ML18191A086

General Electric Provided 100 Copies of Report. Suppression Pool Temperature Response to a Safety/Relief Valve Discharge Through a Ramshead in Mark I & II Containments, NEDO23689, May 1978

ML18191A086
Person / Time
Site:	Nine Mile Point, Columbia, Limerick, LaSalle, Zimmer, Shoreham, Bailly  File:Long Island Lighting Company icon.png (NPF-011, NPF-018, NPF-021, NPF-039, NPF-069, NPF-082, NPF-085)
Issue date:	08/04/1978
From:	Sobon L General Electric Co
To:	Stolz J Office of Nuclear Reactor Regulation
References
MFN-322-78, NEDO23689
Download: ML18191A086 (4)

Text

I=;EGULATORY INFORMATION DI'RIBUTIGN SYSTEM (RIDS) 0 IS Ri BUT ION FOR INCOMING MATERIAL TOPREP

.=,EC: STOLZ J F ORG: SGBGN L J DOCDATE: 08/04/78 NRC CiEhf ELEC DATE RCVD: 0'=:f 16/ 7 LETTER NGTARI"ED: NG COPIES PEl- Ei VEDl

='OCTYPE:

.= I IBJECT: LTP, 1 ENCL 10

=O.'WARDING GE TOPICAL REPT EhJTITLED: "- UPPFES= ION POOL TEMPERATURE RESPONSE

G A '- AFETY/REL1EF VALVF D I'- CHARGE THROUGH A RAN - I i - AD IN NAPl' AND CONTA IMENTS? "

NEO: 36'r ~ i MAY? 1978.

.

REVIEWER INITIAL: X JN DISTRIBUTOR INITIAL:

+ <-"'" >++ <<+'T."." +': > 4'<<DISTR I BUT ION GF TH S MATERIAL I A.'GLLOII'- + +<<++++"

'l l T- '-, .

STANDARDI Eu PLANT TOPICAL R - TS 5 CGRRES - GNDENC - fsE NARK I 8. II CGNTA INNENT (DISTRIBUTICltd CODE TOOER)

INTERNAL: REG FILE++W/0 ENCL CENTRAL FILE++W/2 ENCL 50-322 FILFP+LTR ONLY 50-.52 FILE++LTF: ONLY 0-353 FILE+e-.LTR ONLY 50 358 FILE~<<LTR GhJLY 50-367 FILE++LTR ONLY E ~ FILE~+LTR GNLY 50-.74 FILETS:-<<LTR ONLY 50-3'?8 KLE<+LTR GNLY 50--410 FILE'.~LTR ONLY R~'DR++W/ENCL STRUCTURAL EhJG BR<<+W/ENCL CGNTAINMENT . YSTEM 4'+ll/ENCL(;I)

AD FOR ENG+>W/ENCL(>) C QNDERSON++W/ENCL I PELTIER<<<<W/ENCL M D LYNCH~<<W/ENCL J SNELL<<<<W/ENCL A BGURNIA<<<<W/ENCL W I:ANENT<<.W/ENCL S N I NEP..-"4 WfENCL D .T.,I BEETT =,<<'l W/ENCL DEPUTY DIR DPN++LTR ONLY D VASSALLG~.<<LTR ONLY LWR42 Cl IIEF<<-lb'iiMC, LWRC3 CHIEF++LTR ONLY LWRC1 Cl-I IEF++LTR ClNLY AD FraR PLANT YSTEMS<<~K~Y M RUSI-IBROOK';-<<LTR Clh>LY W PIK-+<<LTR ClNLY LWRÃ4 CIIIEF~<<LTP. ONLY ENG1NEER ING Br(<<+Wf'4 ENCL PLANT Y'- TEI'I'- B <+W/6 ENCL G LEARN>+W/ENCL F SCHRGEDER<<<<W/ENCL DIPECTOR DClR<<<<W/ENCL AD FOP SY= lk PRCI !wwW/EhICL C GRIMES<<~W/ENCL D ZIENANN<<<<W/ -NCL AD FClR ENGR:-. Pl"iG l~~:-W/EhJCL MECI.I ENG BR..<<W/F;NCL P

p p&L E>'ERNAL: LPDP.'S PORT JEFFER ClN-PDR<<<<W/ENCI f GTTSTGWN? PA-PDR r'+W/Et JCL BATAV I A, Old-",- DR'.~~W/- NCL CI-'IE-"TERTGN. IN- PDR~'<<W/ENCL GGLESB Y, IL-,-DR-~~W/ENCL R I CI-ILAtJD. ! JA-PDF;<<~W/ ENCL G WEGG NY-PDR.:+W/ENCL TEI~A++ WfEhJCL N.- I C-:l .~W/ENCL Pll 2 ACRS CAT <<~-:W/16 ENCL

