ML19290B966

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Forwards Program Ltr Explaining Liaison Work W/Jaeri on Mark II Containment Research,Two Jaeri Repts W/Viewgraphs from Recent Meeting W/Tong & NRC Memo Requesting Establishment of Liaison W/Jaeri & Mark II Containment Research Monitoring
ML19290B966
Person / Time
Issue date: 07/26/1979
From: Fabic S
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Mccauley E
LAWRENCE LIVERMORE NATIONAL LABORATORY
References
REF-GTECI-A-08, REF-GTECI-CO, TASK-A-08, TASK-A-8, TASK-OR NUDOCS 8001080073
Download: ML19290B966 (50)
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LST CY bec w/o enc 1s: [ Hanauer F.'Schroeder Dr. E. W. McCauley R. P. Denise Nuclear Test Engineering Division W. Butler Lawrence Livennore Laboratory J. Kudrick P.O. Box 808 C. Anderson Livennore, California 94550 bec w/ enc 1s:

R. Cudlin

Dear Ed:

Please find enclosed:

1) A copy of the program letter that is now being officially processed and which explain.' the nature of your liaison work with JAERI on their MARK II containment research. Notice that $69,000 was added by this program letter, making a total of $119,000 for the combined GKSS and JAERI work.
2) Two JAERI reports and a copy of viewgraphs presented at a recent meeting attended by Dr. Tong. All this material pertains to JAERI's MARK II containment *. team venting tests and all is marked proprietary.

Please arrange for translation of the two JAERI reports, making sure that their proprietary status is not jeopardized. Proprietary material must be clearly identified as such and could only be disseminated to NRC.

3) A copy of NRR's memo requesting establishment of liaison with JAERI and monitoring of MARK II containment research.

Sincerely.

Original Signed By S.8 M f:, Chief t

Analysis Development Branch Division of Reactor Safety Research l733 2Ob

Enclosures:

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,\\u ny AGENDA FOR MARK II NRC fiEETIflG JULY 24, 1979 BETHESDA, tid.

9:00 AM - 12:00 N00N o

INTRODUCTION P. HEDGEC0CK e

LICENSING BACKGROUflD L. SOBON o

PROGRAM DEFIf1ITION A. SMITH o

REMAINING PROGRAfi TASK A. SMITH ACTIVITIES o

POSITION STATEMENTS REGARDING NRC CRITERIA o

GEf4ERIC L. Sosota o

PLANT UNIQUE APPROACHES MK II REPRESEf1TATIVES 1:00 PM - 5:00 PM o

CLOSURE PROGRAfi W. DAVIS o

ACTIVITIES o

DOCUMENTATI0f1 o

SCllEDULES 1733 290 ARS/ou 7/79

r AGENDA FOR MARK II NRC f1EETING JULY 25, 1979 BETHESDA, MD.

9:00 AM - 12:00 N00N e

INDIVIDUAL PROGRAM TASK STATUS e

TASK A.17 CONDENSATION GE OSCILLATION TESTING o

REVIEW 0F MK II SUBMITTALS MK II REPRESENTATIVES e

TASK C.9 WORLD TEST GE MONITORIN3 1:00 PM - 4':00 PM e

NRC REVIEW STATUS & POSITIONS NRC PERSONNEL e

SRSS o

FUi1CTIONAL CAPABILITY o

IMPROVED CHUG LOAD DEFIlllTION (TASK A.16) o MULTIVEllT TEST PROGRAM PHASES I & II (TASK A.11) o SUGGESTED ALTERi1ATIVES FOR:

o WALL & FLOOR VEi1T CLEARING LOADS o

ASYMMETRIC LOCA LOADS e

LOAD CASE NO. 10 l733 pgj ARS/ou 7/79

liARK II CONTAINtiENT PROGRAM TASK STRUCTURE SUtiMARY TOTAL NUMBER OF TASKS

101 MARK II PLANT APPLICATION

% OF TOTAL TASKS LEAD PLANT SER 8

NON-LEAD PLANT 32 COMBINATION OF PLANT CATEGORIES 34 CONFIRMATORY 12 INFORMATIONAL 14 TOTAL 100%

JULY 1979 COMPLETION STATUS:

(BASED ON COST !lEIGHTING) e OVERALL PROGRAM 70%

i733 292 ARS/DH 7/79

MK II CONTAINMENT PROGRAM EFFORT C0t1PLETE CCNDENSATION OSCILLATION EFFORT IN PROCESS TESTS A.17 4T TESTS BOUNDING IMPROVED CHUG A.1 LOADS LOAD DEFINITION z$

JUSTIFICATION A.16 ^

C.7 g$

CHUGGING INCIDENT

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WALL U$

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P AR AT',E T R I C MULTIVENT TESTS TESTS A.7 A.ll IMPACT DATA I

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MONTICELLO FSI WALL g o, j

B3 "T"- QUENCHER PROGRAM THERMAL MIXING MODEL B.6 DFFR EVALUATION N

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MK II CONTAINMENT SUBf1ERGED STRUCTURES PROGRAM ANALYTICAL MODELS MK II UN!QUE APPLICATIONS MEMO DFFR C.1 TESTING G

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SUBMERGED STRUCTURES PROGRAM LOCA/RAMSHEAD ANALYTICAL AIR BUBBLE MODELS A.5 NED0/NEDE-21471 APPLIC. MEMO, 217 30 CH. 2 NRC SUBMERGED STRUCTURES CRITERIA LOCA/RAMSHEAD C.15 LTR. REPT.

WATER JET I

A.5 NED0/NEDE-21472 RING VORTEX APPLIC. MEMO,21730 CH.3 MODEL APPROACH DFFR A.S.5 LTR. REPT.

C.1 APP. MEMO REPT.

