ML19221A651
| ML19221A651 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/04/1979 |
| From: | Milstead W Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7905240245 | |
| Download: ML19221A651 (53) | |
Text
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NUCLEAR REGULATORY COMMISSION
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MEMORANDUM FOR:
D. Crutchfield, Chief, Technical and Administrative Support Branch, Program Support Staff, NRR FROM:
W. Milstead, Containment Systems Branch, DSS
SUBJECT:
RECORD 0F ACTIONS - THREE MILE ISLAND ACCIDENT The attached April 25, 1979 memorandum to R. L. Tedesco from W. R. Butler summarizes communications and calculations which Messrs. Butler, Shapaker, and Milstead participated regarding the TMI-2 accident during the early period of March 28 through April 15, 1979.
I have also attached the originals of ray notes and calculations during this time period. My actio'is in regard to the TMI-2 accident since April 9,1979 have been conducted through the DSS Technical Support Team and are thus documented in the minutes of team meetings and advisorys issued by the team.
Details of pertinent conversations, ca~tculations, etc. supporting team activities are contained in the CSB official log which is maintained by John Kudrick and myself.
Please, advise J. Kudrick or me if you desire a copy of the CSB " log b E w
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William C. Milstead, Jr Containment Systems Br ch Division of Systems Safety
Enclosures:
As stated cc: w/o encls.
w/encls.
J. Kudrick W. Milstead J. Shapaker W. Butler R. Tedesco f 0hf 166 191 l
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APR 2 51979 MEMORANDUM FOR:
R. L. Tedesco, Assistant Director for Reactor Safety, DSS FROM:
W. R. Butler, Chief, Containment Systems Branch, DSS
SUBJECT:
THREE MILE ISLAND, UNIT 2: ANALYSIS AND EVALUATION OF SELECTED CONTAINMENT RELATED ISSUES The purpose of this memorandum is to document the results of analyses and evaluations performed by the Containment Systems Branch for several containment-related issues in support of the incident response team.
As evidenced by the following discussion, the primary concern with respect to the containment centered around:
1) the potential sources of and rates of hydrogen and oxygen production within the reactor vessel and c7ntainment building; 2) the potential for and effects of explosion or detonation af hydrogen within the reactor vessel and containment building; and 3) methods for collection and recoctination of hydrogen.
A small effort was also expended in the evaluation of minimum allowable containment pressure when considering the depressurization effects of containment spray cooling.
1.
Reactor Vessel Non-Condensible Bubble On Friday, March 30, 1979, we were asked to perform a best estinate type analysis to determine the possible contents of a reported non-coadensible bubble of about 1000 ft3 in the reactor vessel upper head and the possible sources of the non-condensibles. We were also asked to estimate the projected growth rate of the bubble due to formation of hydrogen and oxygen by radiolysis of core water.
As a basis for the calculation, we performed an analysis with the COGAP computer code (see SRP 6.2.5) with the following assumptions:
a) 1% failed fuel with 10% of the solids and 50% of the halogens from the failed fuel going into the coolant; b) G-values of 0.44 molecules /100 EV in the core and 0.3 molecules /100 EV in the sump solutions; and c) all radiolysis products thus generated were i44 109 contained in the reactor vessel.
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Contact:
W. Milstead, CSB DUPLICATE DOCUMENT Ext. 27711 Entire document previously entered into system under:
OTM MOI ANO No. of pages:
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