'iSTR I BUT IClN: L-Tr'P E>(CL :lNTROL hJBR: 7'~2 '0027 '

~

~

0 E f~ E R P L, "'-" E LE C 7 R l C N UCLEAR ENERG Y PROJECTS DIM. iSION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFN-322-78

'MC 681, (408) 925-3495 REGULATORV Ant'.yr T qI ~ I 0><

U. S. Nuclear Regulatory Commission Division of Project Management 0 fice of Nuclear Reactor Regulation Washington, D. C. 20555 1

Attention: Mr. John F. Stol.z, Chief Light Water Reactors Branch No. 1

SUBJECT:

GENERAL ELECTRIC REPORT, "SUPPRESSION POOL TEMPERATURE RESPONSE TO A SAFETY/RELIEF VALVE DISCHARGE THROUGH A RAMSHEAD IN MARF,. I AND II CONTAINMENTS," NEDOZ3689, MAY, 1978 1

Reference:

Letter with Report, "General Electric Report, 'Suppression Pool Temperatur~ Response to a Safety/Relief Valve Dis-charge through g. Ramshead in Mark I and II da ".ed March, 1978," to J. F. Stolz, from Containments,'EDCZ3689-P, L. J. Sobon, da'ted March 31,, 1978.

One hundred (100) copies of the subject report are being provided by General Electric for the Mark I and Mark II Owners Groups for your review as part of Mark I Task 7.5 and Mark II Task B.6.

This report is the non-proprietary version of NEDC23689-P which described the analytical models used to predict the temperature distribution in the Mark I and II pressure suppression pools folio~",'ng S/RV discharge through a ramshead device, and was submitted to you in March 1978 (Reference).

Sincerely L. J. Sobon, Manager BWR Containment Licensing Containment Improvement Programs 7 2='0027 LJS:mm/949 Enclosures 100 cc: C. J. Anderson (NRC)

H. C. Brinkmann (Mark II Owners Group)

H. Chau (Mark II Owners Group)

L. S. Gifford (GE, Bethesda)

C. I. Grimes (NRC) o~

I, A. Peltier 6" ID~"

R. L. Tedesco (NRC)

(NRC) l'

ov j~v fW REGULATORY INFORMATION l3XSTRIBUTION SYSTEI'I (RIDS)

I D XSTR BU'I ION FQR INCOMING MATERIAL TOPREP REC: STOLZ J F GRG: SOBGN L J DGCDATE: 07/28/78 NI.C GEN ELEC DATE RCVD: 08/07f78 DOCTYPE'ETTEli iiJ I'$ i I

NO i AR ZE13: YES COPIES RECEIVED

)I LTR 1 ENCL 70

,"'EOUE TXhlG WITHHOLDING PURSUANT TQ 2. 790 INFO... FQRWARDING PROPRIETARY IhlFO

.:aNSISrIhIG QF HARK II CONTAINMENT PROGRAM REPT "EVALUATION GF

,='ID-~TliUCTURE INTERACTION OiV BNR MARK I 1 CONTAINMENT STRLCTURES, "

."~I DE-21936-P, JULY 197'... W/ATT P, GP AFFIDAVIT REVIEWER INI'I I AL: X JM DISTRIBUTOR INITIAL:

-:~->>>>.e>>>>>>>>>>~~>>~>>>>>> DISTRISUTIGN OF THIS MATERIAL IS AS FOLLOWS ~~~~>>~~>>~~~~~~>>~~~

PROPRI TARY TOPICAL RPT RE MARK IX CGNTAINM-NT

<DISTRIBUTIGhI CODE PT02)