QUENCHER WATER JET PLANT UNIQUE QUENCHER AIR BUBBLE A.5 NED0/NED E-214 71 SUPP.1 APPLIC. MEMO,217 30 CH.4 LOCA STEAM

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CONDENSATION u

PLANT UNIQUE EFFORT COMPLETE EFFORT IN PROCESS ARS 7/79

SUBMERGED STRUCTURES PROGRAM EFFORT COMPLETE EFFORT IN PROCESS 1/4 SCALE TESTS DFFR TESTING C.1 NED0/NEDE 23817 O

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& FUNCTIONAL CAPABILITY NRC SUMBERGED PLANT DFFR C.13 STRUCTURES CRITERI A EVALUATION C.1 BY DAR C.15 NRC QUESTIONS U

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lh NEWMARK/ KENNEDY WORLD TEST SRSS CRITERIA MONITORING SUPPLEMENT C.9 C.5.3 N

LN MK II SUPPORTING La ARS PROGRAM REPORT na 7/79 C.0 so oo

ilA.,K 11 GEiltRIC PRCGRAM SCHEDULE LOCA RELATED ACTIVITIES 1979 1980 1981 1

A5 MODEL DATA EVALUATION N

V 70% C0tiPLETE A.5.5 (CHU) RING VORTEX fiODEL N

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60% C0fiPLETE A.11 SUBSCALE MULTIVENT TESTING v

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V 70% COMPLETE A.13 EXTENSION-LATERAL LOADS ANAL. b A

V 30% COMPLETE A.16 IMPROVED CHUG LOADS v

V V-V 75% COMPLETE A.17 CONDENSATION OSCILLATION TESTS v V

V V-V-V i22% C0iiPLETE S/RV RELATED ACTIVITIES 1979 1980 1981 B5 CAORSO QUENCHER TESTS v

Y-Y Y

-V 90% COMPLETE B.14 QUENCHER EMPIRICAL fiODEL UPDATEv V

V V 40% COMPLETE fIISCELLAt1E0llS ACTIVITIES o

APPROVED TASKS A5 QUENCHER AIR BUBBLE

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85% COMPLETE C.5.3 N/K SRSS SUPPLEMENT d

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90%

COMPLETE v

C.6 NRC ROUND 2 QUESTIONS N

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C.9 WORLD TEST fiONITORING v-Y Y

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C.12 NRC QUESTIONS 20.43/20.59 vY V

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1978 1979 1980 1981 "oo ESTIMATED COMPLETION DATE ARS 7 /79

MARK 11 CONIAINMEN1 - SUPPORTING PROGRAM LOCA-RELAT[D 1 ASKS TASK TARGEi DAIE LFAD PLANT SER/

Nt'M3ER ACTIVITY ACTIVITY TYPE COMPIE!!Oy DOCLE NTATION DOC /5UBH INTER!tED PLANT A.I "4T" TEST PROGRAM Phase 1 Test Report Completed NED0/NEDE 13442-P-01 5/76 - 5/76 LP SER/IP Phase ! Appl Memo Completed Application Memo 6/76 - 6/76 LP SER/IP Phase II & 111 Test Rpt Completed NID0/NLDE 13468-P 12/76 - 1/17 LP SER/IP Application Memorandum Com;ileted NLD0/NLUE 23678-P 1/77 - 2/77 LP SER/IP

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A.2 POOL SWELL MODEL REPORT Model Report Completed NID0/NEDE 21544-P 12/16 - 2/77 LP SER/IP A.3 IMPACT TESTS Psir 1/3 Scale Tests Completed NrD0/ NICE 13476-P 8/75 - 9/75 LP SER/IP Mark 1 1/12 Scale Tests Completed NLU0/NIDC 20989-2P 9/75 - 11/75 LP SER/IP A.4 IMPACT MODEL PSIF 1/3 Scale Tests Completed NLD0/NEDE 13426P 8/75 - 9/75 LP SER/IP Mirk I 1/12 Scale Tests Completed fif D0/NEDC 20089-2P '

9/75 - 11/75 LP SER/IP A.5 LOADS ON SUBMERGED LOCA/RH Air Dubble Model Completed NID0/NEDE 21471-P 9/77 - 1/78 LP SER/IP STRUCTURES LOCA/RH Water Jet Model Completed NLD0/NLDE 21472-P 9/77 - 1/78 LP SER/IP Ring Vortex Model Completed Letter Report 5/79 - 5/79 LP/IP 4Q 79 Topical Report IP Applications 11ethods Completed N!D0/NEL'E 21730-P 12/77 - 1/78 LP SER/IP Ouenc. Air Dubble Model 3Q 79 NIDO 21471 Supplement IP Appl. Mem. Supplement 3Q 79 NfDE 21730 Supplement IP Quencher Air Unbble Dat.i Eval.

4Q 19 Report Info 1/4 Scaling Tests Complete NtDE 23817-P 9/78 - 12/18 info Steam Condensation Methods -

Plant DAR's LP SER/IP A.6 CHUGGING ANALYSIS AND Single Cell Report Completed NED0/NEDE 23703-P 9/77 - 11/77 LP SER TESTING Multivent Model Completed NID0/NLDE 21669-P 2/78 - 3/78 IP 4T FSI Report Completed NLD0/NIDE 23710-P 4/78 - 3/78 LP SER A.7 CHUGGING SINGLE VENT CREARE Report Completed NLD0/NEDE 21851-P 6/78 - 7/78 Info.

A.9 ERPI TEST EVALUATION EPRI-4T Comparison Co.npleted NCD0 21667 8/77 - 9/77 LP SER*

EPRI 1/13 SCALE TESTS 3D Tests Compicted EPRI NP-441 4/77 - --

LP SER*

EPRI $1NGLE CELL TESTS Unit Cell Tests 3Q 79 EPRI Report Info A.ll MULTIVENT SU35CALE TESTING Preliminary MV Prog Plan Completed NfD0 23697 17/77 - 1/78 LP SER/IP AND ANALYSIS IN lest Program Plan & Proc. Completed Ulf,0 23697 Rev 1 1/79 - 4/79 IP Q

- Phase !

' Phase i Te:,t Report 3Q 79 Report IP U

MV Test Prog Plan & Proc 3Q 79 NIDO 23697, Rev. 1, Supp. 1 IP (g

- Phase 11 Phase 11 Test Report 2Q 80 Report IP M

CON"AP Tests 3Q 79 Report Info.

11H'i Verification N

1/10 Scale Completed NEDE 25116-P 5/79 - 7/79 Info.

D A.13 SINGLE' VENT LATERAL LOADS Dynamic Analysis Completed Nt00 24106-P 3/78 - 7/78 IP Sumnary Heport Com;11eted NEDE 23006-P 10/78 - 11/78 IP M

Summary Report (Extension) 3Q 79 Report 6

C~D A.1G IMPROVED CHUGGING LOAD Impulse Evaluation Completed Letter Report 6/78 - 7/78 LP SER*

7g der!N! TION Improved Chug Load Defn.

3Q 79 Report IP A.17 STEAM CONDENSATION 05CILL.

4T C.O. Test 2Q80 Report IP y

CK:at/30E2 CK070979

e MARK 11 CONTAINMENT - SUPPORTING PROGRAM SRV - RELATED TASKS TARGET DATE LEAD PLANT SER'/.

