ML18018A381

Submits Formal Clarification of Responses to Safety Review Questions from Containment Sys Branch (480 Series)

ML18018A381
Person / Time
Site:	Harris
Issue date:	10/20/1982
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18018A382	List: ML18018A381 ML18018A385
References
NUDOCS 8210260462
Download: ML18018A381 (15)

Text

REGULATOR NFORMATION DISTRIBUTION EM (RIDS)

ACCESSION NBR:8210260462 DOC ~ DATE: 82/10/20 NOTARIZED:

NO FAOIL:50 400 Shearon Harris Nuclear power Planti Unit lE Carolina 50-401 Shearon Harris Nuclear Power Planti Unit 2i Carolina AUTH BYNAME AUTH0R AFFILIATION MCDUFFIE<M,A, Carolina, Power 5 Light Co, RECIPRNAME RECIPIENT AFFILIATION DENTONiH~ Rs Office of Nuclear Reactor RegulationE Director

SUBJECT:

Submits formal clarification of responses

-to -safety reyiew cluest,ions from Containment Sys Branch (480 series)

~

DISTRIBUTION CODE:

BOOIS:COPIES RECEIVED:LTR 9 ENCL

/

SIZE:

TITLE: Licensing Submittal:

PSAR/FSAR Amdts 8 Related Correspondence NOTES:

DOCKET 05000400 05000401 RECIPIENT ID COPE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL ELD/HDS1 IE/OEP EPDS 35 NRR/DE/AEAB NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB-17 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/OLB 34 NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DSI/ETSB 12 NRR/DSI/P8B 19 N

/RSB 23 4 FIL 04 RM/DDAMI/MI8 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)

LP.DR 03 NSIC 05 COPIES LTTR ENCL 1

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1 RECIPIENT ID CODE/NAME NRR LB3 BC LICITRAg M ~

Ol IE FII E IE/DEP/EPLB 36 NRR/DE/CEB ll NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/QAB 21 NRR/DE/SEB 25 NRR/DHFS/LQB 32 NRR/DHFS/PTRB20 NRR/DS I/AS8 27 NRR/DSI/CSB 09 NRR/DSI/ICSB 16 NRR/DS I/RAB 22 NRR/DST/LGB 33 RGN2 BNL(AMDTS ONLY)

FEMA~REP DIY 39 NRC PDR 02'TIS CO~IES LTTR ENCL 1

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Carolina Power & Light Company g~T ZO ~882 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C.

20555 I

SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.

1 AND 2 DOCKET NOS.

50-400 AND 50-401 CONTAIRKNT SYSTEMS BRANCH SAFETY REVIEW QUESTIONS

Dear Mr. Denton:

Carolina Power

& Light Company (CP&L) hereby submits formal clarification of the Shearon Harris Nuclear Power Plant (SHNPP) responses to the Safety Review Questions from the NRC Containment Systems Branch (480 Series).

This formal clarificat:ion fulfills commitments made in telephone conversations with Mr. E. A. Licitra of your staff and Mr. Larry Cripps, an NRC consultant.

Listed below are the specific clarifications requested by your staff:

480.7 Provide the mass and energy blowdown data for an MSIV failure case.

480. 8 Provide information on penetrations 94C and 95C, similar to that in FSAR Table 6.2.4-1.

480.24 Revise the original response to eliminate the incorrect reference to an attachment l.

480. 29 Provide the basis for the containment fan coolers'erformance curves presented in FSAR Figure 6.2.1-16.

480.34 Provide a copy of relevant portions of WCAP 8587 referenced in the original response.

480.37 Provide additional clarification concerning the inboard isolation valve 2CM-B5-SA, which is normally closed.

480. 38 Provide additional information on penetrations

73A, 73B,

86A, and 86B, similar to that in FSAR Table 6.2.4-1.