INTERNAL: CENTRAL I. XLE>>+W/2 EhlCL Wl +3 50-322 FILE++LTR ONLY 50-352 FILE>>~LTR ONLY 50-353 FILE++LTli ONLY 50-358 I ILE++LTR GhlLY 50- :>> .+>> ONLY 50-374 FILE>+LTR ONLY NRI

-397 FILE4+LTR 50-4'10 FXLE<+LTR OhlLY ENG BR~~W/2

~ gp KECK ]5'TRUCTURAL CONTAINMENT SYSTEMS~~VJ/7 ENCL AD FGR CNG~~W/2 ENCLMM-1'l C ANDERSON+~W/ENCL%V/0 I PELTIER++W/ENCL~ t8 M D LYNCH~~N/ENCL~/I J SNELL+<N/ENCL'!9 A BOURNIA++W/ENCL~( Qr W KANE++W/ENCL~+

S MIIIER~~N/ENCL W/3 D TIBBETTS++llfEhlCL&4,l DEPUTY DIR DPM++LTR ONLY D VASSALLG++LTR ONLY LNR52 CHIEF++LTR ONLY LWR03 CHIEF>>~LTR QllLY'D LWRS1 CHXEF++LTR ONLY FOR, PLANT SYSTEMS~~LTR ONLY M RUSHBROQK+~LTR ONLY W PIKE4+LTR ONLY LWR44 CIIIEF~~LTR ONLY EXTERNAL: LPDR S PORT JEFFERSON-PDR++LTR ONLY POTTSTQWN>PA-PDR~+LTR ONLY BATAVIA GH-PDR++LTR ONLY CHESTERTON> XN-PDR'~~LTR ONLY GGLESBY> IL-PDR++LTR ONLY RICHLAND WA-PDR~>>L'TR ONLY OSWEGO> NY-PDR++LTR ONLY TERA~~LTR ONLY NSICHLTR ONLY L DREHER W/AFF++LTR ONLY ACR GAT ~~I)/16 ENCL WQQ, 30 DISTRIBUTION: 'TR 65 ENCL 37 CONTROL NBA: 782160053 3 I ZE: 1P+4P~ 96P

->>>>ib>>%>>il->>>>wi%8b>A'4 P% iHH&%w w %%%%>>>>>>%%+%+%% THE F ND  %%%>>> 3F% N %%%+4-->>%4 %>>>>>>>>>>>>>>>>>%++

ELECTRIC l'ENERAL ML NUCLEAR ENERGY PROJECTS DIVISION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 NFN- 316- 78 NC 681, (408) 925-3495 July 28, 1978 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. John F. Stolz, Chief Light Water Reactor Branch No. 1 Divison of Project Management Gentl emen:

SUBJECT:

MARK II CONTAINMENT PROGRAM "REPORT, "EVALUATION OF FLUID-STRUCTURE INTERACTION EFFECTS ON BWR MARK II CONTAINMENT STRUCTURES," NEDE-21936-P, JULY 1978 Seventy (70) copies of the subject report (NEDE-21936-P) are being provided by General Electric Company on behalf of the Mark II Owners Group for your review as part of the Nark II Containment Supporting Program, Task C.8. This report describes a study to establish whether fluid-structure interaction (FSI) effects are present in Mark II containment structure responses to hydrodynamic loads.

The enclosed report contains information which the General Electric Company customarily maintains in confidence and withholds from public disclosure. The information has been handled and classified proprietary by General Electric as indicated in the attached proprietary affidavit, and the request is hereby made that NEDE-21936-P and the attached affidavit be withheld from public disclosure in accordance with lOCFR2.790.

A non-proprietary version of this report is being prepared for submittal in August 1978.

Si cer 1 L. J. Sobon, Nanag r BWR Containment Licensing Containment Improvement Programs 782160053 LJS:mh/1661 Enclosure (70) cc: C. J. Anderson (NRC)

H. C. Brinkmann (Mark II Owners Group)

H. Chau (Nark II Owners Group)

L. S. Gifford (GE, Bethesda)

I. A. Peltier (NRC)

R. L. Tedesco (NRC)

File 3.2.7C