ML20024E039
| ML20024E039 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 08/05/1983 |
| From: | Edgar G MORGAN, LEWIS & BOCKIUS, PROJECT MANAGEMENT CORP. |
| To: | Hand C, Linenberger G, Mark Miller Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8308090086 | |
| Download: ML20024E039 (12) | |
Text
i' tu2XfED COf UW.SPONDie.NCh MORGAN, LEWIS & BOCKlu
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Los ANGELES COUN SELORS AT LAW PM LActLPHiA NLw YOmk 1800 M Svartv, N.W.
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,iS H Annissuno WAS HIN GTO N, D.C. 2 O O 3 6 Ts6ae o :taoa) era-sooo 9j S 1933 > l{,
AUG cAEING 4 August 5, 1983 c3 gj.'gq3y GEsRot L. EDGAR nnuca e
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4 Marshall E. Miller, Esquire Dr. Cadet H. Hand, Jr.
Chairman Director Atomic Safety & Licensing Board Bodega Marine Laboratory U.S. Nuclear Regulatory Commission University of California East-West Towers West Side Road 4350 East-West Highway Bodega Bay, California 94923 Bethesda, Maryland 20814 Mr. Gustave A. Linenberger Atomic Safety & Licensing Board U.S. Nuclear Regulatory Commission East-West Towers 4350 East-West Highway Bethesda, Maryland 20814 Re:
Clinch River Breeder Reactor Plant'- Do'cket No. 50-537
~
Gentlemen:
Enclosed are errata sheets for Applicants' prepared testimony (A Exh's 87, 89, and 95) in the above captioned proceedings.
At the evidentiary hearings Applicants will offer versions of Exhibits 87, 89, and 95 which will have the attached errata clearly marked and I
inserted.
f Respectfully submitted, eor L.
dgar Att ey for Project Management Corporation Enclosure GLE:1pn Service List 8309090086 830905 PDRADOCK05000g l
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APPLICANTSDBA TESTIMONY (EXHIBIT 87) ERRATA Page 8 Add a new final paragraph as follows:
In addition to this no-sodium-boiling criterion to. assure core coolability, Applicants have committed to impose a e-
'w quantitative limit related to the degree of internal
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fuel pellet melting for FSAR analyses.
The relationship of the-no-sodium-boiling, fuel melting and other: fuel design criteria are discussed.in Q/A 154.
Q/A 51 discusses the only DBA 3,3.
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which gives rise to fuel s,
melting and itc s
s acceptability.3 In effect, the event does not generate i
i' sufficient molten fuel to s
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prodb~ce significant-l l
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internal fuel ps;essures that would cauce_ cladding 1,,.- [cfailuri and molten fuel y
' ejection.
Thus all other
'k DBA conditions are
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envelopedtby the no-sodium-
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boilihg criterion, as
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disedssed above.-
4
_w Page 33 LinellFt Change ". reach" to " travel i
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from the. evaporators,to"
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Page 38 3rd from'last line Add "at power" af ter "PHTS pumps" '
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. 3 Page 53 Last line Delete "betweensh,at" e
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l Page 54 Line 4 Change tinbalance" to
" i m b a.'y n c e "
3
,s Change "7.1.2"'to "7.1 and Page 56 Line 11 s'
7.2" t;
l Page 59 Table Heading Change "RRS" to "RSS" s
Page 66 Line 8 Change "1300" to "13,000" L
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Page 58 Lines 9, 10
. Replace comma after " power" with period; capitalize
- because*
.Page 81 Line 5 Insert " unacceptable" before " degradation"
'Page 95 Figure 35 Modify per attached mark-up Page 99 Figure 38 Modify per attached mark-up Page 116 Line 6 Change " mills" to " mils" Page 126 Lines 17-19 Revise to read"... wall penetration would occur when the crack length is t
very small..."
(Delete Line 18 entirely.)