8210260462 822020 PDR ADOCN 05000400 PDR 411 Fayetteville Street o P. O. Box 1551 o Raleigh, N. C. 27602

Mr. Harold R. Denton 480.40 Provide a commitment to lock closed the 42-inch purge valves and verify that they are closed every 31 days.

Subcompartment Analysis Provide revised FSAR Tables 6.2.1-12, 15, and 16 to correct typographical errors.

Carolina Power

& Light Company responses to these requested clarifications are attached.

If you have questions on these responses, please contact our staff.

Yours very truly, M. A. McDuffie Senior Vice President Engineering

& Construction JHE/ce (5569C2T5)

Attachment Mr. Prasad Kadambi (NRC)

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

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Daniel F.

Read (CHANGE/ELP)

Mr. Travis Payne (KUDZU)

I P )

t If h

f I'

~

i a~<

1 I

F

MSLB Blowdown 30 percent power full DEB For MSXV Failure Case Gen.

From S09AG04% 01/17/80<

CARD NUMBER SECONDS LBM/SEC BTU/LBM SECONDS LBM/SEC BTU/LBM 301 302 0.

.63700E&04

.44382E&01

.60341E&04

.11895E&04

.34382E&01

.63700E&04

11895E&04

.11929E&04

.54382E&01

.55547E&04

.11955E&04 303 304

.64382E&01

.80000E&01

.51319E&04

.45313E&04

.11977E&04

.74382E&01

.47283E&04

.11996E&04

.12004E&04 NUMBER HOURS LBM/HR BTU/HR HOURS LBM/HR BTU/HR 501 0.

502

.55556E-03

.11466E&08

.99985E&07

.13626E&11

.27778E-03

.10861E&08

.12956E&11

.11953E&11

.83333E-03

.92373E&07

.11064E&11 503

.11111E-02

.85100E&07

.10208E&11

.13889E-02

.78767E&07

.94597E&10 504

.16667E-02

.73720E&07

.88607E&10

.19444E-02

.69655E&07

.83771E&10 505

.22222E-02

.66153E&07

.79595E&10

.25000E-02

.63084E&07

.75930E&10 506

.27778E-02

.60324E&07

.72630E&10

.30556E-02

.57830E&07

.69641E&10 507

.33333E-02

.55528E&07

.66879E&10

.36111E-02

.54207E&07

.65294E&10 508 509 510 511

.38889E-02

.48611E-02

.62500E-02

.76389E-02

.52840E&07

.63652E&10

~.41667E-02

.51452E&07

.61983E&10

.48117E&07

.57970E&10

.55556E-02

.45104E&07

.54340E&10

.42462E&07

.51152E&10

.69444E-02

.40188E&07

.48405E&10

.38233E&07

.46044E&10

.83333E-02

.36553E&07

.44011E&10 512

.97222E-02

.33884E&07

.40782E&10

.11111E-01

.31834E&07

.38299E&10 513 514 515 516 517 518 519 520

.12500E-Ol

.16667E-01

.22222E-01

.27778E-01

.38889E-01

.50000E-01

.61111E-01

.72222E-01

.82603E-01

.13171E&07

.15688E&10

.82603E-01 0.

0.

.30211E&07

.36333E&10

.13889E-01

.28904E&07

.34750E&10

.26917E&07

.32342E&10

.19444E-Ol

.25448E&07

.30561E&10

.24270E&07

.29134E&10

.25000E-01

.23280E&07

.27932E&10

.22421E&07

.26891E&10

.33333E-01

.21007E&07

.25177E&10

.19770E&07

.23678E&10

.44444E-01

.18687E&07

.22366E&10

.17720E&07

.21194E&10

.55556E-01

.16824E&07

.20108E&10

.15972E&07

.19077E&10

.66667E-01

.15180E&07

.18119E&10

.14451E&07

.17237E&10

.77778E-01

.13749E&07

~ 16388E&10 522 100.

