ML19350C164
| ML19350C164 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/23/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8103310377 | |
| Download: ML19350C164 (4) | |
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March 23, 1981_
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4 Docket No. 50-368 2
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T MAR 2 71981*
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Mr. William Cavanaugh III Ds Senior Vice President V
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Ensrgy Supply Department kiTT Ar4ansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
The Reactor Physics Section of the Core Performance-Branch has reviewed your February 20, 1981 submittal en the ANO-2 Cycle 2 reload and has icintified a need for additional information as set forth in the enclosure.
? lease contact us if you have questions regarding the items noted in the encicsure.
Sincerely, w
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Robert A. Clark, Chief Operating Reactors Branch Division of Licensing
Enclosure:
's stated ic: See'next page 9
8'108.810I??
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Arkansas Power & Light Company CC; Mr. David C. Trimble Director Criteria and Standards Division Manager, Licensing Office of Radiation Programs (ANR-460)
Arkansas Power & Lignt' 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 -
Regien VI Office General Manager ATTN: EIS COORDINATOR Arkansas Nuclear One 1201 Elm Street P. O. Box 608 First International Building Russellville, Arkansas 72801 Dallas, Texas 75270-Mr. _ Robert B. Borsum Babcock 6 Wilcox Nuclear Power Generation Division Suite 420 7735 Old Georgetown Road Director, Bureau of Environmental Bethesda, Maryland 20014 Health Services 4815 West Markham Street.
Nick Reynolds Little Rock, Arkansas 72201 c/o DeBevoise & Liberman
- 1200 Seventeenth Street, N.W.
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- Washington, D. C.
20036 Arkansas Pclytechnic College
. Russellville, Arkansas 72801
' Honorable Ermil-Grant-Acting County Judge of Pope County.
Pepe County Courthouse Russellville, Arkansas 72801 Mr. Paul F. Levy, Director Arkansas Department of Energy 3000 Kavanaugh Little Rock, Arkansas 72205' Mr. Charles B. Brinkman -
Manager - Washington Nuclear Operations C-E Power Systems
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. 4853 Cordell Avenue, Suite A-1 Bethesda,. Maryland 20014 9
2AR I 9 I3SI REQUEST FOR ADD 1T10NAL TNFORMAT10N ARKANSAS NUCLEAR ONE, UNIT 2, CYCLE 2 RELOAD (TACS 12078)
Review of the applicant's submittal dated February 20, 1981 on the Arkansas Nuclear One, Unit 2, ( ANO-2) Cycle 2 reload analysis report showed that more information is required for an adequate safety evaluation. The s;5.'s:t report deals, an:ng other things, with fuel system design, nuclear design, reactor protection and monitoring system, and the design and effect of 00E test assemblies. Transient analysis and Technical Speciff-cation changes will be reviewed at a later date. The following general ccm ants can be made:
(a) The Cycle 2 reload was designed similar to Cycle 1, hence, the analysis relies heavily on a comparison of two cycles.
(b)
- n numerous instances adequate detail or justification of conclusions is missing.
A number of specific questions have been brought forth in the review and the folloning additional information is required:
1.
-(Paragraph 5.2.2) For the limiting dropped CEA show the actual Cycle 2 calculated values of the reactivity worth and radial peaking factor shown in Table 5-5.
2.
.(Paragraph 5.3.3.1) Regarding the use of the ROCS coarse mesh neutronics code give some typical examples of how and where it was used and the results obtained.
(?aragraph 5.3.3.2) DIT cross sections reportedly "substantially improved" 3.
the ROCS calculational result agreement with measurement on reactivity,
- cwer distribution, rod worths' and reactivity coefficients. Provide some examples of. the improvements ment'ioned in the cited paragraph.
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2 4.' (Paragraph 10.3) It is not intuitively obvious that the annular
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pellets will have lower local peaking factors or that they will not impact neighboring rods. Provide explicit physics calculaticns to prove the assertions of this paragraph.
5.
(Paragraph 10.3) Provide typical values of the icpact en power peaking caused by the. presence of the non-fuel region of the segmented fuel rods.
6.
Fuel misloading analysis has~ not been presented.
When such analysis is t baitted include analysis for pos[5fon and
( a) orientation misloading.-
(b) Has ANO-2 developed ~ procedures to avoid misloading and misorientation?
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