ML19256D213
| ML19256D213 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/18/1967 |
| From: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910170712 | |
| Download: ML19256D213 (6) | |
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UNITED STATES GOVERNMENT Memorandum To Files DATE: September 13, 1967 ERU Charles 0. Long, Chie f y
Reactor ?roject 3 ranch No. 3, ORL'
- 3. Grimes [-
ReactorProjectD]r,%
FROM :
anch No. 3, DRL
SUBJECT:
SCC?E OF IETROPOLIT!d EDISCN RI'lI'~l Jo-Aff The attached outline indicates the scope of the Metropolitan Edison review as discussed at the August 7, 1967 meeting with Dr. Morris, R. Boyd, S. Levine, D. Skovholt, and B. Grimes. The asterisked items on the outline indicate areas in which Reactor Technology has agreed to provide assistance.
More detailed requests were previously transmitted te the apprcpriate RT branch chiefs by buck slips dated July 10, 1967 (copies attached).
Item 2.1.5.8, " Simultaneous Earthquake and Accident," was added to the list as a result of the meeting.
It was indicated that the ef fect of such a design basis on the reactor design would be investigated and although not yet a requirement, we are inclined towcrd adopting this as a design basis.
It was decided that a response to each of the 70 criteria would not be requested but that a general response would be sought and any dif ferences detailed.
D. Skovholt's group will be consulted during the review to initiate consideration of organization and training of the utility staf f at an early date, particularly in the middle management level.
Dr. Morris indicated that thought should be given to better defining the objectives of the technical specifications at the construction permit stage so that these will be part of the design objectives.
Attachment ec:
ERL Reading R?3 d3 Reading Technology Br. Chie fs S. Levine R. S. Beyd D. J. Skovholt D. F. Ross RP 3 ranch Chief:
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L Buy U.S. Savings Bonds Regularly on the Payroll Savings Plan
s METRCPCLITAN TOISCN CCID.V??
.THREE MIL 2 ISLAND The follcuing areas will be given specific attention in the revie*e of the Metropelitan Edison application.
1.0 SITE
- 1.1 Hydrolegy
- 1.1.1 Ef fluent Release Limits (many reactors on river) 1.1.2 Accidental Release of Liquid Ef fluent 1.1.3 Meeting with our Hydrology Consultants may be Required 1.2 Design of Dams (Consequences of Loss of Dam)
- l.3 Meteorology 1.4 Geology 1.4.1 Foundation Conditions 1.4.2 Exact Location of Structures 1.5 General 1.5.1 Estimate of Future Population Density for 40 Years 1.5.2 Significance of Airpc-t Locations Near Site
- 2.0 CC : TAI!aEST 2.1 Schauer's Questions and Newmark's questions Includin3:
- 2.1.1 Loading Combinations
- 2.1.2 Design of Structures
- 2.1.3 Materials and Construction 2.1.3.1 No Tack '4elding Should be Ocne on A-431 cr A-432 2ebars
- Items carked are the areas where a rec,uest has been made fer assistance from RT.
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- 2.1.4 Testing and In-Service Surveillance 2.1.4.1 Liner Ncndestructive Testin; 2.1.4.2 External Visual Inspection at Desige ?ressure of Ccepicted Structurc 2.1.4.3 Groutin; of Tendens and In-Service Inspection 2.1.5 Earthquake Design 2.1.5.1 Inconsistency in Earthquake Acceleratien Values 2.1.5.2 Golden Gate Spectra is not Apprepriate 2.1.5.3 Same Da ping Values for Design and Maximum Earthquake?
2.1.5.4 Shear Values Require Clarification 2.1.5.5 Piping Seismic Design Needs Amplificatier 2.1.5.6 Crane Design Detail Required
- 2.1.5.7 Simultaneous F rthquake and Accident 2.2 Turbine Missile Analysis (bring up-to-date with Duke) 2.2.1 How Criteria will be Fulfilled on Protection of Contr:1 Room and Feedwater Scurce 2.3 Penetration Design 2.3.1 Advantage and Testability of Fluid-310ck System
- 2.4 Isolatien valve Criteria Including Ste = Line Isclatien "alves 3.0 STE.0! SYSTEM DESIGN 3.1 Reactivity Balances 3.1.1 Accuracy of Calculation 3.1.2 Shutdcun Mar;in during Transients 1450 003
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3.2.2 Lcw Cycle ratig;e Life 3.3 Schadule en Thermal Oeci~r 3.4 Control 2cds 3.4.1 Occument Tests ?erformed to Cate 3.4.2 Occu=ent Improvements and Oif ferences frca ?ravicus Rack and ? inion Eesigns 3.4.3 Document Test of Orop of Assembly into Fuel Element with nc Oeceleration 3.4.4 Consequences of Loss of Seal or Vent:
- 3.5 Centrol and Instrumentation
- 3.5.1 Should there be an Autc=atic Reduction of Feedwater Flow or Scras on Low Te=perature?
- 3.5.2 Should High ?ressure Injection Start Coincident with Scram for Certain Conditions?
3.5.3 Look at Feasibility of Splittin; Control Red Hus
- 3.5.a Oiversity in En~ineered Safeguard Si nals a
a 3.6 leactor Vessel 3.6.1 Look into New " icceptance Tests bein; Ocr.s_Jered for Vessel Plate 3.7 Energency ?cwer
- 3.7.1 Design of System 3.7.2 ledundancy in Emergency Fecdwater Supply 3.7.3
' Jill Emergancy Power be Encush to Orive :endens 2>.e 2cester ?crpc.
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- 5.3 I; Siphonin; ? ssible anc *..ill The Check 'Jalves Serv a2 2 Siphon 3re2h 5.4 Policy on valvin~ Cff ?.ccumulaters
- 5.3 Cold,*2ter Injection Ther 21 Tr ont 5.3.1 Ectails of Calculatio:
5.5.2 ixperinental Information on Crack Propagation 5.6 Need for Autocatic Isolation of Hi~ah ?ressure Injection syster in Case of High Pressure Injection Line Break 5.7 Frelininary resign of Containment Cool 2:s
- 5.8 Iodine Removal Capability of Spray
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