ML18018B466

Forwards Supplemental Info to 831014 Response to Draft SER Open Item 71 Re Containment Isolation sys.Marked-up FSAR Pages Encl.Info Will Be Incorporated Into Future FSAR Rev

ML18018B466
Person / Time
Site:	Harris
Issue date:	11/08/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8311150263
Download: ML18018B466 (7)

Text

REGULATORY ORMATION DISTRIBUTION SY (RIDS)

ACCESSION NBR; 8311150263 OOC ~ DATE: 83/11/08 NOTARI'ZKD: NO FACIL:50 400 Shear on Harr is Nuclear Power Pl antr Unit ii Carol ina

'50<<401'Shear on Harris Nuclear Power Planti Unit 2i Carolina AUTHe NAME AUTHOR AFFILIATION MCOUFFIErMeA.

'Carolina:Power 8 Light Co.,

RECIP ~ NAME RECIPIENT AFFILIATION DENTONiH ~ Re Office of'uclear Reactor Regulationr Director

SUBJECT:

Forwards supplemental info to 831014 response to draft SER Open Item 71 re containment isolation,sys.Marked up FSAR pages encl, Info will be incorporated into future FSAR rev ~

DISTRIBUTION CODE:

8001S COPIES RECEIVEDeLTR "ENCL J'IZE;,

/.

TITLE: Licensing Submittal!

PSAR/FSAR Amdts 3, Related Correspondence NOTES:

DOCKET 05000400 05000401 RECIP IENT IO CODE/NAME NRR/DL/ADL NRR L83~ LA INTERNAL: ELD/HDS1 IE/DEPER/KPB 36 IK/DEQA/QAB 21 NRR/DE/CEB ii NRR/OE/EQB 13 NRR/DE/MEB 18 NRR/OE/SAB 24 NRR/OHFS/HFE840 NRA/OHFS/PSRB NRR/OS I/AEB 26 NRR/DS I/CP8 10 NRR/OS I/ICSB 16 NRR/DS I/PSB 19 NRA/OS I/RSB 23~

RGN2 EXTERNALS ACRS DMS/DSS (AMDTS)

LPDR 03 NSIC 05 RECOPIES LTTR ENCL 0

1 0

1 0

3 3

1 1

1 1

2 2

1 1

1 1

iv 1

1 1

1 1

1 1

1 1

1 1

3 6

6 1

1 1

1 1

REC IP IENT ID CODE/NAME NRR L83 BC BUCKLEYiB 01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/OK/MTEB 17 NRR/OK'/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/OSI/METB 12" S /RAB 22 RM/DDAMI/MI8 BNL(AMDTS ONLY)

FEMA REP DIV 39 NRC POR 02'TIS iCOPIES LTTR ENCL 1

0 1

1 1

1 1.

1 0

1 1

2 2

1 1

1 1

1=

1 0

1 1

1 1

1 1

1 1

1 0

1 1

1 1

1 1

1 1

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 53 ENCL 46

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0 @ME, Carolina Power & Light Company November 8, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~ 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT OPEN ITEMS CONTAINMENT SYSTEMS BRANCH

Dear Mr. Denton:

Carolina Power

& Light Company hereby transmits one original and forty copies of supplemental information in support of our response to the Shearon Harris Nuclear Power Plant (SHNPP) Draft Safety Evaluation Report Open Item 71.

This information consists of marked-up Final Safety Analysis Report (FSAR) pages.

They incorporate information submitted in our letter dated October 14, 1983 (LAP-83-485), and reflect how the SHNPP FSAR will be revised in a future amendment.

If you have any questions regarding this matter, please contact a

member of our staff.

Yours very truly, 8aillS0aSS SSlioa PDR ADOCK 05000400 E

PDR M. A. McDuffie Senior Vice President Nuclear Generation PSA/lcv (8452PSA)

Attachment Cct Mr. Yum-Seng Huang (NRC-CSB)

Mr. BE C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F.

Read (CHANGE/ELP)

Mr. R. P. Gruber (NCUC)

Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 411 Fayetteville Street P. O. Box 1551

~ Raleigh, N, C. 27602

M I I PI I I

.'Ill,~

Is I

1 V

TASLE 624-1 CONTAINMENT ISOLATION SYSTEM DATA F'EIIETRATIDH DATA PCS<K TRAIT)<t OC TAIL e

gee AV VALVE DATA

~'E POSIT <0<t e"

~vT cf h

s<OTK uc c<<<c

-(rg Qs<

s~

1<<

ss sa.

s<<< vsa s TC 810 5

)

YKS NO RIIR SOCTIGti FROH N<sT ILC R500 VSOO VSOI RF IOO CA 12 CA SA IIO HO RlI RH H

H IS 15 C

0 0

AI AI YES YES YE<<

NO IR) ti<s it<a NO liO 2,)

~W~e ~

~svss uw A(/

'I J(

savu asvss $3$

uvre 808 5

YES NO SAFETY IIUECFI<stt-NICN HEAD T<

coLD 1K' 44b v099

~We VI)

V23 V29 VTS ViQ s)88 V30 V505 V506 I'5 119

'I 5

)66 3

CK CK CK CL CI.