TASK NUFFER ACTIVITY ACTIVITY TYPE COMPLETION DOCUMENTATION DOC /5UBM INTERMED PLANT B.1 QUENCIIER EMPIRICAL MODEL OFFR Model Completed NED0/N[DE 21061-P 9/76 - 9/76 IP Supporting Data Completed NED0/NECE 2!078-P 5/75 - 7/75 IP B.2 RAMSHLAD MODEL DrlR Model Completed NC00/NCDE 21061-P 9/76 - 9/76 LP SER Supperting Data Completed NLD0/NECE 21062-P 7/75 - 10/75 LP SER Analysis Corpleted Nl00/N!DE 20912-P 5/75 - 7/75 LP SER B.3 MONTICELLO IN-PLANT Preliminary Test Rpt.

Completed NfD0/NLDC 21465-P 12/76 - 1/77 LP SER 5/RV TESTS lfydrodynamic Peport Completed NLD0/GlDC 2158I-P 8/77 - 8/77 LP SER B.5 5/RV QUENCHER IN-PLANT Test Plan Completed NEDft 20988 Rev. 2 12/76 - 3/77 IP CA0R50 TESTS Test Plan Addendum 1 Completed NIDM 20988 Rev. 2. Add 1 10/17 - 3/78 IP Co.pleted htCM 20900 Rev. 2, Add 2 4/18 - 7/78 IP Test Plan Addendum 2 m

Test Summary Completed tetter Report 3/19 - 3/19 Phase I Test Report Co.rpleted NLDE-25100-P 5/79 - 6/79 IP Phase Il Test Report IQ C0 Report IP B.6 THERMAL MIX 1NG MODEL Analytical Model Completed NT(10/NEDC 23689-P 3/78 - 3/78

. Info.

B.10 MONTICELLO FSI Analysis of F51 Completed NLD0 23034 6/18 - 7/78 LP SER B.11 DFFR RAM 5 HEAD MODEL Data /Model Comparison Completed NSC-GLN 0394 9/77 - 10/77 LP SER TO MCNTICELLO DATA B.12 RAMSHfAD SRV METHODOLOGY Analytical Methods Completed NEDO 24070 10/77 - 11/77 LP SER SLEMAPY B.14 QUFNCHER EMPIRICAL MODEL Model Confirrnation IQ 80 Report Info.

UPDATE L3 h

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CK070979

MARK II CONTAINMENT - SUPPORTING PROGRN4 MISCELLANECUS TASKS TASK TARGET DATE LEAD PLANT SER/

NUMBER ACTIVITY ACT!VITY TYPE COMPLETION 00CtmENTAT!0N 00C/SUBM INTERMED PLANT C.0 SUPPORTING PROGRAM 5ttp Prog Rpt Completed NEDO 21297 5/76 - 6/76 Sepp Preg Ept Rev.

Completed NEDO 21297 - Rev. 1 4/78 - 4/78 5typ Prog Rpt Rev.

4Q 79 Nt00 21297 - Rev. 2 Info C.1 DFFR REVISIONS Revision 1 Completed NED0/NEDE 21061-P Rev. 1

'9/75 - 4/76 Revision 2 Completed NlD0/NIDE 210Gl-P Rev. 2 9/76 - 9/16 Revision 3 Completed NI D0/NIDE 21061-P Rev. 3 6/18 - 6/78 C.3 NRC ROUND 1 QUESTIONS OffR Rev. 2 Completed NID0/NEDE 21061-P Rev. 2 9/76 - 9/76 LP SER*/IP DFFR Rev. 2 Amendment 1 Completed NLD0/NIDE 2l061-P Rev. 2 Amend. I 12/76 - 2/77 LP SER*/IP DilR Rev. 3 Appendix A Completed NLD0/NLDE 21061-P Rev. 3 Appendix A 6/78 - 5/79 LP SER*/IP C.5 SRSS JUST!FICATION Interim Report Completed (NEDE 24010) 4/77 - 3/77 SRSS Report Completed NfD0/NtDE 24010-P 7/77 - 8/77 LP SER*/IP SR55 Exec Report Completad Summary Report 4/78 - 5/78 LP SER*/IP SRSS Criteria Appl.

Completed NID0/NIDE 24010-P Suppl. 1 10/78 - 11/78 LP SER*/IP SRSS Cases Convicted NID0/NEDE 24010-P suppl. 2 12/18 - 2/79 LP/IP SRSS Justification Suppl. 3Q /9 Report LP/IP C.6 NRC ROUND 2 QUESTIONS OffR Amendment 2 Completed NED0/NIDE 21061-P Rev. 2 Amend. 2 6/77 - 7/77 LP SER*/IP OffR Acerd 2, Suppl 1 Completed NLD0/NEDE 21061-P Rev.2 Amend.2 Supp.1 8/77 - 9/77 LP SER*/IP CH R Amend 2, Suppl 2 Completed Nip 0/NIDE 21051-P Rev.2 Amend.2 Supp.2 9/77 - 11/77 LP SER*/IP OffR Rev. 3, Appendix A Completed NLD0/NLDE 21061-P, Rev. 3 Appendix A 6/78 - 7/79 LP SER*/IP C.7 JUSTIFICATION OF "4T" Chugging toads Complete NID0/NEDE 23617-P 7/77 - 8/77 LP $[R/IP EDUNDING Lor:5 Justification Complete NID0/NI DE 24013-P 6/77 - 8/77 LP SER/IP Complete NIP 0/NEDE 24014-P 6/77 - 8/77 LP SER/IP Complete NID0/H[DL 24015-P 6/77 - 8/77 LP SER/IP Complete NID0/NEDE 24016-P 6/77 - 8/77 LP STR/IP Cor;ilete Nt00/N!I)E 24017-P 6/77 - 8/77 LP SER/IP Complete NLU0/NLDE 23t>27-P 6/77 - 8/77 LP SER/IP C.8 5/RV AND CHUGGING Prestressed Concrete FSI Reinforced Concrete Completed NED0/NEDE 21936-P 7/78-7/78 LP SER/IP Steel C.9 MONITOR VORLD TESTS Monitor Tests End of None G

y Program C.13 LOAD COMBINATIONS &

Criteria Justification Completed NEDO 21985 9/78 - 12/78 IP g"

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9 LN C.14 FCC ROUND 3 QUESTIONS Letter Report Completed Letter Report 6/78 - 6/78 LP SER*/IP DfFR, Rev. 3, Appendix A NEC0/NEDE 21061-P Rev. 3 Appendix A 6/78 - 5/79 LP SER*/IP M) g O

C.15 5UBMERGED STRUCTURE CRITERIA NRC Question Responses 3Q 79 Letter Report LP SER/IP QJ Cr4

" Submitted in response to NRC question.

