ML20003J255
| ML20003J255 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/29/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8105110119 | |
| Download: ML20003J255 (3) | |
Text
.
h0SY g
A
\\
i APR 2 ) El re C
Docket No. 50-368
- eGWg
? I'M Y 0 5 19 b h' Mr. William Cavanaugh III O u.S Q
- h D,. b q0/
Senior Vice President Energy Supply Department p'.
k kansas Power & Light
/f P. O. Box 551
~
Little Rock, Arkansas 72203
Dear fir. Cavanaugh:
The Reactor Physics Section of the Core Perfomance Branch has reviewed your March 5,1981 submittal on the ANO-2 Cycle 2 reload and has identified a need for additional information as set forth in the enclosure. This '
infomatico is supplementary to that identified in our letter dated Febraury 20, 1981.
Please contact us if you have questions regarding the items noted in the enclosure.
Sincerely, Orig;nal signed by Robert A. Clark Robert A. Clark, Chief Operating P.eactors Branch #3 Division of Licensing
Enclosure:
DISTRIBUTION:
As stated CFocket Fil O l
NRC PSR cc: See next page L POR NSIC l
TERA l
OR8#3 Rdg DEisenhut OELD I&E (3) l ACRS (10)
JHeltemes t
Gray File RAClark PMKrcutzer (3)
RMartin l
" ' 05110 ll9
?j
.f.>'$l88&r'jfdk$E$k l
- ) 4/;1/81 JFg81
'4/:q/81
.<;-:<s3 i :..: :.. ;
c, iC!.A L R I C O R C CC
-+
/
'o UNITED STATES
- h. s *,* f [,j NUCLEAR REGULATORY COMMISSION p.
g WASHINGTON, D. C. 20555
,y
,s y
%; + o y APR 2 S 381 Occket No. 50-368 Mr. William Cavanaugh III
~
Senior Vice President Energy Supply Department Arkansas Pcwer & Light P. O. Sox 551 Little Reck, Arkansas 72203
Dear Mr. Cavanaugh:
The Reactor Physics Section of the Core Performance Branch has rev'iewed your March 5, 1981 submittal on the ANO-2 Cycle 2 reload and has identified a need for additional infor11 tion as set forth in the enclosure. This' information is supplementary to that identified in cur letter dated February 20, 1981.
Please centact us if you have questions regarding the items noted -in the enclosure.
Sincerely, 0&Yb,Yh~
Robert A. Clark Chief Operating Reactors Branch #3 Divisien of Licensing
Enclosure:
As stated cc: See next page 4
t L
~
Arkansas Power & Light Company cc:
Mr. David C. Trimble Director Criteria and Standards Division Manager, Licensing Office of Radiation Programs ( ANR-460)
Arkansas Power & Light Company U.S. Environmental Protection Agency P. O. Box 551 Washington, D. C.
20460 Little Rock, Arkansas 72203 U.S. Environmental Protecticn Agency Mr. James P. O'Hanlon Region VI Office General Manager ATTN:
EIS CCORDINATOR Arkansas Nuc' ear One 1201 Elm Street P. O. Box 608 First International Building Russellville, Arkansas 72801 Dallas, Texas 75270 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420 7735 Old Georgetown Road Director, Bureau of Environmental Bethesda, Maryland 20014 Health Services 4815 Wes't Markham Street Nick Reynolds Little Rock, Arkansas 72201 c/o DeBevoise & Liberman 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Arkansas Polytechnic College Russellville, Arkansas 72801 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Mr. Cnaries B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems 4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014 4
9
i REQUEST FOR ADDITIONAL INFORMATION ARKANSA5 NUCLEAR ONE, UNIT Z, CYCLE 2 RELOAD (TACS 12078)
Review of the applicant's submittal dated Parch 5,1981 en the A-kahsas Nuclear One, Unit 2, ( ANO-2) Cycle 2 reload analysis report showed that more information is required for an adequate safety evaluation.
This information is in addition to that requested on March 19,1981 and
, pertains to Trsnsient Analysis and Technical Specifications.
The an'alysis submitted is hredicated on an acceptable value of minimum DNBR The analysis supporting this value has been submitted and is being of 1.24.
reviewed separately.
A number of specific questions have been brought forth in the review and the following additional information is required:
The values of the moderat r te perature coefficient (MTC) given in Table 1.
Give 7-2 are extremes that bound the second and future cycle analysis.
typical expt..ad values of the MTC for 20C and EOC for full and zero power.
In the analysis of the feedwater line break the moderator temperature 2.
coefficient is assumed to be zero as opposed to a positive value in the FSAR analysis.
Is this value ennservative?
(
3.
Technical Specification changes 16, 50, 51, and 52 are related to an increase of the shutdown reactivity margin from 15 6K/k to St AK/k to lengthen the available time for operater action. Give more details on the particular considerations which necessitated this change.
4 Technical Specification chang,es 53, 54, and 55 are related to the introduction of the pianar radial peaking factor F in Technical XY Specification change No. 6.
Provide the data base and uncertainty analysis which led to the 1.053 uncertairty factor for F XY 5.
Note, in technical specification change No.17 change "then" to "than" in a, b, and c.
}
G F
e