CL CL CA ra SA SA SA H

H N

H HO HO H

N H

N A

A RN RN Io 10 C

C C

TL Tl, TL I.C C

C C

C C

TL TL TL LC C

C t) 0 0

TL TL TL LC 0

0 Al AI C

C C

TL TL TL LC C

C

) r'.S YF.S YES YES YAKS YES YKS

<XS YES TRS tio t<O tio Nn NO Nn

YcS, Nn NO tt<)

NO NO tto NO

YrS, Ye<<s

<CC

<SCC n

'I' AIN~< ~

J as vast uvs>>

SAFETY INJECTION L<<)t I<TAO To NOI LECS VS I0 V5 II VSA7 5) 55 I

CK CK r~

SA SA Ho 15 t) 0 0

Al YES YKS YKS NO NO tin tto Yrs cs 19 SPARE

<ac

<sac 41 IT<

u vsa uw

)ZCj 5

AI YES NO SAFETY INJECT Ioit-IIICN NEAls To Nol ILrs 943I Ha V4zq V86 V90 V96 Vf)9 V95-VSOO 82 36 160 81 35 139 I

CK CK CF CL CI.

CI.

SA SA SA H

H H

tlo If N

H Rll 10 C

C C

TL TI.

Tl.

C r.

C C

Tt.

Tl.

TL C

0 0

0 TL TI~

TL 0

C C

C YL TI.

Yl.

c YF.S YES YES I'ES YKS YES YES tin NO NO tio tiO lin tK.

tits NO tio tlO tiO ttas

TABLE 6211-1 CONTAINMENT iSOlATION SYSTEM DATA PENETAATIDII DATA RfSsf IAAF MICA a4 4+

s!S WV NLVE DATA SOS VK IOrrSIKsSS

/ ~4

~4 P',f PP /r'V ssoT SSC CrrS sc 11 tss

~ssis ss rss

~~r rV,oJg 4 sss 5'

YKS NO 7

SAFETY INECTION-NIGN IIEAO I NOT IXCS g434 V4V 943Z V39 V45 VS I V58 944 V501 118 28 131 117 27 130 I

CK CK CK CI CL CL CA SA Sh SA N

H H

IIO H

.'I H

IOI 10 C

C C

TL TL TL C

C C

Il.

Tl.

C st 0

0 Tl.

Tl.

YL AI C

C C

TL Yl.

Tl.

C YES

'SKS YKS YK5 YES YES

'I'KS 1,')

~ 's 8) dS NO SO tIO NO Nis IIO

~C O vsS Ss rsS qa ssssss 808 5

il YES NO SAFETY ItII ECTION IIICN NEAO TO COIN IXCS V63 V69 VIS V62 VG8 V74 V)02 151 18 81 ISOll 80 I

CK CK CK GL Ct CI.

CA SA SA SA tt H

H W

N N

H RN 10 C

C C

TL TL TL C

C C

C TL TL TL 0

0 0

TL Tl.

Tt.

0 Al C

C C

Tl.

TL Tl.

C ITS YES YKS YKS YKS lKS IIS 8)

SO SO rVss SO no NO NO

In

'IO ssvss ssrss SCC 'CC 1C 1C g

nn ScC OssC N'ILO-L Cs ~S 050 050 56

~r Se It YES NO N

YKS NO CnttfhlIRIEIIF Sl'RAY COIIYAIIOIEIIT S I'RA'I V27 V21 VSI V43 A

CK rA CK Ch SA Hn I I 10 10 hl AI YES YES YT.S YES SO IIO NO NO NO 2, 3 2,

3

.Il" E w

~siss itsJ I~l 8

047 u

nn no SERVICE NATI:R TO Fhn C(ssIILR An-3 846 RF IRS RN IS 0

0 AI 0

YES NO

~ C<<~(10~ tO g+ q~

See SeCAIOu

@2~~ m.g Z

7ABLK 6.2.(I-I CONTAINMENT ISOLATION SYSTEM DATA l

PEIIETRAT(044 BATA VALVE DA7A P(ICIAI(DH OK(AIL

/ p' e

(.

9 c)

~T g+

v e

e" SPARE O'CVK POSITION SPARE ccnn ff'cv((c M

MO 5l

((0 COI<POIIEIIT C(gt.lt(0 MATER TO RCP VI21 VI)0 CK Ch SA IIO RH 10 Al YES YES YCS YcS CN

~C OAC CCYI<

SC M

t(O t(O C(X<PO<(EI(T COOLl((C MATLR B((M RCP C(NPO< (Et(T Con LII(0 MATER TO REACTOR CA I!At(P 0 RAI TAI(K At(O KXCESS IET-II(h(tl I(EAT FXCI(ht(CLRS VS I V188 V<83 VI22 V 1 82 I

CK Ch CA 2

Ch CA SA HO IQ)

NO IIO Rtl RN RN RN IO 10 IO IO hl Al Al Al YES YES YES YES YES Yes Yes Yes t(0 Hn YCS 5

Mn Mn M

IIO

'(0 CO(ll'0(K((t C(I(>LIIIO

'MhlER IR(h(

RCI'IIKRNA<.

RARRIKRS VSO V191 V 190 CK Ch Ch SA HO NO Rtl RN IO 10 C

0 0

Al hl I'KS YES YES

'r~

(l (r Y~

Ym

+c vl(c fj ac cape M

t(n YES OKNII(

MAIER

.0 I'Rl VS2S OS2$

SA AO RI(

p0 PO t(a t(0 YES YES YES YES