ML19210C759
| ML19210C759 | |
| Person / Time | |
|---|---|
| Issue date: | 10/24/1979 |
| From: | Triplett M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210C757 | List: |
| References | |
| CON-FIN-A-3337, CON-FIN-A-3807 NUDOCS 7911200062 | |
| Download: ML19210C759 (5) | |
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NRC sceu 173 u s. NUCLE AM REGULATORY CCMuisSICN CRCE R NuMSE R (2 78) 20-80-9 STANDARD ORDER FOR DOE WORK 10/11/79 ISSUEO TQ: (CCE Cffice)
ISSUED BY: (N AC Cfficag ACCOUNTING CITAT!CN APeRCPRI ATICN Sv M SCL.
Office of Nuclear Reactor Brockhaven Area Office Regul atlan 31 x0200.200 u,NUM.e.
PERFCAMING CRGANIZATICN AND LCCATICN SEE BELGW PINNUMSc4 3reckhaven National L'aboratory SEE SELOW WOR K FERICD. THIS C A CE R FIN TITLE FIXED C l ESTIMATEC O Mark I Containment Analysis (A-3108)
Facu-TC
.vark I Containment Imolementation (A-3337) 10/1/79 9!/20/50 C8 LIGATION AVAILABILITY PROVIDED SY:
l5 180,000 A. ThiS CRCeR 6.
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O. AMCUNTINC: UCEO IN "C" APPUCABLE TC THE " FIN NUM8ER** CITE 3 IN THtS CRCER.
S 3E5 3EbCN FINANCIAL PLEX 188LITf:
C FUNCS WILL NOT SE AEPRCGAAMMED SETWEEN FINS. UNE O CCNSTITUTES A UMITAT:CN CN CBLIGATICNS
C FUNCS MAY SE REP ACGRAMME NCT TC EXCEE3 C 10% CF FIN LEVEL UP TO SSCK. UNE C CCNST CN CBLICAT:CNS AUTHCAICEO.
STANCA A0 *ERMS AND CCNCITICNS P9CVICE3 CCE AAE CCNSICEREQ FART CF THIS CROER UNLESS CTHE.9 WISE NCTED.
AT*ACH M E NTS.
THE SQLLCWING ATTACHMENTS ARE r4ERE3Y SECU AITY:
MACE A PART CF THIS CACER:
CWCAK CN THIS CACER IS NCT CLASSIFIEC.
" g"ATEMENT C F WCR M C WC AK CN Twi$ CACER INVOLVES CLASSIFIED C ACCIT:CNAL TERMS AND CCNCITICNS INFCAMATICN. NAC FCAM 187 IS AT*ACHEC.
C CTHER REMARKS.
After signature. please sand a Copy of this Order to:
M. Paulette Triplett. NRR, P 42S FIN B&R
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A-3337 20-19-01-03 110 /
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ACCEPTING CRGANIZATICN I
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SCOPE OF WORK MARK I CCNTAINMENT ASSESSMENT HCHNICAL ASSISTANCE General a.
This program will provide for the evaluaticn of the application of experimental and analytical programs related to suppression pool hydrodynamic loads. In application of the experimental programs, specific emphasis will be placed en the examination of the validity of applying test data from scale models to the prototype.
b.
To act as consultants to the NRC in the area of suppression pool hydrodynamics.
c.
To conduct analytical and computer studies, as necessarf, related to suppression cool dynamic loadings and other containment phenomena.
Task I: Safety Evaluation Report This task involves the completien of the generic Mark I Safety Evaluation Report, which documents the technical bases for the Long Term Program suppression pool hydrodynamic load definition techniques. This will include the resolution of staff conrents on initial drafts of the report. This report will be directly apolicable to licensing actions en each of the plants identified in Table 1.
Task II: Confirmatory Testing and Analyses This task involves the review and evaluation of confirmatorf testing and analyses perfonned to support the mposed Mark I load defini tion tecnniques. Specifically, this task includes the follcwing:
a.
Compressibility Effects - the results of analytical studies to assess the influence o# compressibility on scaled pool swell tests.
b.
Condensation Cscillations - the results of confirmatorf tests to ascertain the uncertainty in the condensation oscillation loading functions.
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. Task III: P1 ant Unique Analyses This task involves the review and evaluation of the application of the generic Mark I load definition techniques to the individual plant-unique analyses. Specifically, this task will include the following:
a.
Review Plan - based on the fomats of the first few plant-unique analyses and on the NRC acceptance criteria, a review plan will be formulated to assure consistent and timely evaluations of all of the Mark I plant-unique analyses.
b.
Plant-Specific Loads - any suppression pool hydrodynamic loads that are defined for a specific Mark I configuration will be evaluated separately.
Plant-Specific Evaluation Reports - following the reivew of c.
each Mark I plant-unique analysis, a summary evaluation report for that specific plant will be prepared, describing the conclusions made regarding the plant-specific load definition and degree of confor nance with the NRC generic criteria. These reports will be directly applicable to licensing actions on each of the plants identified in Table 1.
Task IV: Program Activities This task includes ca-call assistance, attendance at meetings as DOR consultants, and miscellaneous monitoring activities not specifically addressed by Tasks I through III.
1372 186
Table 1 Mark I Containment Plants Facility Name Docket No.
Browns Ferry Unit No.1 50-259 Browns Ferry Unit No. 2 50-260 Browns Ferry Unit No. 3 50-296 Brunswick Unit No.1 50-325 Brunswick Unit No. 2 50-324 Cooper Station 50-298 Dresden Unit No. 2 50-237 Dresden Unit No. 3 50-249 Duane Arnold 50-331 Fitzpatrick 50-333 Fermi Unit No. 2 50-341 Hatch Unit No.1 50-321 Hatch Unit No. 2 50-366 Hope Creek Unit No.1 50-354 Hope Creek Unit No. 2 50-355 Mills tone Unit No.1 50-245 Monticello 50-263 Nine Mile Point Unit No.1 50-220 Oyster Creek 50-219 Peach Bottom Unit No. 2 50-277 Peach Bottom Unit No. 3 50-278 Pilgrim Unit No.1 50-293 Qudd Cities Unit No. I 50-254 Quad Cities Unit No. 2 50-265 i J 7 )" kb 7
1 Vermont Yankee 50 -271
MARK 1 ASSESSMENT MILESTONE AND DECISION POINTS 1979 1980 OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP Task 1 Safety Evaluation Report V
Task 11 Confirmatory Tests and Analyses A.
Couvressibility Ef fects v
B.
Condensation Oscillations
--------- NOTE 1 Task 111 Planit Unique Analyses A.
Review Plan v
B.
P l a n t S p e c i f i c L o a ds - - - - - - -- --- - - - -- - --- --- - - - --- --- -- - -- -- ---- - - -- -- - --- --- ---- --- -- -- - -- --- - - N O T E 2 C.
Plant Specific Evaluation Reports ----------- ----------------------------------------------- - NOTE 2 Task IV Prog rati Activi ties v
NOTE 1 Schedule to be established when testing schedule has been submitted by the Mark I Owners Group.
Noll 2 individual schedules will be established when submittal dates are provided by each Mark I licensee,
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