LP SER: Zimmer, LaSalle, Shoreham IP: All Other Plants CK:at/30E1 lJ CK070979

I M "E 1->e-79 MARK II PROGRAM LICENSING BACKGROUND ORIGINAL PRESSURE SUPPRESSION DESIGN BASIS HUMBOLDT BAY LOCA TESTS 1958-1960 BODEGA BAY LOCA TESTS 1962-1963 NEW ERA 0F TESTING STARTS GE SMALL SCALE MARK III TESTS 1971 QUAD CITIES SRV TESTS (RAMSHEADS)

OCT 1972 KWU SRV TESTS (00ENCHERS) 1972-1974 MARVIKEN LOCA TESTS START AUG 1973 GE MARK III PSTF TESTS START fl0V 1973 HYDRODYNAMIC LOADING CONDITIONS BEGIN TO BE DEFINED FIRST RAMSHEAD SRV MODEL APRIL 1973 PRELIM. MARK III P0OL SWELL LOADS APRIL 1974 PRELIM. MARK II SRV LOADS IDENTIFIED DEC 1974 PRELIM. MARK II LOCA LOADS IDENTIFIED JAN 1975 TWO MARK II's REPORT TO NRC f1 ARCH 7,1975 NRC LETTERS REQUESTING LOCA INFORMATION APRIL 17, 1975 NRC LETTERS REQUESTING SRV INFORMATION APRIL 21, 1975 MARK I AND II OWNERS GROUPS FORM MAY, 1975 1733 304 LJS 7/24/79

MARK II PROGRAM LICENSING BACKGROUND PROGRAM APPROACH PHASE I --- DYNAMIC FORCING FUNCTION REPORT (DFFR)

DEFINES HYDRODYNAMIC LOADS FOR LOCA AND SRV, PROVIDES ANALYTICAL TOOLS FOR PLANT UNIQUE LOAD DEFINITION, AND LISTS STRUCTURAL CRITERIA TO BE USED FOR PLANT UNIQUE DESIGN ANALYSIS.

PREPARED BY GE AND SARGENT AND LUNDY SUBMITTED TO THE NRC OCTOBER 25, 1975 REVISIONS MADE AS REQUIRED TO REFLECT RESOLUTION OF NRC REVIEW 0F DFFR AND SUPPORTING PROGRAM uS 1733 305 7/24/79

MARK II PROGRAM LICENSING BACKGROUND PROGRAM APPROACH PHASE II --- DESIGN ANALYSIS REPORT (DAR)

DOCUMENTS THE STURCTURAL ANALYSIS / DESIGN USING PLA UNIQUE HYDRODYNAMIC LOADS AND LOAD CRITERIA THAT RESULT FROM APPLYING THE METHODOLOGY IN THE DFFR PREPARED BY UTILITY AE SUBMITTED TO NRC FEBRUARY THROUGH JUNE 1976 REVISIONS MADE AS REQUIRED TO REFLECT RESOLUTION OF NRC REVIEW OR TO REFLECT CHANGES TO DFFR 1733 306 LJS 7/24/79

MARK II PROGRAM LICENSING BACKGROUND PROGRAM APPROACH PHASE III --- SUPPORTING PROGRAM PROVIDES TESTING AND ANALYSIS INFORMATION TO DEMONSTRATE THE ADEQUACY OF DFFR METHODOLOGY MANAGED BY GE SUBMITTED TO THE f!RC AS EACH TASK IS COMPLETED 1733 307 LJS 7/2l4/79

MARK II PROGRAM LICENSING BACKGROUND PROGRAM INTEGRATI0il MUST CONSIDER STATUS OF DESIGN / CONSTRUCTION e

ALTHOUGH PLANTS ARE AT VARIOUS STAGES OF CONSTRUCTION, ESSENTIALLY ALL EQUIPMENT IS FABRICATED AND MUCH OF IT ALREADY INSTALLED.

e LIKE SEISMIC LOADS, HYDRODYNAMIC LOADS AFFECT THE CONTAINMENT STRUCTURE AND ALL EQUIPMENT CONTAINED WITHIN IT.

e THUS, IN ADDITION TO THE HYDRODYNAMIC LOAD DEFINITION ITSELF, DYNAMIC LOAD COMBINATIONS, THE METHOD OF COMBINING THEM (ABS vs SRSS), AND THE ACCEPTANCE CRITERIA, BECOME EXTREMELY IMPORTANT IN ORDER TO ATTAIN A BALANCED DESIGN.

e ALTHOUGH FUNCTIONAL CAPABILITY IS REALLY A GENERIC NRC CONCERN THAT NEED NOT BE RESOLVED AS PART OF THE MARK II PROGRAM, AN EFFORT IS BEING MADE TO ADDRESS THIS ISSUE.

e BECAUSE OF ADVANCED STAGE OF CONSTRUCTION AND LICENSING REVIEW, ZIMMER, LA SALLE AND SHOREHAM FORM LEAD PLANT SUBGROUP IN MID 1977, e

BECAUSE OF GENERIC NSSS EQUIPMENT ADEQUACY EVALUATION NEEDS FOR MARK II AND III PLANTS, GE INITIATES SEPARATE DISCUSSIONS WITH NRC (MATTSON) IN EARLY 1978, e

SQRT ACTIVITIES AND SCHEDULE HAVE A HIGH POTENTIAL FOR FURTHER COMPLICATING MARK II PROGRAM CLOSURE.

1733 308 LJS 7/24/79

MARK II PROGRAM LICENSING BACKGROUND STRATEGY FOR LEAD MARK II PROJECTS ESTABLISH COMPREHENSIVE LEAD PLANT PROGRAM DEFINITION e

SEPARATE PROGRAM INTO BASIC AND CONFIRMATORY ACTIVITIES e

e KEEP DFFR CURRENT WITH PROGRAM OUTPUT e

COMPLETE OR UPDATE DESIGN ANALYSIS REPORTS e

KEEP PRESSURE ON NRC REVIEW SCHEDULE LEAD PLANT STATUS /0 PEN ITEMS ARE TO BE DISCUSSED IN A SEPARATE MEET 1733 3C9 LJS 7/24/79

MARK 11 PROGRAM LICEllSING BACKGROUf1D KEY AREAS NEEDIflG NRC ATTENTION / RESOLUTION SRSS - MARK H OWNER POSITI0I1S REGARDING NRC ACCEPTANCE CRITERIA ON LOAD DEFINITI0:1 ARE BASED Oil APPROVAL OF SRSS FOR ALL DYilAMIC LOADS (LOCA, SEISMIC, & SRV).

MARK II & III EQUlPMEllT ADEQUACY ASSESSMENTS UTILIZE SRSS COMBINATION METHODOLOGY.

LOAD COMBI!1ATIONS - LOAD CASE 10 IS A NEW NRC REQUIREMENT FOR EQUIPMENT ADEQUACY ASSESSMEllTS WHICH TAKES AN ARBITRARY LOAD COMBINATION FOR DEMONSTRATIllG C0tlTAltlf1EilT ASYMMETRIC LOCA LOAD CAPABILITIES & MAKES IT A MECHANISTIC COMBINAT10fl fl0T PREVIOUSLY CONSIDERED.

