7 inches RV = Relief A = Air SCV = Stop Check Condenser Vacuum mercury vacuum B = Sodium Pentaborate SV = Solenoid S = Steam High Temperature- < 200F VB = Vacuum Breaker W = Water Main Steam Line N = Nitrogen Tunnel 2 Isolation Valve Power Source Isolation Valve Location A = Air Low Low Reactor > 5 inches AC = AC Water Level Indicator I = Inside Containment DC = DC Scale 0 = Outside Containment H = Hand Others stated in Table High Steam Flow < 19 psid Emergency Cooling Isolation Valve Actuation Mode Isolation Valve Actuator System A = Automatic AO = Air Hi gh Radi ati on- < 25 mr/hr HF = High Flow Emergency Cooling HO = Motor

= Manual H

SO = Solenoid- System Vent OP = Overpressure RF = Reverse Flow RMC = Remote Manual Control Room RM = Remote Manual (Local)

Isolation Valve Positions AI = As Is C = Closed 0 = Open

NINE MILE POINT UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM DATA Page 16 of 17 ABBREVIATIONS (Continued)

Isolation Si nal Codes Continued Code Parameter(s) Sensed Set Grou

'or for Isolation Point uni ts Manual N/A Low-Low Reactor Water Level > 5 inches 71ndicator Scale)

High Area Temperature < 190F for Cleanup System

< 170F for Shutdown Cooling System Low-Low Reactor Water Level > 5 inches YIndicator Scale)

High Drywell Pressure < 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 his approval.

it should be referred to the Purchaser for

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.

Normal Operating Hodes and Isolation Hodes (Continued)

R~es oese 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 line. Niagara Hohawk will install two automatic isolation valves duuring 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 sure that a o i 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