0.0 0.0

b

RESPONSE

I480. 8 CONTAINMENT ISOLATION SYSTEM OATA PENETRATIOH DATA VALVE DATA SOLVE POSITION PENETRAYJON DETAJI.

CRC OCC B430 3 le I 56 COttfNT VAQJUN RELIEP-SENSINC B

TYPE h

'IESf ICC ORC 0

B430 31 ~ I 56 CJNfNf VhQJUN RELIEP-SENSINC B

TYPE A

TEST L

A

'T e

R 56 CONftff PRESS St IDE RAJJCE SENSIttC B

TYPE h

TEST B430 31.17 56 QJNfNT VAQJUN RELIKF-SEtiSINC h

TYPE A

TEST SAC OAC 8430

31. 17 56 CONfHf VAQJUN RELIEP-SEtiS INC A

TYPE A

TEST CRC OCC

)JC I

L h

T E

R 56 Gtttfttf PRESS NIJJE RhttCE SeusntC h

TYPE hfESf

480.24 (6.2.l.5)

Provide an'analysis of the effect of the normal contairment purge (NCP)

system, i.e., cn open purge line, cn the minimum containment pressure anaiysis for ECCS performcnce evaluation (reference BTP CSB 6-I ltern B.l.d and BTP CSB 6-.4 Item B.S.c).

Hasoanser..

Rev l per-.ar med for a containment purge system cons st"'ng of tr'a 4

8-inch kismet er 'nes and the fo Llauin An analysis uas performed for Shearan Harr'.s Units '152 (C~L) r to determ'ne the reduct'on in can.a'nment pressure resultin" from containment purg'ng during a

LOCA for ECCS backpr essure deter minatian.

This analysis eas based -upon th'e containnent candit" ons defined in the lim'+ n" CQL Large. Break LOCA F5AR analysis case (OFCLG breaks CD=0.4) obtained using the 1978

-va

~ uation Model.; A'ontainmen. 'olation signal is received in.hat analysis a.

~ 1..03 seconds af.er inception of the LOCA Add ng 1

~ 5 seccnds for s'"nal delays a calcula 'n 's can servat=ve assump.ions:

.5 second isal3t an Our ng fallotting t'h e LOCAr no valve. clasure time is assumed.

the 6.03 second per iad immediately cred't is taken far the r educt'on ef feet'~

lorrr a

the process a.

clos I

rea which occurs rrrhile the valve is in 1

inq fr't'na' esistan ll ce assaciated sith due.

entrance anc ex L cssesr fi ter sr cucteork bends and sk'n 4f g&% ~ A I

w ~

~

C nai naz

')een c=nsidered.

fa I

ca as

.davsn e f fec. s are considered.

No oner t ~ a 's considered.

5teady state f'o~ aut pur",e syste~

ducts

. s established

'mmed'tely at ta e LnCi

+ '4 e the

480. 2'f-g A

m xture o f steam and air will be exhausted from the conta'ment tnrough tne pur"e lines durin

+h e o."a secon 's 4

'4 +

1 41

'~o aiion valves are assumed to remain open

~

Th~

effect of the composition of the gas be'ng exhausted on conta'nment pressure has been bounded by itiv t' h

ves iga zng the tao extreme cases'ir alone and

-team alo M'th ne ith" n several

~econds of the inca pt on o f the LOCAL c onta nment pressure wi 1 wilnave ncr eased

'to

.he po'nt that cf itical flow will occur 'n the purge lines.

To bound the calcu'ated gas m 'x tur e exhausted through the pur"e 1'ests the critical flow rates or steam and air were calcu'ated during the first 6

3 0

seconds of the CO=0.4 GHCLG break transient.,

Using these.

f'ow ratesr cr itica1 floe was ther. conservat'ely assumed to be 'n e erect from t'm" "ero

. Equation 4.1P.

' f'r in e erence was mp'oyed to c

1 "ul-.e the critical flow rate of air throu gh the C".L purge 1'nes.

