ML19326D045
| ML19326D045 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/08/1968 |
| From: | Jewell W HOUSE, HOLMES & JEWELL |
| To: | Bond J, Briggs R, Wells A Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8004300666 | |
| Download: ML19326D045 (3) | |
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DOCKEf NUMBE;I ER00. & UIIL, FAc[ 5'O-3 I'3 m
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H Ce tlS E, H O LM ES & J EWELL
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' Two#eAS C. T.f M.kC, J.,
TQwCR SulLDING "d"f"o".i.U"o" s E
^"""" 888 (MA.Les J. uncotn LITTLE ROCK ARKANSAS 72a oe DA.. ELL D.COvt.
October 8, 1968
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. Algie A.. Wells, Esq.
Dr. John C. Geyer, Chairman Chairman, Atomic Safety and Department of Sanitary Engineer-Licensing Board ing and Water Resources U. S. Atomic Energy Commission The Johns Hopkins University Washington, D. C.
20545 Baltimore, Maryland 21218 J. D. Bond, Esq.
Dr. Lawrence R. Quarles Office of the Hearing Examiner U. S. Atomic. Energy Commission Dean, School of Engineering and Applied Science Washington, D. C.
20545 University of Virginia Charlottesville, Virginia 22901 Mr.
R.' B. Briggs, Director Molten-Salt Reactor Program Oak Ridge National Laboratory P. O. Box Y Oak Ridge, Tennessee 37831 In the Matter of Arkansas Power & Light Company Russellville Nuclear Unit Docket No. 50-313 Gentlemen:
As a result of printing errors, pages 20 and 21 of the Applicant's summary of the Application mailed to you, September 28 omitted some material and included erroneous statements.
We apologize and enclose herewith corrected pages.
Please substitute these revised pages in your copy of the summary.
Sincerely yours,
[L/.
WO v.6 D
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WHJ/cb W. Horace Jewe s
890aE:ED J
Thomas F. Engelhardt, Esq.
cc:
1 Algie'A. Wells, Esq.
OCT11 19033 '9 Roy B. Snapp, Esq.
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can.n Mr. Stanley T. Robinson, Jr. (30 copies)
Honorable Winthrop Rockefeller g
M(.l,;
s/f Honorable Wayne Nordin
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Dr. J. T. Herron
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1 design pressure.
Periodic leak rate tests will be performed 2
to assure integrity at the reactor building.
A tendon sur-3 veillance capability will be available to provide assurance 4
that the tendons are free from harmful corrosion and that 5
excessive steel relaxation has not taken place.
6 3.4 Engineered Safeguards 7
Engineered safeguards are provided to fulfill the 8
following functions in the unlikely event of an accident:
9 a.
Minimize the release of fission products from the 10 fuel to the reactor building atmosphere 11 b.
Ensure reactor building integrity and reduce the 12 driving force for building leakage 13 c.
Remove fission products from the reactor building 14 atmosphere.
15 The engineered safeguards systems can be grouped into 16 an emergency core cooling system, reactor building cooling 17 systems and fission products control systems.
18 The emergency core cooling systems contain both passive 19 flooding and pumping equipment.
The passive flooding 20 equipment consists of two pressurized core flooding tanks 21 which automatically discharge borated water into the 21 Revised 10-7-68
g_
1 thickness, to provide vapor tightness.
The foundation mat 2
aill be bearing on rock and will be approximately 9 feet thick.
3 The building is designed to sustain safely all internal 4
and external loading conditions which may reasonably be 5
expected to occur during the life of the e,.: ion or which 6
could result from the postulated design base accident to the 7
reactor's primary coolant system.
The tendon system used in 8
the structure is of the unbonded type with a protective 9
compound used to prevent corrosion.
Prior to construction, 10 a test will be conducted on the liner plate anchorages to 11 verify certain factors of design analyses.
12 The reactor building is so designed that, with the 13 engineered safeguards systems provided, any leakage of 14 radioactive materials to the environment will result in 15 doses well within AEC's 10 CFR 100 guidelines for any of 16 the postulated accidents.
The integrated leak rate at 17 design pressure will not exceed two-tenths of one percent 18 by volume, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
19 Prior to operation, the reactor building will be sub-20 jected to a structural integrity test and leak rate test.
21 The structural integrity test will be conducted at 115% of 20 TRmduaedouot