ACCEPTANCE CRITERIA - ARBITRARY f!RC CLASSIFICATION OF THE OBE BY ITSELF 3 THE OBE WITH SRV'S AS EQUAL IS NOT APPROPRIATE CONSIDERING THAT LOADS ARE C0ilBINED AS THOUGH INDEPENDENT.

OBE + SRV ALLOWABLE STRESS LIMITS, ilUMBER OF SRV'S, &

THE flEED FOR FATIGUE ANALYSIS (PREVIOUSLY RESOLVED) CREATIllG UllCERTAINTIES IN EQUIPMENT ADEQUACY ASSESSMEllTS.

1733 310 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II POOL DYNAMIC LOADS L0flG TERM PROGRAM LEAD PLANT LOAD LOCA

"" " I.A SUBMERGED BOUfDARY VENT CLEARING LOAD MARCH 20, 1979 LETTER.

24 PSI MARCH 20, 1979 LETTER.

24 PSI STATICALLY APPLIED TO SURFACES STATICALLY APPLIED TO SURFACES BELOW VENT EXIT (ATTEtiUATE TO BELOW VENT EXIT (ATTENUATE TO 0 PSI AT P0OL SURFACE) FOR O PSI AT P0OL SURFACE) FOR PERIOD OF VENT CLEARING.

PERIOD OF VENT CLEARING. ZIMMER AND LASALLE MEET NUREG-0487 1.B.1 P00L SWELL ANALYTICAL MODEL (a)

ACCEPT NUREG 0487 (a) ACCEPT NUREG 0487 (b)

ACCEPT NUREG 0487 (SH0REHAM (b) APPROACH IN RESPONSE TO QUESTION 020.68 TO CF FEBRUARY 16, 1979 LETTER RE-USED.

EMPHASIZE RESPONSE TO QUESTION 020.68).

(c)

ACCEPT NUREG 0487 WITH VELOCITY (c) ACCEPT NUREG 0487 WITH VELOCITY VS. ELEVATION VS. ELEVATION OBTAINED FROM OBTAINED FROM PSAM.

PSAM.

(d) ACCEPT NUREG 0487 (d)

ACCEPT NUREG 0487 (e) ACCEPT NUREG 0487 (e)

ACCEPT NUREG 0487 (f) ACCEPT NUREG 0487 (f)

ACCEPT NUREG 0487 I.8.2 SUBMERGED B0UNDARY POOL SWELL LOAD ACCEPT NUREG 0487 ACCEPT NUREG 0487 I.B.3 POOL SWELL IMPACT LOAD (a) ACCEPT NUREG 0487 (a)

ACCEPT NUREG 0487 (b)

NOT APPLICABLE (N0 LARGE (b)

NOT APPLICABLE (N0 LARGE STRUCTURES).

STRUCTURES).

(c)

ACCEPT NUREG 0487 WITH VELOCITY (c)

ACCEPT NUREG 0487 WITH VELOCITY VS. ELEVATION VS. ELEVATION OBTAINED FROM OBTAINED FROM PSAM.

PSAM.

1733 3ll LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II P00L DYNAMIC LOADS (Continued)

LONG TERM PROGRAM LOAD LEAD PLANT I.B.4 WETWELL AIR COMPRESSION (a)

ACCEPT NUREG 0487 (a) ACCEPT NUREG 0487 (b)

ACCEPT NUREG 0487 (b) ACCEPT NUREG 0487 1.B.5 ASYMMETRIC LOADING _

MARCH 16, 1979 LETTER.

10% OF MARCH 16, 1979 LETTER. 10% OF MAXIMUM BUBBLE PRESSURE MAXIMUM BUBBLE PRESSURE STATICALLY APPLIED T0 1/2 0F STATICALLY APPLIED T0 1/2 0F THE SUBMERGED B0UNDARY WITH THE SUBMERGED B0UNDARY WITH HYDROSTATIC PRESSURE.

HYDROSTATIC PRESSURE.

I.C.1 00'ANCOMER LATERAL LOADS (a)

NUREG 0487 ACCEPTABLE FOR STATIC (a) TASK A.13 SINGLE VENT DYNAMIC LATERAL LOAD TO BE USED.

ANALYSIS.

(b) TASK A.13 MULTI-VENT DYNAMIC (b)

ACCEPT NUREG 0487 LATERAL LOAD TO BE USED.

I.C.2 SUBMERGED B0UNDARY STEAM CONDENSATION LOADS (a) ACCEPT NUREG 0487 (a)

ACCEPT NUREG 0487 (b)

ACCEPT NUREG 0487 (b) ACCEPT NUREG 0487 AS INTERIM.

( ADDITIONAL FREQUENCY RANGES EVALUATED) FINAL BASIS TO BE 4T C.0. TEST RESULTS.

(c)

ACCEPT NUREG 0437 (c) ACCEPT NUREG 0487 AS INTERIM.

FINAL BASIS TO BE TASK A.16 LOAD IMPROVEMENT PLUS MULTI-VENT TEST RESULTS AS CONFIRMATION.

SRV II.A P0OL TEMPERATURE LIMITS (a)

ACCEPT NUREG 0487 (a)

DOCUMENT WILL BE PREPARED USING ADDITIONAL PP&L TEST DATA TO SUPPORT NO (LOCAL) TEMPERATURE LIMIT FOR QUENCHERS.

(b) NUREG-0487 NOT APPLICABLE BA ON (a) AB0VE.

(c)

ACCEPT NUREG 0487.

1733 312 uS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II P00L DYNAMIC LOADS (Continued)

LONG TERM PROGRAM LEAD PLANT LOAD II.B AIR,,LEt(IING LOADS (a)

ACCEPT NUREG 0487 (a) T-QUENCHERS LOAD PREDICTIVE METHODS PRESENTED IN SUSQUEHANNA DAR, SECTION 4.1.3 X-QUENCHER LOAD DEFINITION BEING DEVELOPED BY BURflS & ROE BASED LARGELY Ofl CAORSO TEST DATA (b)

LOAD CASE 5 IS NOT REALISTIC (b)

LOAD CASE 4 IS NOT If;CLUDED FOR EVALUATION.

IT IS B0UNDED BY CASE AfiD SHOULD NOT BE INCLUDED FOR EVALUATION. MULTIPLE 1.a AND 1.b.

VALVE CASES WILL BE ADDRESSED IN PLANT DARs.

(c)

PLANT UNIQUE CLOSURE REPORTS (c) T-QUEliCHER BUBBLE FREQUENCY PRESENTED IN SUSQUEHANNA DAR, DEFINE METHOD USED TO DEFINE SECTION 4.1.3.