Page 140 Line 7 Insert " heat" after'
" generate" Page 165 Line 22 Change "Qalification" to
" Qualification" Page 206 Line 1 Add " Table 6" above "SSST Guidelines and Doses" 4
- Page 206 In the " Low Population
~
Zone". column, change the
" Red Bone Marrow" entry from 1.5 to 0.7 and change x
the " Mortality Risk Equivalent Whole Body Dose" entry from 0.7 to 1.5 i
Page 210 ~
Line 7 Change "zircoloy" to l
"Zircaloy"
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off-site".spower supply consists of four separate connections to the TVA grid as shown'in Figure 35.
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To SMAS ToSHR$
Figure 35. SHRS AC Power Supplies
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The principal on-site power' supplies are three' safety related diesel-generators.
The pony motors of each BTS path and its associated PACC are provided on-site power from a diesel-generator which is separate and independent of t.io diese -generators for the other two paths.
Additional diversity exists because on'e of the three t diesel-generators. is a different size and built by a
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different manuf acturer than the other two.
The design of r
.the,SGABRS electrical equipment and the power supply b
equipment, including the diesel generators, is of proven 7
technology, asemonstrated by service,,in light w'ater reactor s
s plants.
SGABRS mechanical equipment is cafety-related, of l.4 proven design,. designed to the ASME code for nuclear t
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activities are planned to support further refinement of 9
the model.
Further details of the natural circulation verification program are provided in PSAR Section 5.7.5.
Q88.
What are the implications of establishing natural circulation capability for CRBRP?
A88.
By using this natural circulation capability, along with the turbine-driven Afw pump with battery powered instrumentation and control, SHRS capability can be maintained even in the event of loss of all off-site power and loss of all three on-site diesel-generators (station blackout).
Figure 38 summarizes the plant provisions for mitigation of station blackout.
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SD 2 50 (Dp I 3b o s
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1 Figure 38. CRBRP Prova um so m.ugate Station Blackout Q89.
What inherent characteristics of CRBRP contribute to a high SERS reliability?
4
1 APPLICANTS ' HCDA TESTIMONY (EXdIBIT 89) ERRATA Cover Sheet Last line Delete " Corporation" Page 37 Lines 12,13 Revise to read "... in CRBRP-3, Volume 2 as itemized below:
Page 37 In the " Reference" column, delete "(Section of CRBRP-3, Volume 2 unless noted otherwise)"
Page 38 Line 6 Revise to read " Appendix G.2 and Appendix K.2" Page 38 Line 14 Delete reference " Note 2",
and replace with " Appendix K.3" Page 38 Lines 15-21 Delete Notes 1 and 2 Page 45 Last line of A45 Add "For containment penetrations, the limiting penetration is the equipment hatch, which is limited by buckling.
Application of ASME Code Case N-284 showed that the pressure capability of the equipment hatch is comparable to the capability identified in Table 3-10 noted above.
The pressure capability of containment and penetrations will be reassessed at the Operating License review stage."
Page 59 Lines 3-6 Delete "(Letter, John R. Longenecker...
October 20, 1982).
Replace with " (CRBRP-3, Vol. 2.
Appendix K.2). "
Page 93 Line 5 Change "inact" to " intact" Page 110 Lines 4-7 Delete the sentence "For the EOC-4 core, IB... at the core mid-plane."
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Page 113 Note 40, line 2 Chknge "1956" to "1950" Page 117 Table 2 heading Change "BOC" to "BOC-1",
Change "EOC" to "EOC-4" Page 121 Line 14 of conclusion Change "an" to "a" Page 135 Next to last line Change "TI-033-120-130" to "TI-001-130-025" Page 140 Line 2 of reference 2 Change "1975" to "1972" g
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APPLICANTS' RESPONSE'TO' BOARD AREAS OF INTEREST 5 AND 6 (EXHIBIT 95) ERRATA Page 13 Lines 1, 2 Delete "on Page 12",
replace with "below"'
Page 16 Line 1 Insert "a" before " system" Page 24 Line 23 Insert comma after
" requirements" Page 24-last line Add " assembly" after "and" Page 26 Line 2 Insert comma after
" finally" Page 26 Line 10 Insert comma after
" instructions" Page 28 First paragraph, Change " owner" to " Owner" line 9 Page 30 Line 3 Change " programs" to
" activities" Page 31' second paragraph, Change "in" to "at" line 5
_ Page 32 Line 3 Insert comma af ter "ORNL" Page 32 Line 13, 14 Change " quality assurance program to " Quality 1
Assurance Program"
(
Page 32 Line 15 Change " owner" to " Owner" Page 32 Line 19 Change " project quality assurance program" to
" Project Quality Assurance Program."