Figure 94 of Ref erenc~

> was applied to compute the cri.ical flow rate o

steam hrough tne purge

'~nes.

The total mass released dur 'ng the 6~0'3 seconds tnat the valves are presu'med open is calculated as s;earn less than G.Q5 psi in either case.

ibm air or 237 ibm steam.

The 'mpac.

on pressur e

at, 6.03 seconds resulting from this co nt axnmen t loss of BJ.

~

of The effect cf a

containment prcssure reduction o f th' magnitude on the cal=u'xed pe ak clad

.emperature (PCT) is less than t deg-<F 0 Qc T fear

+

~

t cl

) I l

Q C

C

=Q c

se is

>1~l d

~

F a

an; o

Ther=forest

-.".ere la no F" penalty and margin wktn r

"e"

~QrF 2~3 4i PCT reauir ements would rema'.

This

~ ~

y e "e acr~ red in detail c

w ooo-

~

~

V 0

in S a feguard s

"=n "incer '-

-F ~%-PIC 1.

~".aoiror '. n-r Tne Dyn amies

=nd Thermo dynamics o '

~ ~s s'~le lu'

'owx Volume t r p ~ ~~

e

$ ~ 7 '~1" 5 te am Tab le sr

l,

~

4

Res onse 480.29 (Clarification)

Documentation of the basis of the containment fan coolers'erformance curves which appear on FSAR Figure 6.2. 1-16 is provided in the attached letter from American Air Filter dated August 25, 1982.

A b A.merican AirII:iiter Ah ALLIS.CHALQShS COlltANY 21$ CENTRALAYENVQ LOV IS VILLEIKEIITVCKY40280 August 25 ~ 1982 QVZD, ZS Ebssco Services>

Xnc Two Vorld Trade Center, 81st Floor Nev Yor'R,. HY 10048 Rtt!.Y TOI CLEAN Alh OIYISIOH t.o. SOX 2S2SO LOUISVILLE,KYA0222 TELEX: 2O42Sl OI'ERATOh: (S02) SSY4%1 To CALLWIIITEh OVIECT TELEPHONE: (502) SSTA~

httention:

Mr. John BielavsM.

Reference:

Ebasco P,0. NY~35081 Carolina Pover 5.Light Company Shearon Harris Nuclear Pover Plant Containment Fan Cooling Units hAF Pro ect 25-1381 Gentlemen:

Confirming our telecon of 24 August, 1982, the AAF containment fan cooler design and performance data submitted for the referenced project is in strict accordance vith those tcchnical procedures and qualification tests reported by hAF to thc USNRC in Topical Report AAF-TR-7101 "Design and Testing of Fan Cooler-Filter Systems for Nuclear hpplications", dated 20 February 1972.

AAF originally developed a computer program predicting heat transfer under nuclear pover plant environmental conditions using recognised teer n1csl theory.

hAF performed prototype testing on cooling coils on four occasions to verify thc computer program being utilized for equipment design The tests substantiated the theory and computer programs being employed.

Details of the computer program, the prototype testing, and thc correla-tion are described in the topical report~

hAF appeared before thc USNRC to ansver q)iestions on this entire matter shortly after the submission of thc topical report~

This meeting resulted in Supplement Ão, 1 to thc topical report vhich vas issued on 3 August, 1972 Better Airls Our Buslnsss

Zbasco Services, Inc 8r, John Iiaiavski Page Two 25 Au ust 1982 The USNRC letter of acceptance of this topica1 report dated 10 November 1972 is attac 72 i attached for your reference,

?lease 1st us ~or if you require any additional information.

Sincerely, AMERICAN A PI R COMPARE~

a Di isio of lis-Chalmers Corporation Don E. Engleman Product Hanager Nuclear Environmental Systems,.

DER/sm attachment re A ~

al E>> hler Ri>olney%