BUBBLE FREQUENCY.

X-QUENCHER BUBBLE FREQUENCY BEING DEVELOPED BY BURNS & ROE BASED LARGELY ON CAORSO TEST DATA.

II.C.1 QUENCHER ARM LOADS (a) NUREG 0487 NOT APPLICABLE (a) ACCEPT NUREG 0487 (b) ACCEPT NUREG 0487 (b) T-QUENCHER ARM LOADS PRESEN SUSQUEHANf;A DAR, SECTION 4.1.2.5 II.C.2 00ENCHER TIE-DOWN LOADS (a) NUREG 0487 NOT APPLICABLE (a) ACCEPT NUREG 0487 (b) ACCEPT NUREG 0487 (b) T-QUENCHER TIE-DOWN LOADS PRESENTED IN SUSQUEHANNA DAR, SECTION 4.1.2.5.

1733 313 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II PGOL DYNAMIC LOADS (Continued)

LONG TERM PROGRAM LEAD PLANT LOAD SUBMERGED STRUCTURES III.A WATER JET LOADS l

RING VORTEX MODEL INCLUDING 1

WILL ADDRESS CRITERIA BY POTENTIAL FUNCTION FOR INDUCED BY PROPOSING CORRECTED EQUATIONS FLOW BEING FINALIZED.

MORE IN 1.a AND 1.b. SUBMIT PRELIMI-APPROPRIATE ACCELERATION DRAG fiARY RING VORTEX M0D., AND CONSIDERATION TO BE IDENTIFIED.

SUPPORTING SUBSCALE Bt.1CH MARK TEST.

2 DATA FROM T-QUENCHER TEST PROGRAM 2

ZONE OF INFLUENCE DEVELOPED PRESSURE TRANSDUCER P5.5, SHOWS BASED ON T-QUENCHER PROGRAM NO WATER JET EFFECT (SUSQUEHANNA AND/0R QUENCHER WATER JET DAR,SECTI0tl8).

I;0 SIGNIFICANT MODEL. N0 SIGNIFICANT LOADS LOADS BEYOND 5FT ZONE OF BEYOND 5 FT.

INFLUENCE.

3 NUREG-0487 X-QUENCHER CRITERIA ACCEPTED.

III.B AIR BUBBLE DRAG LOADS 1(a) ACCEPT NUREG 0487 ADJUSTMENTS 1(a) ACCEPT NUREG 0487 ADJUSTMENTS TO DRAG TO DRAG (b)

IDENTIFY MORE APPROPRIATE (b)

IDENTIFY MORE APPROPRIATE ACCELERATION DRAG COEFFICIENT ACCELERATION DRAG COEFFICIENT TREATMENT THAN FACTOR OF 3.

TREATMENT THAN FACTOR OF 3.

(c) DEMONSTRATE THAT ACCELERATION (c) DEMONSTRATE THAT ACCELERATION AT CENTER OF STRUCTURE IS AT CENTER OF STRUCTURE IS TECHNICALLY CORRECT.

DEMON-TECHNICALLY CORRECT.

DEMON-STRATE THAT ERROR RESULTING STRATE THAT ERROR RESULTING IN VELOCITY AT CENTER VS.

IN VELOCITY AT CENTER VS.

MAXIMUM VELOCITY IS SMALL MAXIMUM VELOCITY IS SMALL AND B0UNDED BY CONSERVATISM AND BOUNDED BY CONSERVATISM IN VELOCITY APPLIED. THUS IN VELOCITY APPLIED. THUS SIMPLIFIED DFFR APPROACH IS SIMPLIFIED DFFR APPROACH IS ACCEPTABLE.

ACCEPTABLE.

1733 3;4

'S 7/24/79

NRC ACCEPTANCE CRITERIA MARK II POOL DYflAMIC LOADS (Continued)

LONG TERM PROGRAM LEAD PLANT LOAD (d) DEMONSTRATE THAT FACTOR (d) DEM0flSTRATE THAT FACTOR

(&) 0F 4 IS f;0T TECHNICALLY CORRECT

(&) 0F 4 IS ft0T TECHNICALLY CORRECT (e) FOR STAfiDARD DRAG. REFER (e) FOR STAtlDARD DRAG. REFER TO QUESTI0f! RESP 0f4SE TO TO QUESTION RESP 0ftSE TO 020.70.

INTERFEREllCE EFFECT 020.70.

If4TERFEREllCE EFFECT ON ACCELERATI0fl DRAG WILL Oil ACCELERAT10ft DRAG WILL BE ANALYZED Oft A PLAflT UNIQUE BE ANALYZED Oft A PLAflT UNIQUE BASIS.

BASIS.

(f) ACCEPT flVREG-0487 (f) ACCEPT fiUREG-0487 2(a) NOT APPLICABLE (ft0 RAMSHEADS 2(a) ACCEPT NUREG-0487 (b) FOR III.B.l(a) AND (c) THRU (f), SEE AB0VE.

FORIII.B.l(b),

IT WILL BE DEM0flSTRATED THAT A FACTOR OF 3 FOR DRAG COEFFI-CIENTS IS fl0T CORRECT FOR OSCIL-LATIriG BUBBLES AND THAT STANDARD DRAG LOADS ARE flEGLIGIBLE.

3 T-QUENCHER METHODOLOGY PRESENTE 3

T-QUEllCHER BUBBLE LOCATION AND IN SUSQUEHAriNA, DAR 4.1.3.

SIZE ARE PLAf4T UtlIQUE.

AMPLI-TUDE AND FREQUENCY ARE BASED X-QUENCHER METHODOLOGY TO BE ON PP&L PROGRAM, METHODOLOGY PRESENTED IN HANFORD 2 DAR.

FROM NEDE-21471-P IS USED TO APPLY LOAD TO STRUCTURES.

III.C STEAM CONDENSATION LOADS PLANT UNIQUE METHODS BEING ACCEPT NUREG-0487 DEVELOPED.

LJS 1733 315 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II LOAD COMBINATIONS FOR NOTE:

SRSS IS TECHNICALLY JUSTIFIED AND IS THE LICENSIflG BASIS.

LOAD COMBINATI0';

LEAD PLANT LONG TERM PROGRAM

  1. 1 N+5RV T0 B ACCEPTABLE ACCEPTABLE x

N+SRV +0BE TO B AND N&

  1. 2 N+SRV +0BE TO B N+SP,Vall+0BE TO B USED.

2 x

SRV33)+0BE TO C USED.

APPROVED GESSAR APPROACH USED FOR NSSS.

SRV IS ARBITRARY, 2

APPROVED GESSAR APPROACH USED FOR NSSS.

