ML19256F849
| ML19256F849 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, Bellefonte, Crane  |
| Issue date: | 12/05/1979 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Scott S NRC OFFICE OF ADMINISTRATION (ADM) |
| Shared Package | |
| ML19256F850 | List: |
| References | |
| NUDOCS 7912260309 | |
| Download: ML19256F849 (3) | |
Text
'
o, UNITED STATES EI)
NUCLEAR REGULATORY COMMISSION NRC PUBLIC 2, p[,gJ( 7,g DOCUMENT ROOM g
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%O DEC 51979 Docket No. 50-289 MEMORANDUM FOR:
Steve Scott, Acting Chief Distribution Services Branch, ADM FROM:
Richard H. Vollmer, Director Three Mile Island Support
SUBJECT:
THREE MILE ISLAND UNIT 1 BOARD NOTIFICATION 10 CFR 50.54 REQUEST REGARDING DESIGN ADEQUACY OF BABC0CK AND WILC0X NSSS Please forward the enclosed material to the Three Mile Island Unit 1 Board Notification Service Listings. The material is an October 25, 1979, letter signed by H. R. Denton and an evaluation of the letter.
h
' Richard H. Vollrier, Director Three Mile Islaad Support
Enclosure:
As stated cc w/ enclosure:
R. Vollmer J. Collins J. Tourtellotte M. Mulkey G. Mazetis D. Ross H. Silver
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EVALUATION OF THE ENCLOSED'PATERIAL It is the staff's judgment that the enclosed material is relevant to the scope of the proceedings before the ASLB.in the matter of the restart of Three Mile Island Nuclear Station, Unit 1.
The enclosed material (October 25, 1979 letter, from H. R. Denton to the Tennessee Valley Authority) requests information concerning the sensitivity now under construction to feedwater transients of the Bellefonte Nuclear Plar.:
which has a Babcock and Wilcox nuclear steam supp'.y syste.
Similar letters have been sent to all utilities holding construction permits The for plants with a Babcock and Wilcox nuclear steam supply system.
request for information is directly related to the lov wa er inytntory a,nd the presence of a liquid-vapor interface in the B5W once-through steam generator which closely couples the primary system to the st ?am generator conditions with a consequently high sensitivity to feedwater flow rate perturbations.
The additional information being requested from holders of construction permits will allow a determination by the staff whether it is necessary to halt all or portions of the construction of the affected plants pending the results of an ongoing staff study.
The staff has a' study now underway, using Crystal River, Unit 3 an operating facility with a B&W nuclear steam suopiy system, as a reference The objective of this study is to ide.tify accident sequences facility.
leiding to core damage having nigh frequency cc :ared tc the Reactor Safety Study (WASH-1400).
The study uses eve":
ree a-t faul-tree 1 0 l0 0 *D S
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M MUM}'lAL 1638 287 te c hr.i que s.
D
-2 This assessment to be completed in about 6 months will focus on the risk ix.plications of the sensitivity of the B&W design and on the potential interactions arising from the integrated control syster..
1638 288
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