Page 32 Line 22 Change " owner" to " Owner".
Page 32 Line 23 Change " project quality assurance program." to
" Project Quality Assurance Program."
Page 34 First paragraph',
Change " January 1980" to line 1
" April 1983" e e e
A S 4 s
Page 34 First paragraph, Add after "to the Project."
line 7 the sentence "From January 1980 to April 1983, I held this position in an acting capacity."
Page 35 Line 18 Change " Project" to
" Project" Page 35 Line 20 Change " Project" to
" Project"
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a.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD i
)
In_the Matter of
)
)
UNITED STATES DEPARTMENT OF ENERGY
)
)
PROJECT MANAGEMENT CORPORATION
)
Docket No. 50-537
)
TENNESSEE VALLEY AUTHORITY
)
)
(Clinch River Breeder Reactor Plant)
)
)
CERTIFICATE OF SERVICE Service has been effected on this date by personal delivery or first-class mail to the following:
Marshall E. Miller, Esquire Chairman l
Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission I
East-West Towers 4350 East-West Highway Bethesda, Maryland 20814 (2 copies by hand)
Dr. Cadet H. Hand, Jr.
L Director l
Bodega Marine Laboratory University of California West Side Road Bedega Bay, California 94923 (Air Express)
Mr. Gustave A. Linenberger Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission East-West Towers 4350 East-West Highway Bethesda, Maryland 20814 (by hand) w
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' Stuart Treby, Esq.
Sherwin E. Turk, Esq.
Elaine I. Chan, Esq.
Geary S. Mizuno, Esq.
Office of Executive Legal Director U. S. Nuclear Regulatory Commission Maryland National Bank Building 7735 Old Georgetown Road Bethesda, Maryland 20014 (2 copies by hand)
- Atomic Safety & Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555
- Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C.
20555
- Docketing & Service Section l
Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C.
20555 (original, 3 copies, and return copy)
William M. Leech, Jr., Attorney General William B. Hubbard, Chief Deputy Attorney General Michael D. Pearigen, Assistant Attorney General State of Tennessee i
Office of the Attorney General 450 James Robertson Parkway Nashville, Tennessee 37219 Oak Ridge Public Library Civic Center i
Oak Ridge, Tennessee 37830 Herbert S. Sanger, Jr., Esquire l
Lewis E. Wallace, Esquire W. Walter LaRoche, Esquire James F. Burger, Esquire Edward J. Vigluicci, Esquire Office of the General Counsel Tennessee Valley Authority 400 West Summit Hill Drive l
Knoxville, Tennessee 37902 (2 copies) c l
1
Lawson McGhee Public Library 500 West Church Street Knoxville, Tennessee 37902 William E. Lantrip, Esquire Attorney for the City of Oak Ridge Municipal Building Post Office Box 1 Oak Ridge, Tennessee 37830 Leon Silverstrom, Esquire William D. Luck, Esquire U. S. Department of Energy 1000 Independence Avenue, S.W.
Room 6B-256--Forrestal Building Washington, D. C.
20585 (2 copies by hand)
Commissioner James Cotham Tennessee Department of Economic.
and Community Development Andrew Jackson Building, Suite 10007 Nashville, Tennessee 37219 ddMs l
George L.
arV 7 Attorne r
Proj ect anagem Corporation DATED:
August 5, 1983
- /
Denotes hand delivery to 1717 "H" Street, N.W., Washington, D.C.
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