SEE RE-SPONSE TO QUESTION MEB-7b.

f3 N+SRVall+SSE ACCEPTABLE. WE RESERVE RODABAUGH PAPER TO BE USED 4

THE RIGHT TO USE THE AS BASIS FOR ACCEPTANCE TO C RODABAUGH CRITERIA CRITERIA (i.e., C OR D).

  1. 4 N+SRVads+0BE+5BA ENVELOPED BY 55 AND #6 TO C"
  1. 5 N+SRVads+0BUIBA ENELOPED BY #6 TO C"
  1. 6 N+SRVads+SSE+IBA SAME AS POSITION FOR #3 SAME AS POSITION FOR #3.

TO C"

  1. 7 N+SSE+DBA TO C" SAME AS POSITION FOR #3 SAME AS POSITION FOR #3.

SEE RESPONSE TO QUESTION MEB-7a.

  1. 8 N TO A ACCEPTABLE ACCEPTABLE
  1. 9 N+0BE TO B ACCEPTABLE ACCEPTABLE
  1. 10 N+SRV +SSE+DBA APPLIED TO CONTAINMENT ONLY (SEE M 020.22 & DFFR 5.2.4) 3 TO C" 1733 316 LJS

NRC ACCEPTANCE CRITERIA OTHER MISCELLANE0US POSITIONS NRC POSITION LEAD PLANT LONG TERM PROGRAM FUNCTIONAL ACCEPTABLE.

WE RESERVE DEMONSTRATION OF FUNCTIONAL CAPABILITY THE RIGHT TO USE THE CAPABILITY WILL BE BASED ON RODABAUGH CRITERIA RODABAUGH CRITERIA.

MASS-ENERGY ACCEPTABLE T0 ZIMMER AND VERIFICATION OF MASS-ENERGY RELEASE FOR LASALLE.

RELEASE RATE HAS BEEN SHOWN ANNULUS PRESSURIZATION BE ZIMMER, LASALLE AND SH0REHAM ASSUMES VERIFICATION HATCH-2.

OF MASS-ENERGY RELEASE RATE HAS BEEN SHOWN BY ZIMMER, LASALLE AND HATCH-2.

QUESTIONS SEB-2, MEB-5 15% PEAK BROADENING TO BE USED.

SEB-3, MEB-5 CLOSELY SPACED MODES ARE COMBINED PER 1.92 WHERE REANALYSIS IS PERFORMED.

NSSS SCOPE USES MODIFIED SUMMATION PER APPROVED GESSAR.

MEB-1 ACCEPTABLE MEB-2 ACCEPTABLE MEB-6 ACCEPTABLE MEB-7a AND b SEE LOAD COMBINATION TABLE FOR CASE #2 AND #7 MEB-8 SEE FUNCTIONAL CAPABILITY DISCUSSION AB0VE AND LOAD COMBINATION AND ACCEPTANCE CRITERIA TABLE.

1733 317 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II POOL DYNAMIC LOADS BAILLY HANFORD LIMERICK t!INE MILE PT, SUSQUEHANNA LOCA

1. A - VENT CLEARING X

X I. B - POOL SWELL X

I. C - C. O. 8 CHUGGING X

X SRV II.A - TEMPERATURE LIMIT X

II.B - AIR CLEARING X

II.C - TIE DOWN X

-X SUBMERGED STRUCTURES III.A - JET III.B - AIR BUBBLE X

X X

X III.C - STEAM C0ilD.

X X

X X

N co LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK 11 POOL DYNAMIC LOADS BAILLY (SARGENT & LUNDY)

THE DESIGN MEETS NUREG 0487 1.A II.C.ls -

T-0UEllCHER ARM LOADS ARE GENERATED USitlG SUBMERGED STRUCTURE METHODOLOGY SIMILAR TO L PLANTS.

Ill.B.3 T-00ENCHER AIR BUBBLE SUBMERGED STRUCTURE LO ARE GENERATED USING METHODOLOGY SIMILAR TO L PLANTS.

1733 319 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II P0OL DYNAMIC LOADS HANFORD (BURNS & R0E)

I.B.3A - SMALL STRUCTURE POOL SWELL IMPACT LOADS ARE GENERATED PER DFFR, REV. 3 I.B.3c - GRATING POOL SWELL IMPACT LOADS ARE GENERATED WITH DRAG FOR MAXIMUM POOL SWELL VELOCITY (FROM IDEL'CHIK)

APPLIED ON GROSS AREA WITH DYNAMIC LOAD FACTOR OF 2.

I.C.2c - THE SUBMERGED BOUNDARY CHUGGING LOAD IS GENERATED PER BURNS & ROE REPORT " CHUGGING LOADS - IMPROVED DEFINITION AND APPLICATION METHODOLOGY TO MARK II CONTAINMENTS TECHNICAL REPORT", JUNE 1979.

II.A

- NO LOCAL POOL TEMPERATURE LIMIT FOR X-0UENCHER OPERATION III.B.1

- THE LOCA AIR BUBBLE SUBMERGED STRUCTURE LOADS ARE GENERATED USING:

SOURCE - BASED ON PSAM (NEDE-21544-P) AtlD DFFR, REV. 3 FLOW

- THREE DIMENSIONAL SOURCE FLOW IN EXACT CONTAINMENT GE0 METRY DRAG

- PER GENERIC POSITION LJS 7/24/79 1733 320

NRC ACCEPTANCE CRITERIA MARK II POOL DYNAMIC LOADS HANFORD (BURNS & ROE) CONTINUED III.B.3 - THE X-00ENCHER AIR BUBBLE SUBMERGED STR LOADS ARE GEllERATED USING POTENTIAL FLOW WITH SOURCES / SINKS DISTRIBUTED TO MAXIMIZ FLUID TRAtlSIENTS IN CONJUNCTION WITH SRV AIR CLEARING LOAD AND CA0RSO DATA.

III.C

- THE STEAM CONDENSATION SUBMERGED STRUCTUR ARE GENERATED USING POTENTIAL FLOW SOLUTI SOURCES / SINKS DISTRIBUTED TO MAXIMIZE INDUCE FLUID TRAtlSIENTS IN CONJUNCTI0ll WITH APPROP SOURCE STRENGTHS, DRAG COEFFICIENTS AND INTERFEREN EFFECTS.

1733 321 LJS 7/24/79 t

NRC ACCEPTANCE CRITERIA MARK II POOL DYNAMIC LOADS LIMERICK (BECHTEL)

III.B.1 - LOCA AIR BUBBLE SUBMERGED STRUCTUR ARE GENERATED BY USING NEDE-21471-P TO DETERMINE THE IDEALIZED (RAYLEIGH) BUBBL WITH THE EXCEPTION THAT THE TIME DEPEND DRYWELL PRESSURE HISTORY WILL BE USED I DEFINING THE BUBBLE PRESSURE.

