ML20128D865
| ML20128D865 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Oyster Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick |
| Issue date: | 10/22/1975 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Heineman R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9212070406 | |
| Download: ML20128D865 (3) | |
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OCT t 21973 R. H. Heinoman, Director, Division of Technical Review e
TECIDi! CAL ASSISTANCE REQUEST NO. ORB-3-105
..f Your assistance is requested in the following:
PIMT NAMES: Oyster Creek Nucient Generating Station, Nine Milo Point Unit 1, Pilgrim 1, Dresden Units 2 and 3, Millstono Unit 1, Quad Cities Units 1 and 2, Monticello, Peach Botto:n Units 2 and 3, Browns Ferry Units 1 and 2, Vermont Yankee, llatch Unit 1, Brunswick Unit 2, Duano Arnold Energy Centor, Cooper and Fitzpatrick DOCKET NOS.: 50-219, 5 220, 50-237, 50-245, 50-249, 50-254, 50-259, 50-260, " -263, 50-265, 50-271, 50-277, 50-278, 50-293, 50-298, 50-324, 50-331, 50-321, and 50-333 l
RESPONSIBLE BRANCil: Operating Reactors Branch #3 (ORB-3) j CONTACT:
h' alter A. Paulson (ext. 7872)
TECID11 CAL REVIEW BRANCllES: Containment Syste:as Dranch Structural Engineering Dranch, Mechanical Engineering Branch
'L TARGET COMPLETION DATE: December 5, 1975 1
DESCRIPTION OF REQUEST: Background i
During testing of the !brk III pressure suppression containment concept, the General Electric Company identified hydrodynamic ~ loads that were not considered in the design of the !! ark I contain-ment.
In response to our letters of February 15, 1975, and April 17, 1975, identifying our concerns regarding the Mark I containment, the i
licensees of these plants have initiated a j
progran to demonstrato that the I' ark I containment design margins are adequate to withstand the newly identified loads in addition to the loads originally considered in the design. The program consists of two phasos. The purpose of the first phase, tormed the " Mark I Short Term Program" was to verify whether the Mark I containments can withstand the most probable loads induced by a loss of coolant accident.
The second phaso, termed the " Mark I Long Term Program", will develop design basis loads based i
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a R. E. Ilsineman on tha 1 stost pool dynamic information and will assess whether the >hrk I containments are capable of sustaining these loads.
In. addition, loads induced by the actuation of safety / relief valves will be addrossed in the long term program.
The short term program has been completed.
On October 15, 1975, we received the short tern program final report (submitted by CE
'g by letter dated October 6, 1975). This final report consists of the following:
Voluas I
- Program Description and Summary A
of Conclusions, NEDC-20989 Volume II
- LOCA-Reinted llydrodynanic Loads, NEDC-20989-2P Volume III
- Load Application and Screening of Structural Elements, NEDC-20DS9-3P l
Volumo IV
- Structural Evaluation, NEDC-20989-4P Volume V
- Independent Assessment of the Mark I Short-Term Program,-
The licensoes that have operating plants with
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thrk I containments have r3forenced.the above report as justification for their conclusion that continued operation during the long term i
program will not endanger the health and safety of the public.
In addition, the licensees have transmitted,- by letter, a summary of their -
4 proposed long term progran which is now scheduled to be-complotod at the end of the second quarter of 1977.
Request for_ Assistance We request that you review the Mark 1 Short Term'-
Program Final Report and provido a' written evaluation of the adequacy of the justification for continued operation of.the plants with.
!!arh I containments. Your evaluation should include a determination as to whether continued-operation of those plants _will not endanger the health and-safety of the public.
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R. I!. !!sinoman '
In addition, we request that you review the proposed long term program and provide a written "j
ovaluation of tha adequacy of the progra.s.
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h The above referenced submittals have been distributed to the Technical Review Branchos
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j involved.
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l, Georgo Lear, Chief Operatint, nesctors Branch #3 l
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I Division of Reactor Licensing 1
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W. Paulson DISTRIBtTTION:
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T. J. Carter ORB-3 Reading 3
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