THIS IDEALIZED BUBBLE WILL BE USED AS THE SOURCE TERM A MODIFIED IWEGS/ MARS CODE (DEVELOPED F TASK A.16) TO ESTABLISH ACCELERATION AND VELOCITY FLOW FIELDS.

APPLICATION OF FLOW FIELDS WI!L BE THE SAM.E AS LEAD PLANTS FO ITEMS A. THROUGH F.

- STEAM CONDENSATION SUBMERGED STRUCTURE III.C ARE GENERATED BY APPLYING THE C. O. AND CHUGGING SOURCE AT THE VENT EXIT IN A M IWEGS/ MARS CODE (DEVELOPED FOR TASK A ESTABLISH ACCELERATION AND VELOCITY F APPLICATION OF FLOW FIELDS WILL BE MADE APPROPRIATE DRAG COEFFICIENTS.

QUESTIONS MEB-5 AND SEB-3 CLOSELY SPACED MODES.ARE COMBINED PER R GUIDE 1.92 EXCEPT FOR SEISMIC LOADS.

SEISMIC REANALYSIS IS DONE PER ORIGINAL DESIGN LJS I733 322 7/24/79

NRC ACCEPTANCE CRITERIA MARK 11 POOL DYilAMIC LOADS ilINE MILE POINT (STONE & WEBSTER) 1.A GENERIC LOAD PROFILE IS APPLIED DYNAMICALLY.

II.B REFINEMENT OF METHODOLOGY CONSIDERING KARLSTEIN TEST DATA BEING CONSIDERED II.C REFINEMENT OF METHODOLOGY CONSIDERIl1G KARLSTEIN TEST DATA BEING CONSIDERED III.C VARIOUS ALTERNATIVE METHODS FOR DEVELOPING THE FLOW FIELDS ARE BEING EVALUATED 1733 323 LJS 7/24/79

NRC ACCEPTANCE CRITERIA MARK II POOL DYNAMIC LOADS SUS 00EHAliNA (BECHTEL)

I.C.2 - STEAM CONDENSATION BOUilDARY LOADS WILL BE SUPPORTED BY PP&L TEST AT GKM-2 III.B

- LOCA BUBBLE SUBMERGED STRUCTURE LOADS ARE GENERATED USING GREENS' FUNCTION TO DETERMINE FLOW FIELDS.

III.C

- STEAM CONDENSATION SUBMERGED STRUCTURE LOADS ARE GEllERATED USING GREENS' FUNCTI TO DETERMINE FLOW FIELDS.

QUESTIONS MEB-5 AND SEB-3 CLOSELY SPACED MODES ARE COMBINED PER REG GUIDE 1.92 EXCEPT FOR SEISMIC LOADS.

SEISMIC REANALYSIS IS DONE PER ORIGINAL DESIGN BASIS LJS 7/24/79

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Typical Mark II Pressure Suppression Contain=ent 1733 325

DOMESTIC MARK 11 UTILITIES AND PLANTS PLANT N AME UTILITY NAME NORTHERN INDI ANA PUBLIC SERVICE CO.

B Af LLY t CHESTERTON, INDI AN A WASHINGTON PUBLIC POWER SUPPLY SYSTEM HANFORD 2 RICHLAND, WASHINGTON COMMONWE ALTH EDISON COMPANY LASALLE 1 AND 2 CHIC AGO, ILLINOIS PHILADELPHI A ELECTRIC COMPANY LtMERICK 1 AND 2 PHILADELPHI A, PENNSYLVANI A NI AGAR A MOWH AWK POWER COMPANY NINE MILE POINT 2 SYR ACUSE, NEW YORK LONG ISLAND LIGHTING COMPANY SHOREHAM HICKSVILLE, NEW YORK PENNSYLVANI A POWER AND LIGHT COMPANY SUSQUEHANNA 1 AND 2 ALLENTOWN, PENNSYLVANI A CINCINNATI GAS AND ELECTRIC COMPANY ZIMMER CONCINN ATI, OHIO U

U u

Nos 9

MARK ll OWNERS' GROUP

~~

OBJ ECTIVES O TO SATISFACTORILY RESPOND TO THE EXPRESSED NRC CONCERNS RELATING TO DYNAMIC LOADS OCCASIONED BY LOCA AND SRV BLOWDOWN E. VENTS O TO POOL THE TALENTS OF THE OWNERS' ORGANIZATIONS, THEIR ARCHITECT-ENGINEERS, THE GENERAL ELECTRIC COMPANY AND SELECTED CONSULTANTS AND PRODUCE A RESPONSIVE, 5

TECHNICALLY SOUND PROGRAM

[

WHICH RESOLVES THE EXPRESSED Z

CONCERNS

MARK 11 OWNERS' ORGANIZATION M ARK ll OWNERS CONTROL COMMITTEE CH AIRM AN - P.D. HEDGECOCK (WPPSS)

VICE CH AIRMAN - E. MEAD (P.P. & L.)

PROGRAM M ANAGER-A.R. SMITH (GE)

OWNER REPS /AE PROJECT REPS TECHNICAL CONSULTANTS LICENSING LOCA SRV STRUCT/ MECH M. G R ANBACK (NIPSCO)

G. KITZ (FOR CE)

H. CHAU (LILCO)

W. VOLLMER (PECO)

(P. HEDGECOCK)

(E. ME AD) 4H. BRINKM ANN)

(NMCO)

O NCHE ^

l

( ARING SRSS & LOAD COMB.

NRCINTERFACE CHUGGING l

CONDENSATION OSC.

MASS / ENERGY POOL SWELL (EPRI)

SUBMERGED STRUCT.

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WHAT HAS CHANGED SINCETHE LAST

~

MARK ll MEETING WITH THE NRC (SPRING 1978) ON A CLOSURE PLAN FOR THE NON-LEAD PLANTS?

e NRC has issued NUREG-0487 e

Owners have decided upon which quencher to use in all cases (7, T-quenchers and 1, X-quencher) e Karlstein T-quenchers test completed e

Two in-plant SRV tests have been completed CAORSO and TOKAl (both X-quenchersD e

Two full-scale condensation oscillation programs have been agreed to (GKM/PP&L and Mark ll 4T) e The scaled multivent chugging test program (A.11 D d

is approaching completion y

e Three-Mile Island (TMI-2) happened

i WHY IS THERE NOT A TOTALLY GENERIC APPROACH?

e The choice of quenchersis not unanimous hence, both T and X-quencher programs exist e Schedule pressures have caused many AEs to develop their own analytical procedures

  • Plant-unique features tend to preclude the use of sweeping conservatisms which might facilitate a generic approach

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